Text

American Society of Mechanical EngineersSection XI, Inservice Inspection and Repair and Replacements Programs - Summary Reports for Cycle in Operation
	ML021980176
Person / Time
Site:	Browns Ferry
Issue date:	07/09/2002
From:	Abney T; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML021980176 (170)
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{{#Wiki_filter:Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 July 9, 2002 u.s. Nuclear Regulatory Commission ATTN: Document Control Desk Mail stop OWFN, Pl-35 Washington, D.C. 20555-0001 Gentlemen: In the Matter of Tennessee Valley Authority Docket No. 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE INSPECTION (lSI) AND REPAIR AND REPLACEMENTS PROGRAMS -

SUMMARY

REPORTS FOR CYCLE 10 OPERATION In accordance with paragraphs IWA-6220 and IWA-6230 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, 1989 Edition (no addenda), TVA is submitting the BFN Unit 3 outage summary reports for NRC review. The summary reports are for inservice inspection (NIS-I Report), and repair and replacement activities (NIS-2 Report) for Unit 3 Cycle 10 operation. In addition, TVA is submitting a NIS-2 report that was inadvertently omitted from the Unit 3 Cycle 9 NIS-2 slmmary report. That report was transmitted by TVA letter dated July 31, 2000. TVA has determined that certain welds had nondestructive examination (NDE) coverage limitations (less than 90 percent coverage completed) which exceeds that specified in AS ME Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds, Section XI, Division I." The components are 10 Reactor Pressure Vessel (RPV) nozzles (ASME Section XI Code Category B-D, Nozzle-To-Vessel Welds) which had calculated NDE examination coverage ranging between 70 and 77 percent completed. The limitations encountered during the performance of the ultrasonic (UT) examination were caused by component Printed on recycled paper

u.s. Nuclear Regulatory Commission Page 2 July 9, 2002 configuration. The nozzle contours limit the accessible UT examination volume. As a result, TVA will submit a revision to request for relief 3-IS1-7 to address the reduced NDE examination coverage for these components. TVA submitted request for relief 3-IS1-7 for UT examination coverage limitations for other Unit 3 RPV (ASME Section XI, Category B-D) nozzles by letter dated March 26, 1999. NRC accepted TVA's request for relief 3-IS1-7 by letter dated August 2, 1999. There is also one austenitic stainless steel piping weld (DRHR-3-21) where examination coverage was limited to one side of the weld. The weld is Category R-A (ASME Code Case N-577, "Risk-Informed Requirements for Class 1, 2, and 3 Piping, Method A," N-577-2500 Table 1). This weld received greater than 90 percent examination coverage per the requirements of AS ME Section XI. However, 10 CFR 50.55a(b) (2) (xv) (A) restricts taking credit for "one-side" examinations without completing a single-sided ASME Section XI, Appendix VIII Demonstration using flaws on the opposite side of the weld. At this time, no Performance Demonstration Initiative Program exists for single-side austenitic welds. Consequently, only 50 percent examination coverage was achieved. TVA will submit a request for relief to address the reduced examination coverage for this weld. of this letter contains the BFN Unit 3 Inservice Inspection Summary Report (NIS-1) for Code Class 1 and 2 pressure retaining components and their supports. contains the Repair and Replacements Summary Report (NIS-2) for Code Class 1 and 2 components and supports. provides the NIS-2 report for the RWCU system that was inadvertently omitted from the BFN Unit 3 Cycle 9 NIS-2 Summary Report.

u.s. Nuclear Regulatory Commission Page 3 July 9, 2002 If you have any questions regarding these reports, please contact me at (256) 729-2636. ~rY' T. E. Abney Manager of Li and Indus ry Enclosures cc: Enclos~~~~ __ Mr. Paul Fredrickson, Branch Chief u.s. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, S.W., Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Browns Ferry Nuclear Plant P.o. Box 149 Athens, Alabama 35611 Mr. Kahtan Jabbour, Senior Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739

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ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), SECTION XI, INSERVICE INSPECTION (lSI), AND AUGMENTED EXAMINATIONS PROGRAM

SUMMARY

REPORT (NIS-1) FOR UNIT 3 CYCLE 10 OPERATION (SEE ATTACHED)

BFN 'UNIT 3 CYCLE 10 REFUELING OUTAGE NIS-l OWNERS

SUMMARY

REPORT . :.~ &;.-24 RONALD K. GOLUB, MANAGER ~>d~ COMPONENT ENGINEERING 6? TENNESSEE VALLEY AUTHORITY

"'NER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHAIT ANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY N1JCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. UNIT 3 CYCLE 10 NIS-l "OWNER'S REPORT FOR INSERVICE INSPECTION" TABLE OF CONTENTS

OWf;**. -::::; ':;SEE VALLEY AUTHORITY

~t':: OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PLANT P,O. BOX 2000 11 01 MARKET STREET DECATUR, ALABAMA 35609-2000 CHAIT ANOOGA, TENNESSEE 37402 UNIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COrvfMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. APPENDIX I APPENDIX II APPENDIX III APPENDIX IV APPENDIX V APPENDIX VI A IT ACHMENT 1 FORM NIS-l OWNER'S REPORT SCOPE AND INTRODUCTION SCOPE INTRODUCTION lSI

SUMMARY

EXAMINATION

SUMMARY

ASME CODE CASES UNIT 3 INTERVAL STATUS PERSONNEL AND EQUIPMENT CERTIFICATIONS EXAMINATION LIMITATIONS METHOD OF CALCULATION OF LIMITATIONS EXAMINATION LIMITATIONS EXAMINATION PLAN KEY TO WELD TRACKING SYSTEM EXAMINATION PLAN OF CLASS 1 AND 2 COMPONENTS COMPONENT ISOMETRICS

SUMMARY

OF INDICATIONS

SUMMARY

OF INDICATIONS INTEGRAL ATTACHMENT WELDS EXAMINED IN CYCLE 7 RECEIVE AN ENGINEERING EVALUATION TO INCREASE CODE COVERAGE

OWNER: TENNES~:Y , r " -,' AUTHORITY PLANT: BROWNS FERRY NUCLEAR PLANT p,O, BOX 2000 OFFICE C ~.:~ POWER 110 1 MAI<KET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED, COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNlT: NOT REQUIRED, A IT ACHMENT 2 AUGMENTED EXAMINATION

SUMMARY

SECTION 1: AUGMENTED

SUMMARY

SECTION 2: EXAMINATIONS PERFORMED DURING UNIT 3 CYCLE 10 (EXAMINATION SUMMARy) ATTACHMENT 3 IWE-BFN CONTAINMENT INSERVICE INSPECTION PROGRAM

~------------------.------------------------------------. OWNER: TENNESSEE VALLEY! r~::,:.""~"' PLANT: BROWNS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR, P,O. BOX 2000 llOI MARKET STREE"; DECATIJR, ALABAMA 35609-2000 CHAIT ANOOGA, TENNESSEE 37402 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED_ COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. APPENDIX I NIS-l OWNER'S REPORT

OWNER: TENNESSEE VALLEY AUTHOrul: OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 . :jf:OWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. Inservice Inspection Introduction Summary In accordance with paragraph IWA-6220 of 1989 Edition of Section XI of the AStvIE Boiler and Pressure Vessel Code the following infonnation is provided.

1. Date of document completion: June 4, 2002

2. Name of owner and address of principal offices:

Tennessee Valley Authority Office Of Nuclear Power 11 01 Market Street Chattanooga, Tennessee 37402*2801

3. Name and address of the nuclear generating plant:

Browns Ferry Nuclear Plant P.O. Box 2000 Decatur, Alabama 35602

4. Name or number assigned to the nuclear power unit by TVA:

Browns Ferry Nuclear Plant, Unit 3.

5. Commercial operation date of unit:

March I, 1977

6. Numbers assigned to the components by the state:

No numbers assigned

7. National Board Number assigned to the components by the manufacturer:

No numbers assigned

OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT:B' ... f ~ .. ":)'y NUCLEAR PLANT 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED.

8. 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 V.

9. Name and address of principal manufacturer and the principal contract which will identifY the subcontractors/manufacturer's component identification numbers.

The majority of components examined were supplied by: General Electric Corporation San Jose, Ca. Contract Number: 66C31-90744

10. Date of completion of the examinations:

April 08, 2002

11. Name of ANII who witnessed or othenvise verified the examinations and his employer and business address:

Albert L. Ladd and James A. Longenberger. Hartford Steam Boiler of Connecticut 200 Ashford Center North, Suite 300 Atlanta, Georgia 30338

12. Abstract of examinations, conditions observed, and corrective measures recommended or taken:

See Appendix III, IV, V and VI

13. Signature o(ANII:

See NIS-l Form.

FORM NIS-l OWNERS' REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the AS~ Code Rules

1. Owner Tennessee Valley Authority, 1101 Market St. Chattanooga, TN. 37402 (Name and Address of Owner)

2. Piant Browns Ferry Nuclear Plant. P.O. Box 2000 Decatur, AL. 35602 (Name and Address of Pi ant)

3. Plant Unit 3

4. Owner Certificate of Authorization Not Required

5. Commercial Service Date 03/01177

6. National Board Number for Unit Not Required

7. Components Inspected:

Component or Appurtenance Reactor Pressure Vessel Various systems and components. ( See Appendix V) Manufacturer or Installer General Electric TVA Manufacturer or Installer Serial No. Contract No. 67C31-90744 N/A State or Province No. N/A N/A The NIS-l Owners Report for Inservice Inspections

?+ oa-includes Appendices I. II, III. IV, V, and VI and Attachment 2.3 __ _

Total Pages _1_ of_2_ National Board No. N/A N/A Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8.5 in. X 11 in., (2) information in items 1 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.

FORM NIS-l (back) --*-*----l

8. Examination Dates 05/05/2000 to 05/06/2002

9. Inspection Interval from 11119196 to 11118/05 10_ Applicable Editions of Section XI 1989 Addenda NI A 11_ Abstract of Examinations_ Include a list of examinations and a statement concerning status of work required for current interval. See Appendix II, III, IV, and V. Examinations complete the second outage ofthe second period of the second inspection interval.

12. Abstract of Conditions Noted.. See Appendix II, III, IV, V, and VI.

13. 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 Date wrr:~6me~u~::~ak:~:::or:e:~::~~:::t::::: CO::'atid/

r Owner Certificate of Authorization No. Not Applicable Expiration Date Not Applicable CERTIFICATE OF INSERVICE INSPECTION I, The undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of Tennessee and employed by HSB Ct of Hartford. CT., have inspected the components described in this Owners' Data Report during the period 05/05/2000 to 05/06/2002, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report in accordance with the requirements of the ASME Code Section Xl By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners' Data 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 arising from or connected with this inspection. Commissions 7 t! :318 S 7" S A./ L3 4-National Board, State, Province and No.

OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. CONlMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD Nillv18ER FOR UNIT: NOT REQUIRED. APPENDIX II SCOPE AND INTRODUCTION

OWNER: TENNESSEE V ALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: TIIREE CERTIFICATE OF AUTHORIZATION: NOT REQillRED. COMl'v1ERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. Scope: The scope of this appendix is to provide an overview of the Inservice inspections performed during the Unit 3/Cycle 10 Outage on Class 1 and 2 components for ASME Section XI Code credit and other augmented examinations.

== Introduction:== The examinations were performed in accordance with implementing plant surveillance instruction 3-S1-4.6.G "Inservice Inspection and Risk Informed Inservice Inspection Program Unit 3". 3-S1-4.6.G is organized to comply with the lSI NDE requirements of the 1989 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, Division 1, Articles lWX-lOOO, lWX-2000, lWX-3000, and lWX-6000 in accordance with Title 10 Code of Federal Regulations (CFR) Part 50, 50.55a (g); to implement the Browns Ferry Nuclear Plant (BFN) Technical Requirements TR-3.4.3; and to fulfill the requirements ofSPP-9.1, ASME Section XI Inservice Inspection Program. Beginning the second Period of the second Interval, Surveillance Instruction 3-S1-4.6.G implemented the NRC approved BFN Risk-Informed Inservice Inspection Program to address all piping locations that are subject to service induced degradation. In accordance \\vith Regulatory Guides 1.174 and 1.178 and Code Case N-577, this program provides an acceptable alternative approach to the existing ASME Section XI requirements for scope and frequency of piping weld examinations, and satisfies the criteria of IOCFR50.55a(a)(3)(i) providing an acceptable level of quality and safety. Effective June 19,2000, integral attachments are examined in accordance with ASME Boiler and Pressure Vessel Code, Section XI 1995 Edition, 1996 Addenda per Request for Relief3-IS1-9. 3-SI-4.6.G reflects the built-in limitations of the original plant design, geometry, construction, component materials and the current technology or state-of-the-art nondestructive examination techniques. The SI specifies the methods to be used and provides schedule tables from which specific items \\vere scheduled for examination during the outage. Examinations were witnessed or verified by an Authorized Nuclear Inservice Inspector (ANII) and performed in accordance with the Section XI of the ASME Boiler and Pressure Vessel Code.

OWNER: TENNESSEE VALLEY AUTHORlTY O~CEOFNUCLEARPOWER PLANT: BROWNS FERRY l'mCLEAR PLANT P.O. BOX 2000 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COM:MERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. The majority of examinations were performed by the TVA Inspection Services Organization (ISO). Augmentation of personnel was provided by Wesdyne, Inc., and Framatome ANP. An overview of lSI activities consists of the following:

ASME Section XI Class 1 and 2 Piping Examinations
ASME Section XI Class 1 Reactor Pressure Vessel Weld Examinations
AS ME Section XI Class 1 and 2 Support Examinations
Reactor Pressure Vessel In-Vessel Visual Inspection (IVVI)
Augmented Examinations

OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOIt UNIT: NOT REQUIRED. APPENDIX III lSI

SUMMARY

_,.. TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 110 1 MARKET STREET CHAIT ANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTIIORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. Examination Summary: The Unit 3, Cycle 10 Inservice Inspection (lSI) was the second scheduled refueling outage during the second inspection period of the second ASME Section XI 10-year inspection interval. . Approximately 202 visual, 100 ultrasonic, 18 magnetic particle and I liquid penetrant examinations were performed in support of code credit components. Also, preservice examinations were performed; 6 visual, and I liquid penetrant examinations. Ten (10) Notification of Indications (NOI's) were issued to document indications identified during the performance of the examinations. These NOI's were evaluated by engineering and dispositioned (see Appendix VI, .s umrnary of Indications). Other examinations were performed in accordance with BFN's augmented inspection program and are included in Attachment I for information. Approximately 43 visual, 43 ultrasonic, and 10 radiography examinations were performed in accordance with the augmented program. These totals are inclusive of the Reactor Pressure Vessel Internals Inspection (RPVII) on Unit 3 RPV internals and ultrasonic inspection of the core spray piping welds for IGSCC.

r-----~,--- OWNER: '".. ~ -. . ~:: VALLEY AUTHORITY PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 Ul ".\\..:i:: 'J}" NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR. ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. ASME Code Cases The following code cases have been approved for use as applicable during the Unit 3/Cycle 10 outage: N-307-1 N-435-1 N-457 N-460 N-461 N-49 1 N-498-1 N-524 N-532 N-577 Revised Ultrasonic Examination Volume for Class 1 Bolting, Table lWB-2500-1, Examination Category B-G-l, When the Examinations Are Conducted From the Center-Drilled Hole, Section XI, Division 1 Alternative Examinations Requirements for Vessels With Wall Thickness 2 in. or Less, Section XI, Division 1 Qualification Specimen Notch Location for Ultrasonic Examination of Bolts and Studs, Section XI, Division 1 Alternative Examination Coverage for Class 1 and Class 2 We1ds, Section XI, Division 1 Alternative Rules for Piping Calibration Block Thickness, Section XI, Division 1 Alternative Rules for Examination of Class 1, 2, 3 and MC Component Supports of Light Water Cooled Power Plants, Section XI, Division 1 Alternate Rules for 10-Year System Hydrostatic Testing for Class 1, 2 and 3 Systems Section XI Division 1 Alternate Examination Requirements for Longitudinal We1ds in Class I and 2 Piping - Section XI, Division 1 Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report and Submission as Required by IWA-4000 and IWA-6000- Section XI Division I. Reference RFR 3-IS1-6 Risk-Informed Requirements for Class I, 2, and 3 Piping, Method A,, Section XI, Division 1, (RIMS # R08 000601 846), with the more detailed provisions provided in WCAP-14572, Revision I-NPA, "Westinghouse O,,,ners Group Application Of Risk -Informed Methods To Piping Inservice Inspection Topical Report"

OWNER: TENNESSEE 1***:.! ~,.. " lTHORlTY PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 OFFICE OF 1,rL,. "~, "t; -lOWER 110 1 MARKE; STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COIvIMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. UNIT 3 INTERVAL STATUS The BFN Unit 3 cycle 10 outage lSI exami~ations were performed during the second scheduled refueling outage of the second period of the second interval. The component quantities examined were detennined from 3-S1-4.6.G, Table A (Unit 3 Class I and 2 components) and from applicable BFN Unit 3 relief requests, This NIS-I report covers the Cycle 10 outage for Browns Ferry Unit 3. The following table summarizes the percentage of Code required examinations completed to date. Table I summarizes code credited examinations by category and percentages completed and complies with ASME Section XI percentage requirements. TABLEt ASME SECTION XI EXAMINATION

SUMMARY

FOR THE SECOND PERIOD OF THE SECOND TEN-YEAR INSPECTION INTERVAL CATEGORY B-A B-B B-D B-E B-F B-G-l B-G-2 B-G-2 B-H B-1 B-K-l B-K B-L-l B-L-2 B-M-l B-M-2 B-N-l B-N-2 B-O B-P B-O C-A C-B C-C C-D C-F-l C-F-2 C-G D-A D-B D-C F-A % COMPLETE 55% COMMENTS N/A 64% Deferred to system pressure test 29% Risk-Infonned lSI implemented in the second period (cycle 9) 65% 82% Utem # B7.50 and B7.70 when the valve is disassembled) .05% (Item # B7.80 CRD Housing Bolting, inspected when disassembled) N/A Reference RFR # 3-IS1-9 32% Risk-Informed lSI implemented in the second period (cycle 9) 33% Percentage for first period B-K-l's 50% Upgraded to Section XI, 1995 Edition, 1996 Addenda N/A 100% N/A 65% When disassembled 66% Each period Deferral permissible N/A Refer to pressure test program N/A 50% 66% 56% Second period exam selection per ASME Section XI 95 ed. wi 96 add. N/A 31% Risk-Infonned lSI implemented in the second period (cycle 9) 34% Risk-Infonned lSI implemented in the second period (cycle 9) N/A 33% 44% Upgraded to Section XI. 1995 Edition, 1996 Addenda 100% Upgraded to Section XI. 1995 Edition, 1996 Addenda 66% R-A 59% Risk-Infonned lSI implemented in the second period. This percentage does not include Flow Accelerated Corrosion (PAC) Item # Rl.18. Reference BFPER 99-008578-000, 02-005018-000, 02-00-1-920-000.

OWNER: TENNESSEE VALLEY AU" "T" OFFICE OF NUCLE!R PC'i. 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 . f.ANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: TIIREE CERTIFICATE OF AUThORIZATION: ~OT REQUIRED. CO:tv11vffiRCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NIDv1BER FOR UNIT: NOT REQUIRED. PERSONNELIEQUIPMENT CERTIFICATIONS: NDE personnel certification records for TVA and contractor employees are maintained by TVA's Nuclear Engineering and Technical Services Corporate, Inspection Services Organization (ISO). These records are maintained as permanent QA records for a forty year plant life. Any details or specifics regarding NDE certification records should be directed to the ISO at the Sequoyah . Training Center in Soddy-Daisy, Tennessee at telephone number (423) 843-4026. NDE equipment certification records are maintained by the TVA IS O. Any details or specifics regarding NDE equipment certification records should be directed to ISO at the Sequoyah Training Center in Soddy Daisy, Tennessee at telephone number (423)843-4026.

OWNER: TENNESSEE VALLEY AUTHORITY pI OFFICE OF NUCLEAR POWER 110 1 MARKET STREET CHAITANOOGA, TENNESSEE 37402 'T**

'~VNS FERRY NUCLEAR PLANT

,X 2000 Di:,CATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. CO~RCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. APPENDIX IV EXAMINATION LIMITATIONS

OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT: BRow~r'. ~,=,r P.CU*, 'CLEAR PLA1'iT 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA.. 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COlvl1v1ERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. METHOD OF CALCULATION OF LIMITATIONS During the performance of Inservice Inspections, the ASME Section XI Code 1989 Edition, no addenda, requires the determination of the ultrasonic examination volume to establish the required beam path angles needed to maximize coverage and verify technique parameters. This information is necessary in those instances where there may be a reduction in the examination volume. Surface examinations of welded attachments are conducted in accordance with ASME Section XI Code 1995 Edition, 1996 Addenda. Surface examinations are typically conducted on 100% of the weld length plus a defined amount of base material on each side of the weld. Surface areas are calculated in those instances where there may be a reduction in the examination area. The Code required ultrasonic examination volume or surface examination area for each type of piping \\veld or nozzle-to-vessel weld is depicted in the figures of IWB-2500 or IWC-2500. As depicted for piping welds, volume width generally constitutes the weld plus 114" on each side while volume thickness generally constitutes the lower 1/3 of the piping thickness for the length of the weld. As depicted, for nozzle-to-vessel welds, the volume width generally constitutes the weld plus 1I2t (tsl2) on each side of the weld while volume thickness generally constitutes the entire component thickness (i.e. full volume). The volume changes with variations in weld configuration (e.g. transition between different pipe thickness or nozzle-to-vessel configuration). Therefore, it is necessary to determine the required volume for each group of similar welds to allow setting of scanner limits for automated ultrasonic examinations and scan paths for manual ultrasonic examinations. Surface examination area is generally the weld plus 1/2-inch of base material on each side of the weld. Reactor Pressure Vessel Nozzle to shell or head,veld examination volume has been reduced to W' beyond the widest part of the boundary of the deposited weld material in lieu of the requirements of ASME Section XI Figures IWB-2500-7 (a) and IWB-2500-7 (b) per Request for Relief No. PDI-2. Paragraph IW A-2232 of the Code requires that the ultrasonic examination of piping systems be conducted in accordance with Appendix I of ASME Section XI. Appendix I requires that the ultrasonic examination of piping systems be conducted in accordance with Appendix VIII of ASME Section Xl, and the nozzle-to-vessel welds be conducted in accordance with Article 4 of ASME Section V, 1989 Edition as supplemented by Appendix I of ASME Section XI. Appendix VIII and Article 4 define the applicable examination methods (e.g., examination angles, scan directions) to be used during examination. Paragraphs IWA-2221 and IWA-2222 of the ASME Section XI, requires that surface examinations be conducted in accordance with Article 6 or 7, as applicable, of ASME Section V, 1989 Edition. The 1995 Edition, 1996 Addenda will be used for the surface examination requirements ohvelded attachments. TVA developed procedure N-GP-28 to provide a standardized methodology for calculation of Code coverage in those instances where configuration or other components cause an examination limitation. Components/welds with limitations were evaluated in terms of the feasibility of other NDE techniques or methods to increase coverage or for Code Case N-460 applicability. EXAMINATION LIMITATIONS: A tabulation ofNDE examination limitations recorded during the Unit 3/Cycle 10 Inservice Inspection is contained in this Appendix.

Owt-.'ER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY N1F ,~ '~ ! 1>.JT 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 P.O. BOX 2000 DECATIJR, ALABA1V1A 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRE;). COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. The following items/components had less than 100% R-AlCode coverage achieved and TVA elected to use Code Case N-460 which states that when the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage for Class 1 or Class 2 welds may be accepted provided the reduction in coverage for that weld is less than 10%. SYSTEM COMPONENT ID COVERAGE CALCULATED REPORT NO. ASME XI 10CFR50,55a RPV RCH-3-4V 98% 98% R-1l8 The following items/components had examination limitations outside those specified in Code Case N-460. The Inservice Inspection Program 3-SI-4.6.G will be revised to incorporate these limitations in the form of Requests for Relief (RFR). Program revisions, including Requests for Relief, will be submitted to the NRC. SYSTEM COMPONENT ID RHR. DRHR-3-21 COVERAGE CALCULATED ASrvtE XI 10CFRSO.55a 100% 50% REPORT NO. RFRNo. R-140 3-IS1-12 The following items/components had examination limitations outside those specified in Code Case N-460. The Inservice Inspection Program 3-S1-4.6.G will be revised to incorporate these limitations in the form of Requests for Relief (RFR). Program revisions, including Requests for Relief, will be submitted to the NRC. SYSTEM COMPONENT ID COVERAGE CALCULATED REPORT NO. RFRNo. RPV N-7 70% R-125 3-IS1-7 Rev. 01 RPV N-lB 77% R-156 3-IS1-7 Rev. 01 RPV N-2A 77% R-158 3-IS1-7 Rev. 01 RPV N-2C 77% R-160 3-IS1-7 Rev. 01 RPV N-2E 77% R-162 3-IS1-7 Rev. 01 RPV N-3A 77% R-164 3-1S1-7 Rev. 01 RPV N-4A 77% R-166 3-IS1-7 Rev. 01 RPV N-4F 77% R-168 3-ISI-7 Rev. 01 RPV N-5B 71% R-170 3-IS1-7 Rev. 01 RPV N-9 74% R-I72 3-IS1-7 Rev. 01 The Reactor Pressure Vessel Support Skirt, Component Number RPV-SUPP-3-1-IA, is accessible for surface examination only from the outside surface. Therefore, a request for relief (RFR) to use Code Case N-323 Alternative Examination for welded Attachments to Pressure Vessels, is required. The Surveillance Instruction 3-S1-4.6.G, Inservice Inspection Program incorporates this examination coverage limitation in the form of Request For Relief 3-IS1-9.

~---------------------------------------------------------, OWNER: TENNESSEE VALLEY AUTHORITY PLANT: BROWNS FERRY NUCLEAR PLMr OFFICE OF NUCLEAR POWER P.O. BOX 2000 1101 MARKET STREET DECATUR ALABAMA 35609-2000 CHATTANOOGA, TENNESSEE 37402 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NillvfBER FOR lJ}..'1T: NOT REQUIRED. APPENDIX V EXAMINATION PLAN

OWNER: TENNESSEE VALLEY AUTHORlTY OFFICE OF NUCLEAR POWER 110 1 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. The following printout is an outage lSI report designed to meet the reporting requirements of IW A-6000 of the ASME Section XI Code. This report contains Unit 3/Cyc1e 10 Inservice Inspection data for Code Class 1 and Code Class 2 components selected for ASME Section XI credit. Attaclunent 2 contains a summary of Augmented examinations performed during Unit 3/Cycle 10 outage. Essential unit and system files are contained herein as a reference to describe abbreviations and features in the printout. The aforementioned precedes the outage lSI report. Code Class 3 Inservice data and reports are contained in the Browns Ferry Inservice Inspection (lSI) Final Plant Report.

OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 110 I MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. CO:MMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD Nillv1BERFOR UNIT: NOT REQUIRED. Key to computer weld/feature tracking system A. CYCLE-Refueling Cycle Number and Unit Number B. SYSTEM-System/Component CCWS-Closed Cooling Water System (Reactor Building Closed Cooling Water) CRDS-Control Rod Drive System CSS-Core Spray System EECW-Emergency Equipment Cooling Water System FPCS-Fuel Pool Cooling System FWS-Feedwater System HPCIS-High Pressure Coolant Injection System MSS-Main Steam System RCICS-Reactor Core Isolation Cooling System RECIR-Recirculation System RHRS-Residual Heat Removal System RHRSW-Residual Heat Removal Service Water System RPV - Reactor Pressure Vessel RWCU-Reactor Water Cleanup System C. Component Number/Identifyer D. Drawing-lSI Drawing Number and sheet number from the Surveillance Instruction (SI-4.6.G) E. Exreq-ASME Section XI Code year and interval (See Note # 1) F. Category-Code Category G. Item Number-Code Item Number H. Exam Scheduled

1. NDE METH-Nondestructive Examination (NDE) Method ET - Eddy Current Test MT -.Magnetic Particle Test PT - Penetrant Test RT - Radiography Test UT - Ultrasonic Test VT-Visual Test

OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BRG'VNS FERRY l'mCLEAR PLANT P.O. BOX 2000 DECATIJR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COtvfMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR 'UNIT: NOT REQUIRED. J. Calibration Standard-If required K. Exam Date-Date of Inspection L. Exam Report No. - Examination Report Number M. Exam Results - P - Pass R-Rejectable E-Evaluated acceptable for continued operation by Engineering O. COM:MENTS NOTE (1): EXREQ Identifyers: 86E ASrvIE Section XI Code 1986 Edition! Second Interval P 11 Preservice Examination Cycle 111 Second Interval N-491 - Preservice examination during or following initial system heatup and coo1down B02 Examinations performed to NUREG-0313 & Generic Letter 88-01 for IGSCC detection B05 Examination of RPV Shell Welds Code Category B-A It. # B 1.12 in accordance with 10CFRSO.55a (g)(6)(ii)(A) B07 Examinations performed to the recommendation of GE SIL-571 OT1365 - Augmented examinations of RPV Internals

OWNER: TENNESSEE VALLEY AUTHORlTY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORlZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. UNIT 3/CYCLE 10 lSI REPORT OF CLASS 1 AND CLASS 2 COMPONENTS

April 30, 2002 Albert Ladd, ANI/ ANII, PEC-l C, BFN BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 CYCLE 10 REFUELING OUT AGE INSER VICE INSPECTION (lSI) SCAN PLAN, REVISION 3. Attached for your review is the BFN Unit 3 Cycle 10 refueling outage lSI Scan Plan, Revision 3. The examinations are scheduled to be performed during the Unit 3 outage by BFN Site Engineering/Component Engineering. The examinations are performed to satisfy the requirements of ASME Code Section XI, 1989 Edition, No Addenda. This document was prepared by Hal Hodges ofBFN Component Engineering and coordinated with Fred Froscello and Darlene Tinley of TV AN Inspection Services. Harold E. Hodges BFN Component Engineering ~ .. s:.e-"JJ... " _ Darlene Tinley 6 ISO, NDE Level III cc: T. S. Taylor, PEC-l C, BFN M. L. Turnbow, STC-lI, ~~5(?~;; Albert Ladd, ANI/ ANII Concurrence ot- 004410 - 000.. l¥1~ s ~ 1 ~ lfYJ?,

Revision 003 07/0112002 Total Examinations: 350 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR POWER PLANT - UNIT 3 EXAMS SCHEDULED FOR CYCLE 10 SYSTEM WELDNO SEGMENT ISONO CYCLE ITEMNO CATEGORY EXREQ EXSCHD NDEPROC CALSTD COMPDlA NOMTHCK COMPDESA COMPDESB CCWS CCWS CRDS CRDS CRDS CRDS CRDS CRDS CRDS 3-S1-3.3.11 3-S1-3.3.11 3-47B468-248 3-47B468-252 3-478468-256 3-478468-285 3-478468-291 3-47B468-294 3-478468-301 CRDS 3-47B468-301-IA CRDS 3-478468-314 CSS 3-478458-100 CSS 3-47B458-560 CSS CSS CSS CSS CSS CSS CSS CSS 3-47B458-75 3-478458-81

1-S1-3.3.6 3-S1-3.3.6 CS-3-R-29 DSCS-3-02 DSCS-3-02 DSCS-3-08 CSS DSCS-3-08 C8S TSCS-3-424 EECWS 3-47B451H0002 EECWS 3-478451 R0067 EECWS 3-47B451S0073 EECWS 3-47B451S0076 EECWS 3-47B451S0132 EECWS 3-47B451S0135 EECWS 3-47845IS0142 EECW8 3-47B45180309 EECWS 3-S1-3.3.14.A EECWS 3-S1-3.3.14.B FPCS 3-S1-3.3.3 FWS 3-47B415-21 N/A N/A 3-181-0 I 44-C-02 3-ISI-O I 44-C-02 3-1SI-0 I 44-C-02 3-ISI-O 144-C-O I 3-ISI-O I44-C-O I 3-ISI-0 I44-C-O I 3-ISI-O I 44-C-O 1 10 10 10 10 10 10 10 10 10 3-ISI-OI 44-C-O 1 10 3-ISI-0144-C-02 10 3-ISI-O 104-C-02 10 3-ISI-0339-C-0 1 10 C7.30 C7.70 FI.20A F1.20B FI.20B F1.20B F1.2OA FI.20B FI.20B C3.20 F1.20B FI.20A Fl.IOC 3-ISI-0104-C-0I 10 F1.20A 3-ISI-OI04-C-02 10 F1.20B N/A 10 C7.30 N/A 10 3-ISI-0 1 04-C-0 I 10 3-ISI-0331-C-0 I 10 3-ISI-0331-C-0 I 10 3-ISI-033I-C-OI 10 3-ISI-0331-C-OI 10 3-ISI-033I-C-O1 10 3-ISI-0390-C-02 10 3-ISI-0390-C-01 10 3-ISI-0390-C-0 1 10 3-ISI-0390-C-0 I 10 3-ISI-0390-C-03 10 3-ISI-0390-C-03 10 3-ISI-0390-C-02 10 3-ISI-0390-C-02 10 C7.70 F1.20A Rl.I6C NU0313 R1.l6C NU0313 TS3432 Fl.30A F1.30B F1.30B Fl.3OA F1.30B F1.30B Fl.30B F1.30B 10 D2.1O 10 D2.1O N/A 10 D2.10 3-ISI-0336-C-0 I 10 FI.I OD C-H C-H F-A F-A F-A F-A F-A F-A F-A C-C F-A F-A F-A F-A F-A C-H C-H F-A R-A C

R-A C B-J F-A F-A F-A F-A F-A F-A F-A F-A D-B D-B D-B F-A 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 96E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 B02-02 89E-02 B02*02 B04-02 89E-02 89E-02 89E-02 89E-02 89E*02 89E-02 89E-02 89E-02 89E-02 89£-02 89E-02 89E-02 VT-2 VT-2 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 MT VT-3 VT-3 VT-3 VT-3 VT-3 VT-2 VT-2 VT-3 UT UT UT UT UT VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-2 VT-2 VT-2 VT-3 N-VT-4 N-VT-4 N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-MT-6 N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-4 N-VT-4 N-VT-I N-UT-64 N-UT-64 N-UT-64 N-UT-64 N-UT-76 N-VT-! N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-4 N-VT-4 N-VT-4 N-VT-I BF-79 BF-79 BF-79 BF-79 BF-75 06.00 06.00 06.00 06.00 06.00 ( 06.00 06.00 12.00 12.00 12.00 10.00 14.00 16.00 12.00 12.00 12.00 12.00 12.00 10.00 6.00 06.00 06.00 08.00 06.00 06.00 10.00 12.00 1.00 0.688 0.688 0.688 0.688 0.688 RGDHGR RGDHGR RGDHGR RGDH3R RGDSTRT RGDHGR RGDHGR WLDATT

VSLSUP RGDSTRT VARSUP RGDSTRT RGDHGR HRS EL EL EL P

P P EL P EL P RGDSTRT RGDHGR RGDHGR RGDHGR RGDHGR RGDHGR RGDHGR RGDANCH SNBR SORT ORDER: SYSTEM-WELDNO Page 1 0/9

SYSTEM WELDNO SEGMENT ISONO CYCLE ITEMNO CATEGORY EXREQ FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS 3-47B415-21 3-47B415-22 3-47B415-23 3-47B415-25 3-47B415-25 3-47B415-36 3-47B415-36-IA 3-47B415-41 3-47B415-4I-IA 3-47B415-59 3-47B415-59-IA 3-47B415-67 3-47B4I 5-67-IA 3-554 3-554 3-554 3RFWA-13T 3RFWA-16T 3RFWA-27E 3RFWB-13T 3RFWB-16T FWS 3RFWB-20E FWS GFW-3-09 FWS GFW-3-15 FWS KFW-3-38 HPCIS 3-47B455-621 HPCIS 3-47B455-635 HPCIS 3-SI-3.3.9 HPCIS 3-SI-3.3.9 HPCIS THPCI-3-07OA 3-47B400-114 3-47B400-74 3-47B400-94 3-SI-3.3.I.C 3-SI-3.3.I.C 3-SI-3.3.I.C 3-ISI-0336-C-0 I 10 3-ISI-0336-C-OI 10 3-ISI-0336-C-0 I 10 3-ISI-0336-C-0 I 10 3-ISI-0336-C-OI 10 3-ISI-0336-C-0 I 10 3-ISI-0336-C-OI 10 3-ISI-0336-C-O I 10 3-ISI-0336-C-O I 10 3-ISI-0336-C-O I 10 3-isI-0336-C-O 1 10 3-ISI-0336-C-0 1 10 3-ISI-0336-C-O I 10 3-ISI-O:}27-C-OI 10 3-ISI-0327-C-OI 10 3-ISI-0327-C-OI 10 3-003-036 3-ISI-0327-C-OI 10 3-003-036 3-ISI-0327-C-O I 10 3-003-037 3-ISI-0327-C-OI 10 3-003-040 3-ISI-0327-C-0 1 10 3-003-040 3-ISI-0327-C-OI 10 3-003-041 3-ISI-0327-C-0 I 10 3-ISI-0327-C-0 I 10 3-ISI-0327-C-OI 10 3-ISI-0327-C-OI 10 3-ISI-0335-C-O I 10 3-CHM-2413-C-02 10 N/A 10 N/A 10 3-ISI-0333-C-0 I 10 3-ISI-0338-C-02 10 3-ISI-0338-C-OI 10 3-ISI-0355-C-0 I 10 N/A 10 N/A 10 N/A 10 MSS MSS MSS MSS MSS MSS MSS MSS MSS MSS 3C RFPT Exhaust Line 3-001-026 3HDVZ-S1AE-FCVI55-4P 3-001-002 10 10 10 10 82 Cross under C2 Cross over 3-001-016 3-001-021 Fl.lOD F1.10D F1.10D F1.10D Fl.lOD F1.10C BIO.20 FI.40C BI0.40 F1.10D BIO.20 FUOD BIO.20 B12.50 B12.50 B12.50 RU8 RU8 RU8 RU8 RU8 R1.18 TS3432 TS3432 TS3432 FUOC FI.20A C7.30 C7.70 TS3432 FUOC Fl.lOD FI.20B C7.30 C7.50 C7.70 RU8 Rl.18 Rl.18 RU8 F-A F-A F-A F-A F-A F-A B-K F-A B-K F-A B-K F-A B-K B-M-2 B-M-2 B-M-2 R-A R-A R-A R-A R-A R-A B-1 B-1 B-J F-A F-A C-H C-H B-1 F-A F-A F-A C-H C-H C-H R-A R-A R-A R-A P07-02 89E-02 89E-02 89E-02 P07-02 89E-02 96E-02 89E-02 96E-02 89E-02 96E-02 89E-02 96E-02 89E-02 89E-02 P07-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 B04-02 B04-02 B04-02 89E-02 P07-02 89E-02 89E-02 B04-02 89E-02 P07-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 EXSCHD NDEPROC CALSTD COMPDIA NOMTHCK COMPDESA COMPDESB VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 MT VT-3 MT VT-3 MT VT-3 MT VT-I VT-3 VT-3 UT UT UT UT UT UT UT UT UT VT-3 VT-3 VT-2 VT-2 UT VT-3 VT-3 VT-3 VT-2 VT-2 VT-2 VT UT VT VT N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-MT-6 N-VT-I N-MT-6 N-VT-I N-MT-6 N-VT-I N-MT-6 N-VT-l N-VT-l N-VT-l N-UT-26 N-UT-26 N-UT-26 N-UT-26 N-UT-26 N-UT-26 N-UT-76 N-UT-76 N-UT-76 N-VT-I N-VT-l N-VT-4 N-VT-4 N-UT-76 N-VT-l N-VT-l N-VT-I N-VT-4 N-VT-4 N-VT-4 BOP-VT-2 N-UT-26 BOP-VT-2 BOP-VT-2 12.00 12.00 12.00 20.00 20.00 12.00 12.00 24.00 24.00 12.00 12.00 24.00 24.00 24.00 24.00 24.00 Step Wedge 24.00 Step Wedge 20.00 Step Wedge 12.75 Step Wedge 24.00 Step Wedge 20.00 Step Wedge 12.75 BF-75 12.00 BF-75 12.00 BF-75 12.00 BF-42 10.00 10.00 10.00 26.00 26.00 1.500 2.000 0.500 0.750 0.994 0.994 0.994 1.531 1.281 0.844 1.531 1.281 0.844 0.566 0.566 0.566 0.593 SNBR SNBR SNBR SNBR SNBR CFS WLDATT VARSUP WLDATT SNBR WLDATT SNBR WLDATT INT INT

INT GRID GRID GRID GRID GRID GRID EL P

RED TEE EL EL P VARSUP RGDHGR P CFS SNBR RGDANCH FACComp GRID FACComp FACComp P .:-:.;.;.;.;.:.:-:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.;.:.;.;.;.;.;.;.:.:-;.;.;.:.;.;.;.:-:.:.:.:.:.;.:.:.:.:.:.;.:.:.:.:.:.;.:.;.;.;.;.;.;.:.;.:.:.:.:.:.;.:.:-:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.;.:,:-:.;.:.:.:.:.;.:.:.;.;.;.:.:.:.;.:.:.:.;.:.:.:.:.;.:.:.:.;.:.:.:.:.:.:.;.;.;.;.:-:.;-:-:.;.:-:.;.;.;.;.:.;.;.;.;.;.:.:.:.;.;.:.:.:.:.:.:-:-:-:.:.:.:.:.:.:.:.:.:.:.:.:.g.:.:.:.;.:.;.;.:-:.:.:-:.:.;.;.;.;.;.;-;.;.:.;.;.;.;.;.;.;.;.:.;.;.;.;.;.;-:.:.:.;';':';.:':';';';';':':.:':';';';':':';';';,;':0:';';';.:.;.;.:.;.:.:.:.:.:.:.:.:.:.:.:.:.;.:.:.:.:.:.:.:.:.:.:.;.:.;-:.;.;.:.:.:.;.;.:.:.:.:.:.:.:.;.:.;.:.;.;.;.;.;.:.;.;.;.;.:.:.:.:.:.;.;.;.;.;.:.:.;.:.;.;.;.:.;.:.;.:.;.;.:.;.:-:.:.:.; SORT ORDER: SYSTEM-WELDNO Page 2 0/9

SYSTEM WELDNO MSS MSS MSS GMS-3-06 GMS-3-24 MSBC-3-08 MSS MSBC-3-09 MSS MSBC-3-11 MSS PCVI-3-005-PBC MSS PCVI-3-019-PBC MSS PCVI-3-019*PBC MSS PCVI-3-022-PBC MSS PCVI-3-041-PBC MSS PCVI*3*041*VBC MSS PCVI*3*179*PBC MSS PCVI-3-180*PBC RCICS 3-S1-3.3.1O RCICS 3-S1*3.3.10 RECIR 3-47B465-482 RECIR 3-47B465-483 RECIR 3-47B465*504 RECIR GR-3-63 RECIR KR-3-45 RECIR KR-3-50 RECIR RBC*3*1 RHRS 3-47B452*1382 RHRS 3-47B452-1426 RHRS 3-47B452-1426-IA RHRS 3-478452-1456 RHRS 3-478452*1 474*IA RHRS 3-478452*1487 RHRS 3-47B452*1496 RHRS 3-47B452-1496*IA RIIRS 3-47B452*1537 RHRS 3-47B452-1537-IA RHRS 3-47B452-1557-IA RHRS 3-47B452-3033 RHRS 3-47B452*3044 RHRS 3-S1-3.3.8.A RHRS RHRS RHRS RIIRS 3-S1-3.3.8.A 3*SI*3.3.8.B 3-SI*3.3.8.B 3-S1*3.3.8.C SEGMENT ISONO CYCLE ITEMNO CATEGORY EXREQ 3-1S1-0329-C-0 1 10 3-ISI-0329-C-02 \\0 3-1S1-0313-B-OI 10 3-ISI-0313-B-O 1 10 3-ISI-0313-B-OI 10 3-1S1-0313-B-OI 10 3-ISI-0313-B-0 1 10 3-ISI-0313-B-0 1 10 3-ISI-0313-B-0 1 10 3-ISI-0313-B-OI 10 3-isl-0313-B-01 10 3-ISI-0313-B-O 1 10 3-ISI-0313-B-O 1 10 N/A 10 N/A 10 3-ISI-0337-C-02 10 3-ISI-0337-C-02 10 3-ISI-0337-C-02 10 3-ISI-0328-C-02 10 3-ISI-0328-C-0 1 10 3-ISI-0328-C-02 \\0 3-ISI-0328-C-0 1 10 3-ISI-0395-C-07 10 3-ISI-0395-C-04 10 3-ISI-0395-C-04 10 3-ISI-0395-C-09 10 3-ISI-0395-C-09 10 3-ISI-0395-C-II 10 3-ISI-0395-C-06 10 3-ISI-0395-C-06 \\0 3-ISI-0395-C-08 10 3-ISI-0395-C-08 10 3-ISI-0395-C-IO 10 3-ISI-0340-C-0 1 \\0 3-ISI-0340-C-0 1 10 N/A 10 N/A N/A 10 10 10 \\0 TS3432 TS3432 B7.50 B7.50 B7.50 B7.50 B7.50 B7.50 B7.50 B7.50 B7.70 B7.50 B7.50 C7.30 C7.70 FI.\\oC Fl.40C Fl.40D NU0313 NU0313 NU0313 B7.50 Fl.20A Fl.20A C3.20 Fl.20A C3.20 FI.20A Fl.20B C3.20 FI.20A C3.20 C3.20 Fl.lOC Fl.IOC C7.30 C7.50 C7.30 C7.70 C7.30 B*l B-1 B-G-2 B-O-2 B-G-2 B-G-2 B*G*2 B-G-2 B-G-2 B-G*2 B*G*2 B-G-2 B-G-2 C*H C*H F-A F-A F-A E C C B-G-2 F-A F-A C-C F-A C*C F*A F*A C-C F-A C-C C-C F*A F*A C-H C-H C*B C*H C-B B04*02 B04-02 89E-02 89E-02 89E-02 89E-02 89E*02 P07-02 89E-02 89E*02 89E-02 89E-02 89E*02 89E*02 89E*02 89E-02 89E*02 89E*02 B02*02 B02-02 B02-02 89E*02 89E*02 89E-02 96E-02 89E*02 96E*02 89E*02 89E-02 96E-02 89E-02 96E-02 96E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 EXSCHD NDEPROC CALSTD COMPDIA NOMTHCK COMPDESA COMPDESB UT UT VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-l VT-I VT-I VT-2 VT-2 VT-3 VT-3 VT-3 UT UT UT VT-I VT-3 VT-3 MT VT-3 MT VT-3 VT-3 MT VT-3 MT MT VT-3 VT-3 VT-2 VT-2 VT-2 VT-2 VT-2 N-UT-76 N-UT-76 N-VT-I N-VT-l N-VT-I N-VT-I N-VT-l N-VT-I N-VT-I N-VT-l N-VT-I N-VT-l N-VT-l N-VT-4 N-VT-4 N-VT-l N-VT-I N-VT-l N-UT-64 N-UT-64 N-UT-64 N-VT-l N-VT-l N-VT-l N-MT-6 N-VT-l N-MT-6 N-VT-I N-VT-l N-MT-6 N-VT-l N-MT-6 N-MT-6 N-VT-l N-VT-I N-VT-4 N-VT-4 N-VT-4 N-VT-4 N-VT-4 BF-I04 BF-104 BF-57 BF-57 BF-57 26.00 26.00 28.00 28.00 28.00 28.00 28.00 20.00 20.00 20.00 24.00 20.00 24.00 24.00 20.00 0.950 0.950 1.138 1.138 1.138 0.625 1.000 1.00 0.500 0.875 P EL BLTG BLTG BLTG BLTG BLTG BLTG BLTG BLTG BLTG BLTG BLTG VARSUP CFS SNBR EL TEE VLV P P EL P EL BLTG SNBR SNBR WLDATT SNBR WLDATT RGDHGR RGDHGR WLDATT RGDHGR WLDATT WLDATT VARSUP VARSUP

SYSTEM WELDNO RHRS 3-SI-3.3.8.C RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS 3-SI-3.3.8.C DRHR-3-03 DRHR-3-03B DRHR-3-03B DRHR-3-12 DRHR-3-13B DRHR-3-13B DRHR-3-21 DRHR-3-21 DSRHR-3-04 DSRHR-3-04 RHR-3-002-GOO I RHR-3-002-G003 RHRG-3-05-B RHRG-3-06A-B RHRG-3-06B-B RHRG-3-06B-B RHRG-3-06B-B RHRG-3-06B-B RHRG-3-08-B RHRG-3-12-B RHRG-3-13-B RHRG-3-14-B TRHR-3-222 TRHR-3-246 RHRS TRHR-3-28I RHRS TRHR-3-293 RHRSW 3-47B450-252-IA RHRSW 3-47B450-293-IA RIIRSW 3-SI-3.3. I 3 RPV 3-S1-3.3.l.A RPV 3-SI-3.3.l.A RPV 3-S1-3.3.l.A RPV 3-S1-3.3.l.A RPV 3-S1-3.3.2.A RPV RPV RP.V RPV 3-SI-3.3.2.A 3-S1-3.3.2.B 3-SI-3.3.2.B 3-S1-3.3.7 SEGMENT ISONO CYCLE ITEMNO CATEGORY EXREQ N/A N/A 3-ISI-0330-C-0 I 3-ISI-0330-C-O I 3-ISI-0330-C-0 I 3-ISI-0330-C-0 I 3-ISI-0330-C-O I 3-ISI-0330-C-0 I 3-ISI-0330-C-0 I 3-ISI-0330-C-0 I 3-ISI-0330-C-O I 3-ISI-0330-C-O I 3-ISI-0330-C-O I 3-ISI-0330-C-O I 3-ISI-0422-C-0 I 3-ISI-0422-C-O I 3-ISI-0422-C-O I 3-ISI-0422-C-O I 3-ISI-0422-C-O I 3-ISI-0422-C-0 I 3-ISI-0422-C-OI 3-ISI-0422-C-OI 3-ISI-0422-C-0 I 3-ISI-0422-C-O I ISI-0393-C-16 ISI-0393-C-16 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 3-ISI-0393-C-14 10 3-ISI-0393-C-14 10 3-CHM-2416-C-02 10 3-CHM-2416-C-03 10 N/A N/A N/A N/A N/A N/A N/A N/A N/A 10 JO 10 JO 10 10 JO JO JO JO C7.50 C7.70 NU0313 Rl.16G NU0313 NU0313 R1.I6G NU0313 Rl.I6C NU0313 NU0313 TS3432 Rl.lI Rl.lI C2.33 C2.31 C2.31 C2.33 C2.31 C2.31 Cl.lO F1.40B F1.40B F1.40B Rl.l1 Rl.lI Rl.lI RI.!I D1.20 D1.20 D2.10 B15.70 BI5.10 B15.50 B15.60 C7.30 C7.70 C7.30 C7.70 C7.30 C-H C-H D R-A G D R-A G R-A C C B-1 R-A R-A CoB CoB CoB CoB CoB CoB C-A F-A F-A F-A R-A R-A R-A R-A D-A D-A D-B B-P B-P B-P B-P C-H C-B C-lI C-H C-H 89E-02 89E-02 B02-02 89£.02 B02-02 B02-02 89E-02 B02-02 89E-02 B02-02 B02-02 B04-02 89£.02 89E-02 89E-02 89E-02 89E-02 89E-02 AOI-02 AOI-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 96E-02 96E-02 89£.02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 EXSCHD NDEPROC CALSTD COMPDIA NOMTHCK COMPDESA COMPDESB VT-2 VT-2 UT VT-2 VT-2 UT VT-2 VT-2 UT UT UT UT UT UT VT-2 MT MT VT-2 PT UT UT VT-3 VT-3 VT-3 UT UT UT UT VT-I VT-I VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 N-VT-4 N-VT-4 N-UT-64 N-VT-4 N-VT-4 N-UT-64 N-VT-4 N-VT-4 N-UT-64 N-UT-64 N-UT-64 N-UT-64 N-UT-64 N-UT-64 N-VT-4 N-MT-6 N-MT-6 N-VT-4 N-PT-9 N-UT-26 N-UT-18 N-VT-I N-VT-I N-VT-I N-UT-76 N-UT-76 N-UT-76 N-UT,76 N-VT-I N-VT-I N-VT-4 N-VT-2 N-VT-4 N-VT-4 N-VT-4 N-VT-4 N-VT-4 N-VT-4 N-VT-4 N-VT-4 BF-57 BF-57 BF-87 BF-87 BF-57 BF-57 BF-57 BF-57 BF-40 BF-IOI BF-101 BF-101 BF-IOI 24.00 24.00 24.00 24.00 24.00 24.00 20.00 20.00 24.00 24.00 24.00 24.00 24.00 24.00 24.00 24.00 1.219 1.219 1.219 1.219 1.219 1.219 1.031 1.031 1.219 1.219 1.219 1.219 0.375 0.375 0.375 0.375 0.750 0.750 VLV P P VLV P P EL EL P P P P NOZ

SHL NOZ NOZ NOZ NOZ SHL WLDATT WLDATT WLDATI VLV VLV FH P

P FH P P VLV VLV EL EL TEE TEE SHL PL PL PL PL PL FLG SHL SHL SHL EL EL VLV EL TEE EL WLDATI WLDATI -:':':':':':':':':':':':':':',,,:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.;.:.:.:.:.:.:.:.:.:-:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.;.;.:.:.:.;.:.;.:.:.:.:.:.:.:.:.:.:.:-:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.;.:.:-:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.;.:.:.:.:.:.:.:.:.:.:.:.;.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.;.:.:.:.;.:.;.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.;.:.;.:.;.;.:.:.:.;.:.:.;.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:-:.:.:.;.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:':':':':':':':':':':';0;':':';':';':';';';':':';';':';':.;.:.;.;.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.:.;.:.;.;.:.;.:.;.;.;.:.:.:.: SORT ORDER: SYSTEM-WELDNO Page 4 0/9

SYSTEM WELDNO RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV 3-SI-3.3.7 NIO-SE NIB NIB-IR N2A N2A-IR N2C N2C-IR N2E N2E-IR N3A N3A-IR N4A N4A-IR N4F N4F-IR N5B N5B-IR N6B-3-2-BC N7 N7-IR N9 N9-IR RCH-3-2C RCH-3-2C-FLEX RCH-3-3V RCH-3-4V RPV-BUSH-3-31 RPV-BUSH-3-32 RPV-RUSH-3-33 RPV-BUSH-3-34 RPV-BUSH-3-35 RPV-BUSH-3-36 RPV-BUSH-3-37 RPV-BUSH-3-38 RPV-BUSH-3-39 RPV-BUSH-3-40 RPV-BUSH-3-41 SEOMENT ISONO CYCLE ITEMNO CATEOORY EXREQ N/A 10 ISI-0445-C-0 I 10 3-ISI-0328-C-02 10 3-ISI-0328-C-02 10 3-ISI-0328-C-02 10 3-ISI-0328-C-02 10 3-ISI-0328-C-02 10 3-ISI-0328-C-02 10 3-ISI-0328-C-02 10 3-ISI-0328-C-02 10 3~ISI-0329-C-01 10 3-ISI-0329-C-01 10 3-ISI-0327-C-OI 10 3-ISI-0327-C-0 I 10 3-ISI-0327-C-0 I 10 3-ISI-0327-C-0 I 10 3-ISI-0331-C-0 1 10 3-ISI-0220-C-0 1 10 3-ISI-0295-A-O I 10 3-ISI-0295-A-01 10 3-ISI-0295-A-0 I 10 3-ISI-0220-C-0 I 10 3-ISI-0220-C-O I 10 3-ISI-0295-A-0 I 10 3-ISI-0295-A-0 I 10 3-ISI-0295-A-0 I 10 3-ISI-0295-A-01 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-0 I 10 3-ISI-0267-C-01 10 3-ISI-0267-C-0 I 10 3-ISI-0267-C-0 I 10 3-ISI-0267-C-01 10 3-ISI-0267-C-0 I 10 3-ISI-0267-C-0 I 10 3-ISI-0267-C-0 I 10 3-1SI-0267-C-0 I 10 3-ISI-0267-C-0 I 10 C7.70 N/A B3.90 B3.100 B3.90 B3.100 B3.90 B3.100 B3.90 B3.100 B3.90 B3.100 B3.90 B3.100 B3.90 B3.100 B3.90 B3.100 B7.50 B3.90 B3.100 B3.90 B3.\\OO BI.40 BI.40 BI.22 BI.22 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 86.50 86.50 C-H SIL-571 B-D B-D B-D B-D B-D B-D B-D B-D B-D B-D B-D B-D B-D B-D B-D B-D B-0-2 B-D B-D B-D B-D B-A B-A B-A B-A B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-0-1 89E-02 B06-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 EXSCHD NDEPROC CALSTD COMPDIA NOMTHCK COM POE SA COMPDESB Vf-2 trr trr trr trr trr trr trr trr trr trr trr trr trr trr trr trr trr Vf-I trr Vf-I trr trr trr MT trr trr Vf-I Vf-I Vf-I Vf-I Vf-I Vf-I Vf-I Vf-I Vf-I Vf-I Vf-I N-Vf-4 N-trr-64 N-trr-9 N-trr-55 N-trr-9 N-trr-55 N-trr-9 N-trr-55 N-trr-9 N-trr-55 N-trr-9 N-trr-55 N-trr-9 N-trr-55 N-trr-9 N-UT-55 N-trr-9 N-trr-55 N-Vf-I N-trr-9 N-Vf-I N-trr-9 N-trr-55 N-UT-9 N-MT-6 N-trr-78 N-trr-78 N-Vf-I N-Vf-I N-Vf-I N-Vf-I N-Vf-I N-Vf-I N-Vf-I N-Vf-I N-Vf-I N-Vf-I N-VT-I . SQ-85 2.00 BF-18 28.00 BF-84-IR BF-18 12.00 BF-85-IR BF-18 12.00 BF-85-IR BF-18 12.00 BF-85-IR BF-18 26.00 BF-84-IR BF-18 12.00 BF-84-IR BF-18 12.00 BF-84-IR BF-18 10.00 BF-85-IR BF-19 4.000 BF-18 BF-85-IR BF-19 BF-18 BF-19 BF-18 -264 -264 -96L -96L 0.250 6.600 6.600 6.600 6.600 6.600 6.600 6.600 6.600 4.000 6.600 4.00 4.00 4.00 4.00 NOZ SHL NOZIR NOZ NOZIR NOZ NOZIR NOZ NOZIR SHL NOZIR NOZ NOZIR NOZ

NOZIR NOZ NOZIR BLTO CLHD NOZIR SHL NOZIR HD CHFLO VERTLS VERTLS BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH SE NOZ SHL SHL SHL NOZ SHL SHL SHL NOZ NOZ FLO HD SORT ORDER: SYSTEM-WEI-DNO

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SYSTEM WELDNO RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV R~Y RI'V RPV-BUSH-3-42 RPV-BUSH-3-43 RPV -BUSH-3M RPV -BUSH-3-45 RPV -BUSH-3-46 RPV -BUSH-3-47 RPV-BUSH-3-48 RPV-BUSH-3-49 RPV-BUSH-3-50 RPV -BUSH-3-51 RPV -BUSH-3-52 RPV -BUSH-3-53 RPV-BUSH-3-54 RPV-BUSH-3-55 RPV -BUSH-3-56 RPV-BUSH-3-57 RPV-BUSH-3-58 RPV -BUSH-3-59 RPV-BUSH-3-60 RPV-LlOS-3-31 RPV -LlOS-3-32 RPV -LlOS-3-33 RPV-LlOS-3-34 RPV-LlOS-3-35 RPV-LlOS-3-36 RPV-LlOS-3-37 RPV-LlOS-3-38 RPV-LlOS-3-39 RPV -LlOS-3-40 RPV-LlOS-3-41 RPV-LIOS-3-42 RPV-LlOS-3-43 RPV-LlOS-3-44 RPV-LlOS-3-45 RPV-LIOS-3-46 RPV -LIOS-3-47 RPV-LlOS-3-48 RPV-LlOS-3-49 RPV-LlOS-3-50 RPV-LIOS-3-51 SEOMENT JSONO CYCLE JTEMNO CATEOORY EXREQ 3-JSI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-O 1 10 3-ISI-0267-C-O 1 10 3-ISI-0267-C-01 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-O 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-01 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-O 1 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-OI 10 3-JSI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-01 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISJ-0267-C-0 1 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-O 1 \\0 3-ISI-0267-C-O 1 10 3-ISI-0267-C-OI \\0 3-ISI-0267-C-0 1 10 3-ISI-0267-C-OI 10 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B6.40 B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I 8-0-1 B-O-I B-O-I 8-0-1 8-0-1 B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-G-I B-O-I 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 EXSCHD NDEPROC CALSTD COMPDIA NOMTHCK COMPDESA COMPDESB VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 N-UT-37 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 BF-126 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 -13 BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH BUSH . BUSH BUSH BUSH BUSH LIO LIO LIO LIO LIO LIO LIO LIO LIO LIO LIO LIO LlO LlO LlO LIO LIO LIO LIO LIO LIO SORT ORDER: SYSTEM-WELDNO Page 60[9

SYSTEM WELDNO RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV Rl'.V RPV RPV-LlGS-3-52 RPV-LIGS-3-53 RPV-LIGS*3*54 RPV*LIGS*3*55 RPV -LIGS-3-56 RPV-LIGS-3-57 RPV*LIGS*3*58 RPV -LlGS-3*59 RPV-LIGS-3-60 RPV -NUTS-3-31 RPV *NUTS*3*32 RPV *NUTS*3*33 RPV *NUTS*3*34 RPV*NlJrS*3-35 RPV-NUTS-3*36 RPV*NUTS-3-37 RPV*NUTS*3*38 RPV*NUTS*3*39 RPV-NUTS-3-40 RPV*NUTS*3-41 RPV*NUTS*3-42 RPV-NUTS-3-43 RPV -NUTS-3-44 RPV-NUTS-3-45 RPV -NUTS-3-46 RPV-NUTS-3-47 RPV -NUTS*3-48 RPV-NUTS*3-49 RPV*NUTS*3*50 RPV *NUTS-3-51 RPV *NUTS*3*52 RPV -NUTS-3-53 RPV-NUTS-3-54 RPV-NUTS-3-55 RPV*NUTS*3*56 RPV-NUTS*3*57 RPV-NUTS*3*58 RPV -NUTS-3-59 RPV-NUTS-3-60 RPV*STUDS*3*22 SEGMENT ISONO CYCLE ITEM NO CATEGORY EXREQ 3*ISI-0267-C*0 1 10 3*ISI-0267 -CoO 1 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-OI 10 3*ISI*0267*C-OI 10 3*ISI-0267-C-O 1 10 3-ISI-0267-C-OI 10 3*ISI*0267*C*0 1 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-O 1 10 3-1SI-0267-C-O 1 10 3*ISI*0267-C-O 1 10 3*ISI-0267*C-OI 10 3*ISI*0267*C*0 1 10 3*ISI*0267*C-OI 10 3-ISI-0267-C-OI 10 3-ISI*0267*C-OI 10 3*ISI*0267*C-OI 10 3*ISI-0267-C*OI 10 3-ISI-0267*C-OI 10 3-ISI*0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-O 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267-C-OI 10 3*ISI-0267*C-OI 10 3*ISI*0267*C*0 1 10 3-ISI-0267-C-OI 10 3*ISI-0267-C*OI 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-0 1 10 3-ISI-0267*C*0 1 10 3-ISI-0267*C*OI 10 3*ISI-0267-C-0 1 10 3-ISI-0267-C-0 1 10 3-ISI-0267*C*0 1 10 3-ISI*0267*C-0 1 10 3*ISI*0267-C-0 1 10 86.40 86.40 86.40 86.40 86.40 86.40 B6.40 86.40 86.40 B6.10 B6.1O B6.1O B6.10 86.10 B6.10 B6.1O 86.10 86.10 B6.1O B6.10 B6.10 B6.1O B6.10 B6.1O B6.1O B6.10 B6.10 B6.10 B6.10 B6.1O B6.1O B6.10 B6.1O B6.10 B6.1O B6.10 86.10 86.10 B6.1O B6.30 B-G-I 8-G-I B*G*I B-G-I 8-G-I B*G*I B-G-I 8-G*I B*G*I B*G*I 8-G-I B-G-I B-G-I 8*G*I B*G*I 8-G-I 8-G-I 8-G*I B-G-I 8-G*I B*G*I B-G-I B-G-I B-G-I 8-G-I B-G-I 8-G*I 8-0*1 8-G-I B-G-I 8-G-I B-G*I B-G-I B*G*I B-G-I 8-G-1 B-G-I 8*G-I B-G*I B-G-I 89E-02 89E-02 89E*02 89E*02 89E-02 89E-02 89E-02 89E-02 89E*02 89E*02 89E-02 89E-02 89E-02 89E-02 89E*02 89E*02 89E-02 89E-02 89E-02 89E-02 89E*02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E*02 89E-02 89E-02 89E*02 89E-02 89E-02 89E*02 89E-02 89E-02 89E-02 89E-02 89E*02 89E-02 EXSCHD NDEPROC CALSTD COMPDlA NOMTHCK COMPDESA COMPDES8 UT UT UT UT UT UT UT UT UT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT VT MT N-UT*37 N-UT-37 N*UT*37 N*UT*37 N-UT-37 N-UT-37 N-UT*37 N-UT-37 N*UT*37 N-VT*I N-VT-I N-VT*I N-VT-I N*VT*I N*VT*I N-VT*I N*VT*I N-VT*I N-VT*I N-VT-I N*VT*I N*VT*I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N*VT*I N*VT*I N-VT-I N*VT*I N-VT-I N-VT*I N*VT*I N*VT*I N-VT-I N-VT-I N*VT*I N-VT*I N-MT*6 BF*126 BF*126 BF*126 BF-126 BF-126 BF-126 BF*126 BF-126 BF*126 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 08.50 06.00 -13 -13 -13 -13 -13 -13 -13 -13 -13 65.56 LIG LIG, LIG LIG LIG LIG LIG LIG LIG CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHD8LT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHD8LT SORT ORDER: SYSTEM-WELDNO Page 70/9

SYSTEM WELDNO RPV RI'V RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RI'V RPV Rry RI'V RPV-STUDS-3-23 RPV-STUDS-3-24 RPV-STUDS-3-25 RPV -STUDS-3-31 RPV-STUDS-3-32 RPV-STUDS-3-33 RPV -STUDS-3-34 RPV-STUDS-3-35 RPV-STUDS-3-36 RPV-STUDS-3-37 RPV-STUDS-3-38 RPV-STUDS-3-39 RPV -STUDS-3-40 RPV -STUDS-3-41 RPV -STUDS-3-42 RPV -STUDS-3-43 RPV.STUDS-3-44 RPV-STUDS-3-45 RPV -STUDS-3-46 RPV *STUDS*3-47 RPV *STUDS-3-48 RPV *STUDS-3-49 RPV-STUDS-3-50 RPV-STUDS*3*51 RPV-STUDS*3*52 RPV -STUDS*3*53 RPV*STUDS*3*54 RPV*STUDS-3-55 RPV-STUDS*3-56 RPV -STUDS*3*57 RPV-STUDS-3-58 RPV -STUDS*3*59 RPV -STUDS*3*60 RPV*SUPP*3*1 RPV*SUPP*3*1*IA RPV *SUPP*3-1*IA RPV*WASH*3*31 RPV-W ASH*3-32 RPV* W ASH*3*33 RPV.WASH-3-34 SEGMENT ISONO CYCLE ITEMNO CATEGORY EXREQ 3*ISI*0267*C*0 I 10 3*ISI*0267*C*0 1 10 3*ISI*0267*C*0 1 10 3-ISI-0267-C-OI 10 3-ISI-0267-C-O I 10 3*ISI*0267-C-0 1 10 3-ISI*0267-C-0 1 10 3*ISI-0267*C*0 1 10 3*ISI*0267*C*OI 10 3*ISI*0267*C*0 1 10 3:ISI-0267.C*OI 10 3-ISI-0267*C-O 1 10 3*ISI*0267*C*0 1 10 3*ISI*0267'(;*01 10 3*ISI-0267'(;-O 1 10 3-ISI-0267-C-OI 10 3*ISI-0267'(;-O 1 10 3*ISI-0267*C-O 1 10 3*ISI*0267-C*0 1 10 3-ISI*0267-C*OI 10 3*ISI-0267*C*OI 10 3*ISI*0267*C*0 1 10 3*ISI*0267*C*0 I 10 3-ISI*0267-C-0 I 10 3-ISI*0267*C*0 1 10 3*ISI-0267-C*0 1 10 3-ISI*0267*C-0 1 10 3*ISI*0267*C*0 1 10 3*ISI*0267*C-0 I 10 3-ISI*0267*C*0 1 10 3*ISI*0267*C-OI 10 3-ISI-0267*C*0 I 10 3*ISI-0267'(;*01 10 3-ISI-0416*C*02 10 3-ISI*041 6*C*02 10 3*ISI*0416*C*02 10 3*ISI*0267*C*OI 3*ISI-0267*C*0 I 3-ISI*0267*C*0 1 3*ISI*0267*C*0 I \\0 10 10 10 86.30 86.30 B6.30 B6.20 B6.20 B6.20 86.20 86.20 B6.20 86.20 86.20 86.20 86.20 86.20 B6.20 B6.20 B6.20 B6.20 86.20 86.20 B6.20 B6.20 B6.20 B6.20 B6.20 86.20 86.20 B6.20 B6.20 86.20 B6.20 B6.20 B6.20 FI.40B BIO.1O BIO.1O B6.50 B6.50 B6.50 B6.50 B*G*I B*G*I B*G-I B*G*I B*G*I B*G*I B*G*I B*G*I B*G*I B*G*I B-G*I B-G*I B-G-I B*G-I B*G-I B-G*I B*G*I B-G-I B*G-I B*G-I B*G*I B-G-I B*G*I B*G*I B*G*I B*G*I B*G-I B-G*I B*G*I B*G*I B-G-I B*G*I B*G*I F*A B*K B-K B*G*I B*G*I B*G-I B*G*I 89E*02 89E*02 89E*02 89E*02 89E*02 89E*02 89E*02 89E*02 89E-02 89E-02 89E*02 89E*02 89E*02 89E-02 89E*02 89E*02 89E*02 89E*02 89E*02 89E*02 89E*02 89E-02 89E*02 89E*02 89E*02 89E*02 89E*02 89E*02 89E*02 89E*02 89E*02 89E*02 89E-02 89E*02 96E*02 96E*02 89E*02 89E*02 89E-02 89E*02 EXSCHD NDEPROC CALSTD COMPDIA NOMTIICK COMPDESA COMPDESB MT MT. MT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT VT-3 MT UT VT*I VT*I VT*I VT*I N*MT-6 N*MT*6 N*MT-6 N-UT-67 N*UT*67 N*UT*67 N-UT-67 N-UT-67 N*UT-67 N*UT-67 N-UT*67 N*UT-67 N-UT-67 N-UT-67 N*UT-67 N*UT-67 N-UT-67 N*UT-67 N*UT*67 N-UT-67 N*UT-67 N*UT-67 N*UT*67 N*UT*67 N-UT-67 N*UT-67 N-UT*67 N*UT*67 N*UT-67 N*UT-67 N-UT*67 N-UT-67 N-UT-67 N-VT-I N*MT*6 N*UT*7 N*VT*I N-VT-l N*VT-l N*VT-l BF*126 BF-126 BF-126 BF*126 BF-126 BF*126 BF*126 BF*126 BF-126 BF-126 BF*126 BF*126 BF*126 BF-126 BF*126 BF*126 BF-126 BF*126 BF*126 BF*126 BF-126 BF*126 BF*126 BF-126 BF*126 BF-126 BF-126 BF*126 BF-126 BF-126 BNp*60 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 65.56 08.62 08.62 08.62 08.62 CLHDBLT CLHDBLT CLHD8LT CLHDBLT CLHDBLT CLHD8LT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT CLHDBLT STAB IA IA WASH WASH WASH WASH SORT ORDER: SYSTEM-WELDNO Page 8 0/9

SYSTEM WELDNO RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV . RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV-W ASH-3-35 RPV -W ASH-3-36 RPV-WASH-3-37 RPV-W ASH-3-38 RPV-W ASH-3-39 RPV-WASH-3-40 RPV-WASH-3-41 RPV-W ASH-3-42 RPV-WASH-3-43 RPV-WASH-3-44 RPV-W ASH-3-45 RPV -W ASH-3-46 RPV-W ASH-3-47 RPV -W ASH-3-48 RPV-W ASH-3-49 RPV -W ASH-3-50 RPV-WA..<;H-3-51 RPV -W ASH-3-52 RPV -W ASH-3-53 RPV-W ASH-3-54 RPV-WASH-3-55 RPV RPV-WASH-3-56 RPV RPV-WASH-3-57 RPV RPV-WASH-3-58 RPV RPV-WASH-3-59 RPV RPV-WASH-3-60 RWCUS 3-478406-286 RWCUS 3-478406-286-IA RWCUS RWCU-3-001-0016 RWCUS RWCU-3-001-0017 RWCUS RWCU-3-001-0018 SLCS 3-S1-3.3.4 SLCS 3-S1-3.3.4 SLCS 3-SI-3.3.4 SLCS 3*SI*3.3.4 SWQS 3-SI*3.3.\\5 SWQS 3-S1-3.3.15 SEOMENT ISONO CYCLE ITEMNO CATEOORY EXREQ 3-ISI-0267-C-O I IO 3-ISI-0267-C-0 I IO 3-ISI-0267-C-01 10 3-ISI-0267-C-01 10 3-ISI-0267-C-01 10 3-ISI-0267-C-01 10 3-ISI-0267-C-0 I IO 3-ISI-0267-C-01 10 3-ISI-0267-C-0 I IO 3-ISI-0267-C-0 I 10 3-ISI-0267-C-O I IO 3-ISI-0267-C-O I 10 3-ISI-0267-C-01 10 3-ISI-0267-C-O I IO 3-ISI-0267-C-01 10 3-ISI-0267-C-O I 10 3-ISI-0267-C-O I IO 3-ISI-0267-C-O I 10 3-ISI-0267-C-0 I IO 3-ISI-0267-C-0 I 10 3-ISI-0267-C-0 I 10 3-ISI-0267-C-0 I 10 3-ISI-0267-C-0 I IO 3-ISI-0267-C-0 I IO 3-ISI-0267-C-O I 10 3-ISI-0267-C-0 I IO 3-ISI-0334-C-O I IO 3-ISI-0334-C-O I IO 3-ISI-0332-C-0 I 10 3-ISI-0332-C-01 IO 3-ISI-0332-C-0 I IO N/A 10 N/A IO N/A IO NlA 10 N/A 10 N/A IO 86.50 B6.50 B6.50 B6.50 86.50 86.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 B6.50 86.50 B6.50 86.50 B6.50 B6.50 B6.50 86.50 B6.50 86.50 86.50 86.50 86.50 86.50 FI.IOC 810.20 TS3432 TS3432 TS3432 C7.50 C7.30 C7.50 C7.70 C7.30 C7.70 8-0-1 B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I 8-0-1 B-O-I B-G-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I B-O-I F-A B-K B-J B-J B-J C-H C-H C-H CoIl C-H C-H 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 96E-02 804-02 804-02 B04-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 EXSCHD NDEPROC CALSTD COMPDIA NOMTHCK COMPDESA COMPDES8 VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-I VT-3 PT UT UT UT VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-l N-VT-I N-VT-I N-VT-I N-VT-l N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-VT-I N-PT-9 N-UT-64 N-UT-64 N-UT-64 N-VT-l N-VT-4 N-VT-4 N-VT-4 N-VT-4 N-VT-4 BF-118 BF-118 BF-118 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00. 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 06.00 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 08.62 1.000 0.432 0.432 0.432 WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH WASH VARSUP WLDATT EL P P EL EL P SORT ORDER: SYSTEM-WELDNO Page 9 0[9

OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. ASME SECTION XI PRESSURE TESTS CLASS 1, 2, AND 3

Exam Requirements 89E-02 System RHRS RHRS RHRS RHRS RHRS RHRS HPCIS HPCIS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RHRS RPV RPV CSS CSS CSS CSS SLCS SLCS SLCS SLCS FPCS RPV RPV RPV RPV SWQS SWQS EECWS EECWS Weld No RHRG-3-06-B RHRG-3-05-B DRHR-3-13B DRHR-3-13B DRHR-3-03B DRHR-3-03B 3-SI-3.3.9 3-SI-3.3.9 3-SI-3.3.8.C 3-SI-3.3.S.C 3-SI-3.3.8.C 3-SI-3.3.8.B 3-SI-3.3.S.B 3-SI-3.3.8.A 3-SI-3.3.S.A 3-SI-3.3.8.A 3-SI-3.3.8.A 3-SI-3.3.7 3-SI-3.3.7 3-SI-3.3.6 3-SI-3.3.6 3-SI-3.3.6 3-SI-3.3.6 3-SI-3.3.4 3-SI-3.3.4 3-SI-3.3.4 3-SI-3.3.4 3-SI-3.3.3 3-SI-3.3.2.B 3-SI-3.3.2.B 3-SI-3.3.2.A 3-SI-3.3.2.A 3-SI-3.3.15 3-SI-3.3.15 3-SI-3.3.14.B 3-SI-3.3.14.A ISO No. 3-ISI-0422-C-01 01 3-ISI-0422-C-01 01 3-ISI-0330-C-01 01 3-ISI-0330-C-01 01 .3-ISI-0330-C-01 01 3-ISI-0330-C-01 01 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A TENNESSE v,._L.EY AUTHORITY BROWNS FERRY NUCLEAR POWER PLANT - UNIT 3 Cycle Exreq Cat Item No ExSchd Date Report No Results 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 89E-02 89E-02 802-02 89E-02 802-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 89E-02 COB CoB G R-A G R-A C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H 0-8 C-H C-H C-H C-H C-H C-H D-B D-B C2.33 C2.33 NU0313 R1.16G NU0313 R1.16G C7.30 C7.70 C7.30 C7.50 C7.70 C7.30 C7.70 C7.30 C7.30 C7.50 C7.50 C7.30 C7.70 C7.30 C7.30 C7.70 C7.70 C7.30 C7.50 C7.50 C7.70 02.10 C7.30 C7.70 C7.30 C7.70 C7.30 C7.70 02.10 02.10 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 20020407 20020407 20020407 20020407 20020110 20020110 20010216 20010216 20010216 20020327 20020327 20010302 20001207 20001207 20010302 20001101 20001101 20010720 20010928 20010928 20010720 20020331 20000801 20020331 20020331 20020328 20020407 20020407 20020407 20020407 20010625 20010625 20011204 20011101 R155 R155 R155 R155 R017 R017 ROOB R008 R008 R064 R064 ROO9 ROO6 ROO6 ROO9 ROO4 R004 R012 R013 R013 R012 R065 R002 R065 R065 R066 R068 R068 R067 R067 R010 R010 R016 R015 A A A A A A A A A A A A A A 'A A A A A A A A A A A A A A A A A A A A Pressure Tests Comments Loop 2 Partial for remainder see R006 Partial for remainder see ROO9 Partial for remainder see ROO9 Partial for remainder see ROO6 Loop 1 (MC) Loop 2 (8&0) Loop 2 (8&0) Loop 1 (MC) Examined lAW IWA-5250 (a)(2) Page J of2

TENNESSE v,._,-EY AUTHORITY Exam Requirements 89E-02 BROWNS FERRY NUCLEAR POWER PLANT - UNIT 3 Pressure Tests RHRSW 3-SI-3.3.13 10 89E-02 0-6 02.10 VT-2 20011001 R014 A CCWS 3-SI-3.3.11 N/A 10 89E-02 C-H C7.30 VT-2 20010102 R007 A CCWS 3-SI-3.3.11 N/A 10 89E-02 C-H C7.70 VT-2 20010202 R007 A RCICS 3-SI-3.3.10 N/A 10 89E-02 C-H C7.30 VT-2 20010711 R011 A RCICS 3-SI-3.3.10 N/A 10 89E-02 C-H C7.70 VT-2 20010711 ROll A MSS 3-SI-3.3.1.C ,N/A 10 89E-02 C-H C7.30 VT-2 20020503 Rool A MSS 3-SI-3.3.1.C N/A 10 89E-02 C-H C7.50 VT-2 20020503 R001 A MSS 3-SI-3.3.1.C N/A 10 89E-02 C-H C7.70 VT-2 20020503 R001 A RPV 3-SI-3.3.1.A N/A 10 89E-02 B-P 615.10 VT-2 20020407 R155 A RPV 3-SI-3.3.1.A N/A 10 89E-02 B-P 615.50 VT-2 20020407 R155 A RPV 3-SI-3.3.1.A N/A 10 89E-02 6-P 615.60 VT-2 20020407 R155 A RPV 3-SI-3.3.1.A N/A 10 89E-02 B-P 615.70 VT-2 20020407 R155 A Page 20f2

EXAM REQUIREMENTS VT-2 System Component Number RHRS 3-SI-3.3.8.C RHRS 3-SI-3.3.8.C RHRS 3-SI-3.3.8.C RHRS ORHR-3-03B RHRS ORHR-3-03B RHRS ORHR-3-13B RHRS ORHR-3-13B RHRS RHRG-3-05-B RHRS RHRG-3-06-B RHRS 3-SI-3.3.13 RPV 3-SI-3.3.1.A RPV 3-SI-3.3.1.A RPV 3-SI-3.3.1.A RPV 3-SI-3.3.1.A RPV 3-SI-3.3.2.A RPV 3-SI-3.3.2.A RPV 3-SI-3.3.2.B RPV 3-SI-3.3.2.B RPV 3-SI-3.3.7 RPV 3-SI-3.3.7 SLCS 3-SI-3.3.4 SLCS 3-SI-3.3.4 OWNER: TENNESSEE VALLEY AUTHORITY NUCLEAR POWER GROUP 1101 MARKET STREET CIIA TT ANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CYCLE: 10 COMMERCIAL SERVICE DATE: MARCHI, 1977 CERTIFICATION OF AUTHORIZATION: NOT REQUIRED NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED ISO Drawing Exam Category Item Exam Calibration Exam Exam Exam Comments Requirement Number Scheduled Standard Date Report Results N/A 89E-02 C-H C7.30 VT-2 20010216 R008 A Loop 2 N/A 89E-02 C-H C7.50 VT-2 20010216 R008 A N/A 89E-02 C-H C7.70 VT-2 20010216 R008 A 3-ISI-0330-C-01 01 B02-02 G NU0313 VT-2 3-ISI-0330-C-01 01 89E-02 R-A R1.16G VT-2 3-ISI-0330-C-01 01 B02-02 G NU0313 VT-2 3-ISI-0330-C-01 01 89E-02 R-A R1.16G VT-2 3-ISI-0422-C-01 01 89E-02 C-B C2.33 VT-2 3-ISI-0422-C-01 01 89E-02 C-B C2.33 VT-2 89E-02 O-B 02.10 VT-2 20011001 R014 A N/A 89E-02 B-P B15.10 VT-2 20020407 R155 A N/A 89E-02 B-P B15.50 VT-2 20020407 R155 A N/A 89E-02 B-P B15.60 VT-2 20020407 R155 A N/A 89E-02 B-P B15.70 VT-2 20020407 R155 A N/A 89E-02 C-H C7.30 VT-2 20020407 R067 A N/A 89E-02 C-H C7.70 VT-2 20020407 R067 A N/A 89E-02 C-H C7.30 VT-2 20020407 R068 A N/A 89E-02 C-H C7.70 VT-2 20020407 R068 A N/A 89E-02 C-H C7.30 VT-2 20001101 R004 P N/A 89E-02 C-H C7.70 VT-2 20001101 R004 P N/A 89E-02 C-H C7.30 VT-2 20020331 R06S A N/A 89E-02 C-H C7.S0 VT-2 20000801 R002 P Examined lAW IWA-S2S0 (a)(2) 0512112002 Page 2 of3

OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERP' .- T~; ." PLANT P.O. BOX 200(, DECATUR, ALA3AMA 35609-2000 UNIT: TIIREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COM:MERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. ISOMETRICS FOR COMPONENT LOCATIONS

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1. ~~~6~ F JgA~j~Nf~~~\\~?~K~mR Jt\\AT(R I AL. \\

2. NOZZLES N-11A, N-llB, N-12A, N-128, N-16A,1 AND N-16B ARE CATECORY B-E.

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RPV-STUDS (01-92)

NUTS

RPV-NUTS (01-92)

HASHERS

RPV-WASH (01-92)

BUSH/Ne RPV-BUSH-J-(OI-92) ... Gt.lIN .e. s TENNESSEE VALLEY AUTHORHY BROWNS FERRY NUCC£AR-PLANT UNIT 3 '1F.SSEL S WD L CCA ! IONS ~AC£:iI._ ~r ! ~ I sl.~~T?_ ORAW/V; NO. /.'1£1' j:j S~*f.* (ioi ~ ALL A/D HISTORY RESEARCHEP AT ROOO ceo

270' 240' PCADAN RCH-3-2C-FLEX (360" SEE DETAIL C o* -RCH-3-1V ~ ~!~ OETAll A ~ ~~E DETAIL B ~N6B ~SEE DETAIL A -RCH-3-4V 180' LIFTING LUG (4 TYP." CID 'y' OIMfNSIQNS N6A 5/8" N68 5/8' N7 1/16" N6A-.J-7-8C N68-3-2-8C" --- 90' REFERENCE DRAW 8&W 722876 8&W 122877 NOTE: THIS DRAWING SUPERSEDES CHM-2102-A (UNIT 3 ONLY MATERIAL SPECIFICATIONS CLOSURE HEAD DOME/SEGMENTS CS MN/MO N-7 NOZZLE - AS08 CL.2 (MN-MO) LONG WELD NECK - SA-70S GR. II CS N6A.N68 NOZZLE - AS08 CL.2 (MN-MO) LONG WELD NECK - SA-lOS GR.II CS ASME CC-1 (EQUIVALENT) DETAIL A 120' r:6ii;:;;':';" ; OHA IL C ALL AID H I STORY RESEARCHED AT ROOO 111111 I flllIlllI 111111 III " II 57U310464 .fWD MAKINGS CC 3 3'ISI'IZt5-A aaaoOl D4ZZ'7 010 1.,,*../.... * '17 I JIOl I 'f( 1-,,, I(LD" I.,A I NIl. liLl) I/;:~ 000 I ISM.O TO Cll[AT( c::a:a :IIJI"(.. O($ A'-OfSIOMeo,SI-02tl-A_'., oUIiI '0 Dl"'Cl .... CDd'-":11O STATUS Ha A... IIIII:MO au '10',14. JQh A/'O to I'll CMMCK IIU 1 DAn I If,aleNtll) o_I.... lt..,I'OI'urol*NT~ S I TENNESSEE VALLEY AUTHORITY BRowNs FERRY-NuCLEAR PLANT UN IT.3 CLOSURE HEAD ASSEM8LY WELD LOCATIONS ---SCii:l7ifS -'-01 OF 01 SI.1'#. (;LB 1.J:i~~*295 Ak;Oo cco

ADMIN PCV7-3-779-x.. ADMI N I m<NL'~~MC I TfKTf!9NIX 4J29 TEKNICAO 8.2 noppy '8F4 PCADAM ADMIN REFERENCE DRAWINGS: 3-47£801-1 ~ ASHE CC-1 (EGUIVALENT) PCV7-3-042-X (REFER TO NOTE 2 FOR HS8C-3-12~" SUFFIX, TYPICAL2- ) HSBC-3-11 ADMIN ADMIN r::::::.. PCV7-03-037-X PCV7-3-030-X -- NOTES:

7. THIS DRAW I NC SUPERCEDES IS I-0022-A*o UNI T 3 ONL Y.

2. SUBSTITUTE "VBC" FOR "X" WHEN EXAM.

NC)'

VAL VE BODY BOL TlNC AND "PBC" FOR ";' ( WHEN EXAMININC VALVE TO PIPE BOLn:,.,.) TENNESSEE VALLEY AUTHORITY SI BROWNS FERRY NUCLEAR PLANT UNIT 3 MAINSTEAM SYSTEM BCL TEO CON"IECTIOf':S eRA',,'/: FHB SCALE. NTS sfir'E T'iOF j sliet T (,,I ~~~~~I;~~ CCD

NOTE:

1. PIPE SEGMENTS CONTAINING THO LONGITUDINAL SEAMS HILL 8E IDENTIFIED AS:

(BASE WELD NO.) -LS-ID (DOHNSTREAM) (BASE HELD NO.) -LS-2D (DOHNSTREAM) (BASE HELD NO.) -LS-1U (UPSTREAM) (BASE HELD NO.) -LS-2U (UPSTREAM) THe -LS-1 SEAM HILL BE NUMERICALLY CLOSEST TO O* ON THE PIPE AND THE -LS-2 SEAM HILL BE NUMERICALLY FARTHeRMOST FRON O* ON THE PIPE. (e.g. -LS-l AT 130*. AND -LS-2 AT 310*)

2. PIPE SEGMENTS CONTAINING ONLY ONE LONGITUDINAL SEAN WILL BE IqENTIFIED AS:

(BASE HELD NO.) -LS-D (DOWNSTREAM) (BASE HELD NO.}-LS-U (UPSTREA~ KFH-3-1S-KFH-3-17--- GFW-3-J4-- --KFH-3-35 --GFH-3-15 -GFW-3-33 REFERENCE DRAWINGS 47KJ545-1 47H335-2 GE 729E152 2-ISI-0277-C (SH. 1) SUPPORr /.lAp THIS DRAHING SUPERC£DES CHH-2138-C ALL SHEETS. MATERIAL SPECIFICATIONS .4155 CL. 1 GR. KCF70. OR A234 GFR. HP8. OR 04333 GR.S SCH.jO~ OR 04420 GR.HPLl S" X 0.593" NOM. HALL 12" X..D..Q5.§~ MIN. WALL 16" XV,.llii'70NOM. WALL (16' SCH 100) 20" X 0.t142" MIN. HALL 24" X 0.994" MIN. HALL 26" X 0.994" MIN. WALL NOTES J. flf NOZZLES N-4A-IR N-4B-IR N-4C-IR N-40-IR N-4E-IR N-4f-IR (INNER RAOIUS) j ~~ GE FlELD HELDS HERE MADE IN THE FIELD BY TVA ASME CC-l (EGUI VAL ENT) PCAOAU KFW-3-14 -:- GFW-3 -GFH-3-28 KFW-3 - KFH-3-33 ~KFW-3-41 KFW-3-34-- KFH-3-32 GFW-3-27 ... r KFW-3-40 IrKFW-3-45 ""6'. ir GFH-3-15 KFW-373 HCV-3-57 + ~ 3-554 ,/ ~o REDUCER \\ I KFW-3-08 61 + -9<'<-0 4-~ ~ i~~ "GFW-3-30 -! 24" X 20"~ r ":>6'. v. 6'.... (3-554-BC GFW-3-12 -2"'-- KFW-3-10-LSJ KF"fI-3 ~ I / a--~4-, ~~

.>:,..~.,\\

KFH-3-12 KFH-3....... __ 'N-GFW-3-04('~'tb'-9, O.,:>~ 3-569 GFH-3-07--- -v; ':O'-i! ~"6' 3-568-t. 20' X 12" REDUCER~~~\\.J rKFW-3-43 GFW-3-06~ r~~:~~~-8C ~~z:,~. ~~H-3-01 r 'II / J KFW-3-()7- ~oi'-....: KFH-3-0S-LS_ II) GFW-3-03 // KFW-3-03 GFH-3-08 ~ KFH-3-42 ~ KFH-3 ;:! r .,..... 9 ... tL,E. 0 I.) -KFW-3-H ? I'E."" .-,,"(.1' \\.J" ~_C-GFW-3 '? /'>S~~C;\\'O~~ ~ GFW-3-18 KFW-3-44/ KFH-3-05-Ls--M~ /1 Z/KFW-3-25 ~~_\\ 11'~KFW-3-21 KFW-3 ~1Il1 r KFW-3-26 ~-

1'<-

0 ~C... 0" KFW-3-05 _ ~ :.., r \\t'!GFW-3-23.,..... 90 I'" etC ~",E.... g) v- ~"'. ) .. fl", \\.... ~z KFH-3 1,bo't:? -1:;6'"" I4t~st I<FW-3-3S- ".,a<'+.:4-,

r..... <G;'.>!'-9, KFN-3-24 GFW-3-3??-, -\\7 HCV-3-66

~:;.¥.~.$-cf.s> ~. Zl- ~; ~~ GFW-3 1/ c,,~ KF~-3-23-[S_~vtr GFtI-3-24 ~ ~ KFW-3-23___ I ~KFW-3-27 ~~ KFH-3-22-LS-l f G;</-'~:l;~rs"~.1 \\ '-24" X 20" REDUCER KFtI-3-22-LS-2 GFW-3-2~O,,"-KFH-3-2B GFW-3-20 P/ L KFW-3-28-LS FCV-3-572 FCV-3-572-BC 002 .lOW,,, Rr.1 "(YISfC PIA AIUS uEMO R:;l !)7110~ DC! AHG F>EIotO'IEC CA..... IN~ Cl,j,SS,f,'::... T,r"', (AC¥INI$IRA1'Vf. Alloll$l()Nl ~2' X~-N-N L-.,~ K-KELLOGJ SHOPWELD UNIT NO. I G-GE FIELD HELD FEEDWATER WELD NO. ALL AID HISTORY RESEARCHED AT ROOO Nt V I CHANGt RH HJ.RCiiAtlE: ttk., ~"l""'Wlw I ':HlClI.l~ ittiiARt: tt!iNICA TENNESSEE VALLEY AUTHORITY 1-1 r---*\\-B""'R~O;;";WN;,;;:'S;.r=;F£RRY NUCLEAR PLANT i i UNIT 3 { FEEOWA TER SYSTEM HELD LOCA TIONS SU6HJ t'ir*n "PPRO'lfD ~b,P;~,-tDAJC~:Ii.: _ fl!.1.§:1-U-.§ 618 CCD c... a \\ fell-R')

A - LOOP GR-J-5J (OL) \\ fNIA-SE GR-J-5J-LS RWR-J-OOI-GOOI KR-J-45 \\. \\ ~'2F f rRWR-J-OOI-GOOJ KR-3-45-LS-1 -......... " \\ A O' N2F_/O":::; KR-3-4S-LS-2 ___', ~'!JO" 11', H '---- GR-3-S4 (OL) --.[ RWR-J-OOI-GOl3 ~'L"f.¥./~~ lJiS ~:'Z-1'~'OO" iii.;>;: ~O. GR-J-54-LS -"""'1 RWR-J-001-GOI5-..... ~-,;::;, '); .... ~ ~~..., ~'J",'C'oo./; GR-J-SS ",_ ~!\\i 00 ~- ~ ~ -Po. "'6'0 -: I C;01 0-0 OISJ

t:~ I

~~~001~ 01Z-..:c 001-~ .... c.> I I<tll< 001~C; ,G 9--- ~ REFERENCE DRAWINGS' TVA 47K1544-J GE 15JF754 KELLOGG BF 2-180 NOTE: THIS DRAWING SUPERSEDES CHM-21J9-C ALL SHEETS MATERIAL SPECIFICATIONS: AJ78. TP J04 4" X 0.337" NOM WALL THK. (55) 28" X I./J8" NOM. WALL THK. (SS) SUCTION 28" X 1.322" NOM. WALL THK. (SS) DISCHARGE SMOJ WPJI6NG 12" X 0.602" MIN. WALL 22" INTEGRAL REO. TEE 0.980" MIN. WALL 28" X 22" CROSS 0.980" MIN. WALL 28" X 24" INTEGRAL TEE X 1.272" MIN. WALL ASME CC-I (EQUI VALENT) ~<!, I I<tll<~~~ ,00' /;,0 0 ..... ") I ,~ 0'

r::ci I

~ ... ~ ~)) -9""-1> ~- RWR-J-00I-GOI6 2!: ~ ~

$V)1

~ <-I ~ KR-J-46 /RWR-J-001-G024 ~~ ~-"" 'J. '00" 'G) O"d' '4,0 ~ RWR-3-00/-G020 '.?" KR-J-46-LS _ I ~ J--RWR2~-.oO/-G022 ---I ~ -"'RWR-J-001-GOI7 ZZ ~ BENT INTEGRAL TEE --- W/12 "X22 " REO. (2 TYP.) SEE DETAIL A ~ ~RWR-J-001-GOI9 RWR-J-001-G02J ~ RWR-J-001-G021.../ SW-TPR-J-19 ~ 28" X 24" TEE..-/ RWR-3-001-G025......-/ 00 11 KR-J-02-LS """'" I (;, '-...:... 28' X 22" CROSS I-;-~ 11'/22" X 12" REO. I <;)(:l SEE DETAIL B ',I t::x: l<;)r-1'- I()~ IV)'" l;t~ [). t ir K;-~-_0047 KR-3-47 -...... I "INATION LINE KR-J-02 \\4R~g5f~fTA"'I~ ~ -- GR-3-0HS-1 KR-J-47-LS-1 'l~~ I~ r--.J1 ~ "- GR-3-0HS-2 KR-J-47-LS-2 ~ ~GR-J-OI 2~ ~ ~ GR-J-OJ (OL) GR-J-56 / \\ \\ "- FCV68-0J -BC Fm'-Ol FCV6B-03 FCV68-01-BC /../ !: 'c:::J GR-3-02 GR-J-57 k~:S-49. GR-3-01-LS GR-J-S7-LS KR-3-48 ---.... GR-3-04 N-N l' "- GR+5B KR+" ..Jt! I 1 BELD NO. KR-3-48-8L~L~_;l K _ KEllocJDS~O"'O,-J ""'T ND. KR-3-4 G _ GE nEt SYSTEM PCAI)AII ALL A/D HISTORY RESEARCHED AT ROOO DETAIL A - ONE PEICE SPECIAL FORGING DETAIL B - ONE PEICE SPECIAL FORG/!-. H'A I tf/" 000 I ISSUEO '0 CRUff: cw svP[AS[OU 45-0£51(;1"(0 ISI.ont..c~1 III AhO 10 OtI'H.. 1 AS COMSrltUCTt:O,UlV$ P[II IIIIIS W[uo 1114 "0'0$ lO$l A/O 110-112

NOV, CrWrtG£ 11['

OJ-I( J orlill J Dtl!.k, OSGM J Itvll'll "Af'poJ"I-u,POJ'N'nlI,s,:.r.. S I TENNESSEE VALLEY AUTHORI TY BROWNS FERRY NUCLEAR PLAN]" UN IT.3 R£CIRCULATION SYST£M wno LOCATIONS APPRovED D~!,'j;!J;4 CLe SCAl ( NTS SH£fr, OF 2 Surd) ~G~--- fi=.*tv 3-1 SI-0328-~: 00 CCO

B - LOOP RWR -COOl r RWR-J-002 KR-J-SO CR-J-S9 (OL) \\ f N1B-SE CR-J-S9-LS KR-J-SO-LS-l -.......""\\ \\ NIB 180' KR-J-SO-LS-2 _ ~~),~O* [ ~t~ /)<::l CR-J-60 (OL) ___ RWR-J-002-C01J......... ~~'1. ' ~ CR-J-60-LS ~l RWR-J-002-COI5_ ~ 5:l I CR-J-61 ",-" ~ ~ G010 - 02'-'- ~,O 12 ---'- N2A r -J-002-COOJ -1>.., ~. '? I4-IR ~ /i'.'J'o. -0/<. H f--- ('> ""-I>, i?,.:>_ tIi,.:>s 6: J-o. G"oo. -'?"-I>

i?"

'j:> <' 'Gl -....;:p; 0:::: U 006'./:'< /-:s:.. ......,;r ~;;; fr/llt' 02,GO ..,0 It'/llt'.. '1.,G001 / yOO G009 REFERENCE DRAWINGS: TVA 47K1S44-J GE ISJF754 KELLOGG BF 2-180 NOTE: THIS DRAWING SUPERSEDES CHM-21J9-C ALL SHEETS MATERIAL SPECIFICATIONS: AJ78, TP J04 4" X 0.JJ7" NOM WALL THK. (SS) 28" X 1.IJ8" NOM. WALL THK. (55) SUCTION 28" X I.J22" NOM. WALL THK. (55) DISCHARGE SMOJ WPJ76NG 12" X 0.602" MIN. WALL 22" INTEGRAL RED. TEE 0.980" MIN. WALL 28" X 22" CROSS 0.980" MIN. WALL 28" X 24" INEGRAL TEE X 1.272" MIN. WALL ASME CC-l (EQUIVALENT) 1111 ,0°'1.' IIII~ ~- RWR-J-002-COI6 GR-J-61-LS - i KR-J-Sl " KR-J-Sl-LS-2 ~ .. ~- ~-'" RWR-J-002-G022 ""-, RWR-J-002-G020-...--... T 22" /'~-l RWR-J-DD2-GD2J RWR-J-OD2-G021 /../ SW-TPR-J-21 r OR-J-'" I~ l::s ~-'" ./ RWR-J-002-G~18 ~~RWR-J-002-GOI7 2~ BENT INTEGRAL TEE ""-..... W/I2"X22 " RED. (2 TYP.) SEE DETAIL A ~~RWR-J-002-GOI9 i;;;............. 28" X 22" CROSS I_~ W/22" X 12" RED. "IQ'" SEE DETAIL B ',I t:5! lCr-I' _ I()~ I(J)'" I ;ten KR-J-26 ,r GR-J-JJ D'" .---KR-J-24 IQ... rR-J-6JB.. KR-J-Sl-LS-l ~ "i~ CR-J-62 / FCV68-77~_BC ~ FCV68-6J J /' GR-J- "R-J-6J-LS J 5J ___ v, KR-r GR-J-27 (OL) ~ 8" 1'--J"1' /' --- ,. DECON"",.", ~ '-= ~"'--'-- GR-3-2,",S*' flffcLl~j _____ "4 ~, OR.3':,;3-2,",S-2 KR-J-52.J ~1~~ L I \\ \\ GR-J- ~g~~~:~~ KR-3-52-LS-J [ 0 28 KR-3-52-L1-KR_3~;3-30 OR-3-27-L5 2 GR-J-64 ( J OL) XR-N-N K = KELLOGG SHOP WELD ~I I I I WELD NO. C = CE FIELD WELD ~ SYSTEM UNI T NO. ALL A/D H I STORY RESEARCHED AT ROOO DETAIL A - ONE PEICE SPECIAL FORGING DETAIL B - ONE PEICE SPECIAL FORG/~ "II..I t4/A 000 I ISS\\I£D 10 CRUTE ceo :!>VP[RSfOf5 As.onU'It{O IS._OlU_C_! Itt.u() 10 OlPICI "'S COfrISfItUCU:O $'AluS PtR finIS "YO 11:14 t70~5 )O~: "/0 IIO-It) C'ttAHQ[A[f "AI[ I Wilt I CMII.A I O~ IlIw~ li-IoI't1)I'~f'f)I'IJ'~t)1,",:.v S I TENNESSEE VALLEY AVTHORI TY BROWNS FERRY NUCLEAR PLANT UNI T.3 RECIRCULATION SYSTEM cco

6HS-3-08-L~ KHS-3-028 GH5-3-08 KHS-3-028-LS~ j( N3A-$E KH5-3-027............ ("<-{., ~ KHS-3-009 '1-~Ij/'4-~~"'I' CKHS-3-010 ~ '.,.>: ~ KHS-t -Ols, >~ :..J H - N30-sE KHS-3-027-L5-1 -KH5-3-023 ~~ :3: 8J GH5-3-34 ~KHS-3-022 11~~Hi.-i.-W03 GHS-3-34-LS GHS-3-07 ____ lllfl~i~3~~~Sj~ 1: rtfHS:3:~~~4 :~~:j:lg8-L5-I I ~r:.. u .2 018 ,~ KH5-3-108-L5-2 or",..,.... - ..... \\j) KH5-3-107 ~ \\~~ KH5-3-I07-LS KHS-3-002 IQ ~ KHS-3-002-LSI KHS-3-101 REFERENCE DRAWINGS: 47K1767 47W335-1 KELLOGG 729E229 NOTE: THIS DRAHING SUPfRCEDES CHH-2!40-C (SH. i) MATERIAL SPECIFICA T1(jN~S::-------i A-155 6R.KC70 CL.I. DR A-516 0.950" MIN. HALL. OR A-106 GR.8 SCH.80. OR A-234 SR.8 (SCH.80 OR 0.950* HIN. WALL), OR A-lOS GR. II (SCH. OR NIN. HALL TO SUIT PIPE), OR A-I06 GR.B SCH. 160 6" X 0.719* NOH. HALL (SCH. 160) 26" x 0.950* HIN. WALL NOTE: ALL FIELD WELDS WERE HADE 8Y TVA I\\I~ ~i ~ KHS-3-o02-LS2 ~\\ KHS-3-102 KHS-3-103 KHS-3-098 KHS-3-099 NOTE: J l~ ~~ \\\\ I KHS-i<J.P.P3_095

1. PIPE SEGHENTS CONTAINING TWO LONGITUDINAL 6HS 3 07 LS KH'l-3-096 SEAHS HILL BE IDENTIFIED AS:

~ KHS-3-097 KHS-3-092 (8ASE NCLD NO.) -LS-ID (DOWNSTREAH} KH5-3-024, \\ '\\ KHS-3-094 (SASE HELD NO.) -LS-IU (UPSTREAH) ASHE CC-l (EQUIVALENT) KHS-3-D24-LS~~ i) \\ \\\\ fF KHS-3-D93 (8ASE HELD NO.) -LS-2D (DOWNSTREAH) GHS-3-0~ '\\ I '~~~:j:8Z8 (8ASE HELD NO.)-LS-2U (UPSTREAM) }\\ ~ -!I IiKHS-3-091 THE -I.S-l SEAH WILL BE MJMERICALLY CLOSEST GHS-3-D6-LSI KHS-3-025 TO O* ON THE PIPE ANO THE -LS-2 SEAH WILL 8E GHS-3-D6-L52:>- /, KHS-3-025-LS-./ Y rKHSK~S:~~082_LSl NUMERICALLY FAf!THEFflOST FROH O* ON T~ PIPE. --.lh GHS-3-33 / / I ),.t:(KHS-3-0S2-LS2 (e.g. -L5-1 AT 130. ANO -LS-2 AT 310 ) ~Z~:~:80j~ KHS-3-026J~ 1 /KHS-:-~B2 _

>: < 2. PIPE SEGHENTS CONTAINING ONLY ONe KH§-'j-15

.!J I\\I~ / r ~:!s!3!l!sLS

~~

LO"GITUDINAL SEAH WILL BE IDENTIFIED AS: §::~:1:8H KHS-3-026-LS'/

rKHS-3-1~6~S I eM (BASE WELD NO.) -L5-0 (DOWNSTREAM) ro..<r.

KHS-3-0I2 r ./,,--KHSS 33 °08s5 I~:t (BASE WELD NO.) -LS-U (UPSTREAM) (l.,'!o I ~KH - 4 lor- .;;--KHS-3-083 0 ~~ GHS-3-05"'/ { KHS-3-088 ~.-~ ~1'Ij KHS- -087 I

~

.~ GHS-3-05-LS- - , ~KHS-~-086

~~

"-.. ~

I )0 KHS-3-104-LS I

0Q"i ~ GHS-3-31 ~ FCV-I-015 'hl~ l F"C~--OI5-BC I...

115 II r-

'5- -1 ,C")~ l J1 \\"'" L*g§3~JJ~ (. ~HfMf) ._ I~~ J1'-LGHf-Ef-O{-L~A --./I~-t t:I FCV-Ol-iJU GHS-3-32 FCV-OI-0U-BC FCV-I-052 GHS:3:32:LSI>--I-~./ '-GH5-3-03 FCV-OI-051 \\\\\\'-. GMsff!i';-052-BC GHS 3 32 LS2 1./ FCV-OI-05~-B \\ \\\\'KHS-3-II2-LS ,l. ~ * //\\ 6,115-3-02 ~V':,-I'- "'-3-0' f.XKl<S-3-1O. -GHS-3-31-1.5 ~" \\. ~f!!f!-:i!;W tl'JJtfNtfJJl' GHS-3-04-L51:>----;.'--t', / \\ "GH5!f.!!?8-LS D GH5-3-04-L5~2 .... \\" ~"-KHS-3-00I-LS GHS-3-28 ~6& 6H5-3-29 ~t1J= K-SHOP HELD .-L UN}T NO. 1 G-FIELD HELD HAIN sTEAH WELD NO. ~.... PCAOAU KH5-3-001 GHS-3-30"'/ GHS-3-30-LS1 ~ GH5-3-30-L52-;:7 .'LL. ~/D HISleR' ~-ESoARC... ~O f' 1<000 I AOUt" I llilk I I NIA I til" I./~. 'I ~~- _1915" "PI lilY! "'\\10.,," tll51' 164 M1YI I".... :.l ltV t.. 1( I OlIN I o-.:~ TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT S I UNIT 3 MAIN STEAM SYSTEM HELD LOCA TIONS DnA"'f/; P.'"18 'orr: T-9 ~--- ,ORA".:Hfi N:;J. ~t'.f.Y ."'.'~-!!i~ Eoe Gl..D3-I5I-0329-C 2"01 'Ar,.. ~-B-89 I ceo

~~E:j:gEE:tE:~ I<H5-3-055 GMS-3-17-L5 '4 -

0- __

I<HS-3-0y ~ REFERENCE DRAWINGS: 47K1767 47W33S-1 KELLOG 729E229 NOTE: THIS DRAWING SUPERCEDES CHH-2!40-C (SH. 2) 'Ar.:-SPEcrFICATIlJNs: r k-GH;;:::: '\\ -i. N3C-5E K. S-3-D5HS- ~ ... 32626_L5 ~ GHS- - ~ K.'H5-3-0BO "'-3-" ~ ~--r,","3':080-L5-2 A-155 GR.KC70 CL.!. OR A-516 0.950' MIN. WALL. OR A-106 GR.B SCH.BO. OR A-234 GFI.B (SCH.BO OR 0.950' MIN. WALU. OR A-lOS GR.II (SCH. OR MIN. WALL TO SUIT PIPE), OR A-I06 GR.S SCH. 160 ~ OBO-L5-4 232.~ ~ ~ LKHS- ~~ gJ19." XgAl. '!oiJ...ltll:!~* 1605 (fe" x 0 594' AI, 'All CH

80) 26" X 0.950' AlIN. 'ALL NOTES:

KH5-3-052 ------ KHS-3-07';/ GHS-3-12-b GHS-3-S2-LS1 GHS-3-S2-LS2~ NOTE:

1. PIPE SEGMENTS CONTAINING TWO LONGITUDINAL SEAMS WILL BE IDENTIFIED AS:

(BASE WELD NO.) -LS-10 (BASE WELD NO.) -LS-20 (BASE WELD NO.) -LS-JU (B~SE WELD NO.) -LS-2U (DOWNSTREAM) (DOWNSTREAM) (UPSTREAM) (UPSTREAM) THE -LS-l SEAM WILL 8E NUMRICALL Y CLOSEST TO O' ON THE PIPE AND THE -LS-2 SEAM WILL BE NUMERICALLY FARTHERMOST FROM O* ON THE PIPE. (e.g. -LS-1 AT 130*, AND -LS-2 AT 310 0 ) KHS-3-030. /' ,.. ~, ~6e .,\\....

2. PIPE SEGMENTS CONTAINING ONL Y ONE LONGITUDINAL SEAM WILL 8E IDENTIFIED AS:

'. (BASE WELD NO.) -LS-D (DCWNSTRAN) I I L Tr-N-N

- FIELO NELO I

~IT NO. I K = SHOP WELD ~ (BASE WELD NO.) -LS-U (UPSTREAM) r~:-'"iiS-NOlliJs (INNERRAO/(JS~ '--.!!,-:!l!.~!!! A",o._~~:!.C'-IR ____ J HiiiiSTEAH WELD NO. PeAOAJI . r KMS-3-079 ALL FIELD WELDS WERE HADE BY TVA ASHE CC-l (EQUIVALENT) KHS-3-062

~~

\\ ""5-3-22 05B-LSl 1 ~~ ...-I<H55_3_058_L52 1 1 ~ I<HS-3-063J 0 3" RCIC, (3" WELD - OUTSIDE SCOPE OF SECTION XI 151 PROGRAM SI-4,6.(;) / "KH, 8 lOr-KH5-3-05 5 11:ll... "_-3-062-1. 'tiii OETAIL "A"-"A U \\ / '~" 1 -t-+.s-,

~

I~rl 'ofI'.r.r. I' 16:e ~'<...

J...

I",,... \\ .J~' ~'!f,t;;M5fO' ~~ "A* '\\ -./'1'.... 027 11II.... ,,\\ v-". FCY-l-BC 4 ~ \\\\ 3" RCIC I<~: Ij r 'PEN. X-7S -.Li, \\.... J1H.S -Ll., 03. ~ I7\\: '-fr3-J* V----'f~-1-038-BC t ~~.l~-sc '--!!'f..':sIfBIFfftff' ~1fI1 (;115-3-11 ~~s ~-3-.1i~ (FL -L1 PEN. X-7C ~'- (;H5-3-.19-LS 6H5-3-19 I I FCV-0!-037 -BC FCY-0!-037 6HS-3-20 nV~N I kCl I 1'1,,, I 1"/1. 11l:,,- cca,55,;(" 10 (~t... 1t "r; !...:f'fR!O(crs....... cr";'c.-.tc,S,.llU*';'J CI') J...., 10 eft,,;' ~~ (l.l. GHS-3-21// GMS-3-2S-L51 GH5-3-21-L52 ""':::::-I<H5-3-056 ~KH5-3-057-LS1 KHS-3-057-LS2 AS I.,I6,IH\\JI,;IU.. Sl"'hr~ "tll RoWS WW RH 'IIfl.o~C!o j34: jA.f\\J j.l)d.t ~n c.. _~~ A£J c,;.u cnli C"~1t C~ b.~ * "'~;:l l oFP:: ~r ,:D KHS-3-057 ALL AID HISTORY RESEARCflED AT ROOD

> I TCNNESSEE VALLEY AUTHORITl BROWNS FERRY NUCLEAR PLA, UNIT 3 MAIN STEAM SYSTEM WELD LOeA TIc:,.r" Ol1Alif'l: PHB

'DATE: If-jj.."ir 'c1$r;5f!!,_-,:_ OA T£'o 6-13.. 69 cco

NOTE: o.o.s--? 0'-?.yk-?,..I: ,\\ 9 \\.552. I. PIPE SEGM<NTS CONTAINING TWO LONGITUDINAL SEAMS WILL BE IDENTIFIED AS: '..1'0.'0.,,<

0.

ff,<SS,< 0'-?.y-?, '" -t ,5 A(>.~'\\. 19 1t,!I !I,OOA 5 It'll 1'\\' Y 1 A Ek' 05 s.1'\\'II..;.~' ~,O 00 (BASE WELD NO.)-LS-ID (BASE WELO NO.)-LS-2D (BASE WELD NO.)-LS-IU (BASE WELD NO.)-LS-2U (DOWNSTREAM) (DOWNSTR£AM) (UPSTR£AU) (UPSTREAU) ..1,0. / ~05~.;.~' A' oz.,G oo~ ~ /./ 0 G'l1 !I'o oz.,G TH£ -LS-1 S£AM WILL B£ NUU£RICALLY CLOSEST TO 0' ON TH£ PIP£, AND TH£ -LS-2 S£AU WILL B£ NUMERICALL r FARTHERUOST FROU 0' ON THE PIPE. (tI.g. -LS-I AT lJO', AND -LS-2 AT Jl0'V 2 PIPE SECMENTS CONTAININC ONL r ONE

LONGITUDINAL S£AM WILL B£ ID£NTlFlED AS ¥ (BASE WELD NO.)-LS-D (DOWNSTREAU)

(BASE W£LO NO.)-LS-U (UPSTR£AM) ~,\\.5 ..,0 .;.~,J -09'- ~,O~ 05~';'~' ~.01i*\\.5 // \\\\'1-' ~,O ~~\\t ~..;.~'. I I~ ~ ~ I~cr!!.. I,~~ .... '1'" I;t:<:s'-,;, tl

~~""S))'

I~,. ~. ill / O~';'~~,!I,Of>A /:/0'1-'11 'l1A'\\4.SG )0,;:: /f~G'l1'".~,Oc; z.,\\.5':,

0.

~ "d";1- ~,O ~,\\.5

£ 0..£

/v'<' .;.~,J,0<- 11'.y~ 11'.y~

z

/05\\td..;.lt*~ .,£" 1 5" ~P' 5~', ,0,\\,\\.5'Z. j.lAfC~jrC....... ""'" -;; ~5' ._, __,0- ,_0'_/;" $1' ,"( o.-?%<!'o. ~'J.y<!,- '0."0.-, (l/.

.t6-o.-,?~'f"o. -s.:

~..I: 'J "\\.......--05 1'

0.

0. 'D?~ '0<

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\\ I \\ ~~., \\ ' O>b~ i '. ",($I FCV-~~5 ~~ ""\\,"V",, a-U. q, , \\ V L. J-478400-206 -:,. \\-/ - '\\ J-478400-206-IA 'q;.~ \\' fT.2S",2.4.J8 0 ) o~ \\v-s. \\ ~C'l \\ ~..,..~ \\ ~ -C'I ,\\ " =-s... -.j>-~ <:) \\ I \\ FCV-I-27 'C.~., \\ o;.b~ \\ \\~-s.. ~o \\- ~ .... ~,\\ .~ \\ "-:s;... -+-lt. ~ \\ "(.. ~\\, ~L..J-47B400-79 FCV-I-38..). ~-i ,J-47B400-79-IA c-,t<' (1.25",2.4J8") ~'" FCV-I-52 REFERENCE DRAWINGS BP-20J-3 0-47W400 SH. 1 & 5 DRAVO E-2479-1C-l TURBINE STOP VAL VES I ISI-0354-C fSH. 1) WELD MAP NOTE; THIS DRAWING SUPERSEDES CHM-2411-C SH. I MS-3-H-17 ( ) -MS-J-H-1J MS-J-H-1J-IA n.S") LEGEND RIGIO SUPPORT VARIABLE SUPPORT ANCHOR CALC(JLATION BRANCH PROJECT IDENTlfI[RS CO-OJ001-9104J6 CO-OJOOT-910569 CO-OJ001-910429 CO-OJOO 1-9 10421 ASME CC-2 (EQ()I VALENT) NOTES:
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~~REOUEST FOR RELIEF lSI-II DRAWING NO. 0-47W400 SH. I & 5~~
~~2. IN DETAIL A THE X CORRESPONDS TO THE SUPPORT NUMBER.~~
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OWNER: TENNESSEE VALLEY AUTIIORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 1101 MARKET STREET CHATTANOOGA, TEN1'<'ESSEE 37-\\.02 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. Key to computer weld/feature tracking system A. CYCLE-Refueling Cycle Number and Unit Number B. SYSTEM-System/Component CCWS-Closed Cooling Water System (Reactor Building Closed Cooling Water) CRDS-Control Rod Drive System CSS-Core Spray System EECW - Emergency Equipment Cooling Water System FPCS-Fuel Pool Cooling System FWS-Feedwater System HPCIS-High Pressure Coolant Injection System MSS-Main Steam System RCICS-Reactor Core Isolation Cooling System RECIR-Recirculation System RHRS-Residual Heat Removal System RHRSW-Residual Heat Removal Service Water System RPV-Reactor Pressure Vessel RWCU-Reactor Water Cleanup System C. Component NumberlIdentifier D. Drawing-lSI Drawing Number and sheet number from the Surveillance Instruction (SI-4.6.G) E. Exreq-ASME Section XI Code year and interval (See Note # 1) F. Category-Code Category G. Item Number-Code Item Number H. Exam Scheduled I. NDE METH-NondestrUctive Examination (NDE) Method ET-Eddy Current Test MT - Magnetic Particle Test PT - Penetrant Test RT - Radiography Test UT - Ultrasonic Test VT - Visual Test
OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. J. Calibration Standard-Ifrequired K. Exam Date-Date of Inspection L.Exam Report No.- Examination Report Number M. Exam Results - P - Pass R-Rejectable E-Evaluated acceptable for continued operation by Engineering O.COMMENTS NOTE (1): EXREQ Identifiers: 89E ASME Section XI Code 1989 Edition! Second Interval 96E ASME Section XI Code 1995 Edition, 1996 Addenda P07 Preservice Examination Cycle 10/ Second Interval B02 Examinations performed to NUREG-0313 & Generic Letter 88-01 for IGSCC detection B04 Weld inspection for Pipe Whip Protection B06 Examinations performed to the recommendation of GE SIL-571 OT1365 - Augmented examinations ofRPV Internals
OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CE.A. IT ANOOGA, TENNESSEE 37*J.02 PLANT: BROWNS FERRY NUCLEAR PLA1'lT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. APPENDIX VI
~~SUMMARY~~
OF INDICATIONS
OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PLANT P.O. boX 2000 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMl'v1ERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNlT: NOT REQUIRED. Summary of Indications Indications detected during the performance of examinations for Browns Ferry Nuclear Plant Unit 3/Cycle 10 were evaluated in accordance with approved written procedures. Generally, examination results yielded either No Recordable Indications (NRI) or Recordable Indications. Recordable Indications were evaluated to determine their origin. Indications determined to be of a geometric, metallurgical, or similar origin were typically dispositioned as non-relevant. Indications determined to be of a non-geometric, non-metallurgical, or similar origin were typically dispositioned as relevant. Such indications required additional measures such as further evaluation in accordance with AS ME Section XI acceptance standards, engineering analysis, repair, or replacement. NOINo. Code Component Indication Resolution Additional Cat. Identifier Description samples U3CIO-OOI. F*A 3*47B451HOOO2 Loose jam nut Evaluated Acceptable Not Required (No corrective measures required) U3CIO*OO2. C-B RHRG*3*06B-B Linear indication Cosmetic Not Required (No corrective measures required) U3CIO*OO3. F*A RHRG*3*12*B Loose Nut Evaluated Acceptable Not Required (No corrective measures required) U3CIO*OO4* F*A RHRG*3*13*B Loose bolting Evaluated Acceptable Not Required (No corrective measures required) U3CIO*005 ~ F*A RHRG*3*14*B Loose bolting (nuts) Evaluated Acceptable Not Required (No corrective measures required) U3ClO*008
~~F*A 3*47B465-483 Jam nut not flush Evaluated Acceptable Not Required (No corrective measures required)~~
U3CIO*OO9. B.Q*2 RBC-3*1 Leakage at bolted Evaluated Acceptable Not Required connection mating surface (No corrective measures required) U3CIO*Oll. F*A 3-47B400*114 loose nut Evaluated Acceptable Not Required (No corrective measures required) Not Required U3CIO-Ol2
~~F*A 3-47B452*3044 Unable to verify setting Evaluated Acceptable (No corrective measures required)~~
~~U3CIO*OI3~~
~~F*A 3-47B455*621 Missingjam nut Evaluated Acceptable Not Required (No corrective measures required)~~
There were no unacceptable indications detected. ADDITIONAL SAMPLES There were no additional samples required this outage.
t'.)\\VNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET -~ CHATTANOOGA, TEN"NESSEE 37-t02 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: 1\\OT REQUIRED. ATTACHMENT 1 INTEGRAL ATTACHMENTS EXAMINED IN CYCLE 7 RECEIVE AN ENGINEERING EVALUATION TO INCREASE CODE COVERAGE
O"':;~.,..:::::-~~, *. i~.$SSEE VALLEY AUTHORITY '-.. JIi"df?rCE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: TIIREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COtv1MERCIAL SERVICE DATE: MARCH I, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. ATTACHMENT 1 INTEGRAL ATTACHMENT WELDS EXAMINED IN CYCLE 7 RECEIVE AN ENGINEERING EVALUATION TO INCREASE CODE COVERAGE. During the Unit 3 Cycle 7 Refueling Outage in February 1997, three integral attachment welded supports in the Residual Heat Removal (RHR) System received a partial surface examination due to the limited access and/or interference's. The RHR integral attachment welds reported calculated coverage's of 85.2%, 88.9%, and 89.4% each in the Unit 3 Cycle 7 Refueling Outage NIS-I 90 Day lSI Report. In March of 2000, Browns Ferry Nuclear Plant Engineering Civil Design performed a calculation with reduced effective integral attachment weld lengths. This evaluation increased the code coverage to 100%. Reference Engineering Work Request EWR# 00-3-000-005 (RIMS # R21 00000314 001). COMPONENT ID RHR-3-146-IA 3-47B452-1385-IA 3-47B4521451-IA CODE COVERAGE CALCULATED FEBRUARY 1997 88.8% 89.4% 85.2% CODE COVERAGE CALCULATED MARCH 2000 100% 100% 100% lSI REPORT U3C7 R-013 R-048 R-018
OWN"ER: TENNF .-::y AUTHORITY PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 OFFICi. j{ POWER i 101 M,,'lRKET STREET CHATTANOOGA, TE1'.'NESSEE 37402 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. ATTACHMENT 2 UNIT 3 CYCLE 10 AUGMENTED EXAMINATION
~~SUMMARY~~
OWNER: TENNESSEE V ALLF OFFICE OF }1JCL~::. __ " i--' nOl MARKET STRE~T CHATTANOOGA, TENNESSEE 37-l02 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COrvtMERCIAL SERVICE DATE: MARCH I, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. This section includes augmented examinations performed to comply with NRC or TVA self-imposed requirements. Typical sources include generic letters, IE Bulletins, technical specifications, vendor recommendations, and industry experience. The following summarizes the augmented examinations performed during the Unit 3 Cycle 10 outage and references the corresponding paragraph in 3-SI-4.6.0. Paragraph 7.11.3 Augmented Examination of Austenitic Stainless Steel and Dissimilar Metal Welds . Susceptible to IGSCC CBWRVIP-75) Austenitic stainless steel and dissimilar metal circumferential welds in piping four inches or larger in nominal pipe diameter which contain reactor coolant at temperatures above 200 degrees F during power operation shall be examined. There was no new IGSCC identified in Cycle 10.
~~Reference:~~
~~BWRVIP-75 NUREG-0313 TOTAL NUMBER WELDS EXAMINED CATEGORY OF WELDS DURINGU3/CIO Outage A 71 0 B N/A N/A C 79 6 D 2 2 E 10 1* F N/A N/A G 2 2 (VT-2)~~
Category E weld GR-3-53 received a full examination for detection, in addition the known flaw location was examined to detennine flaw growth..There were no new flaws and the known flaw remains essentially unchanged.
OWNER: TENNESSEE VALLEY AUTHOru'" "Pi OFFICE OF NUCLEAR POWER 110 I MARKET STREET CHATTANOOGA, TENNESSEE 37402 . BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNiT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH I, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. Paragraph 7.11.4 Reactor Pressure Vessel Interior Augmented examinations of the RPVinterior components are performed in accordance with 0-TI-365, Revision 7, Reactor Pressure Vessel Internals Inspection (RPVII) Units 1,2 and 3. Core Sprav Downcomer Piping UT Examinations: TOTAL = 20 Downcomer "A": Welds P4A, P4B, P4C, P4D, P5, P5&6, P6&7, P7, P8A&P8B Downcomer "B": Welds P5, P5&6, P6&7, P7, PSA&PSB Downcomer "D": Welds P5, P5&6, P7, PSA&PSB
~~Reference:~~
BWRVIP-18, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines, EPRl TR-I06740 Examination Results: No indications ofIGSCC cracking observed. Core Sprav Piping Loop A and B Visual CEVT-l) Examinations: Total = 14 CS-PI-120, CS-P2-120, CS-AP3-11S, CS-BP3-122, CS-PI-240, CS-P2-240, CS-CP3-238, CS-DP3-242, CS-APSa-7.5, CS-APSb-7.5, CS-AP4d-7.5, Loop A& B welded repair clamp, and CSAD311S-AOI
~~Reference:~~
BWRVIP-18, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines, EPRl TR-I06740 Examination Results: No indications ofIGSCC. Core Plate Bolts Visual (VI-3) Examinations: Total = 34 CPHDB L-IO (0-90°) 9 bolts, CPHDB L-IO (90-ISOO) 9 bolts, CPHDB L-IO (1S0-2700) S bolts, CPHDB L-IO (270-360°) S bolts
~~Reference:~~
BWRVIP-25, BWR Core Plate Inspection and Flaw Evaluation Guidelines, EPRl TR-1072B4. Examination Results: No Recordable Indications noted.
OWNER: TE:N'NESSEE VALLEY AUTHORITY O~CEOFNUCLEARPOWER PLAl'IT: BJ)~"" \\VNC:"'-*'"SRRY NUCLEAR PLANT I" 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 L ~::"".t>.lUt", ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COtv1MERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NillvlBER FOR UNIT: NOT REQUIRED. Steam Drver Visual (VT -3) Examination: Total = 3 Weld: SDCW # 2 R, SDCW # 2 H, 'and SDCW # 2 L
~~Reference:~~
GE Letter Number BFSE 94-002 Examination Results: No Recordable Indications noted. Jet Pump Visual (EVT-l) Examinations: Total = 97 JP7-RB-Ia JPS-RS-7 JP3-WD-I JP4-RB-ld JP9-DF-l JP7-RB-Ie JPS-MX-2 JP4-IN-4 JP4-RB-2b JP9-WD-I JP7-RB-2a JPS-DF-I JP4-MX-2 JP4-RB-2d JPIO-IN-4 JP7-B-RS-S JPS-RB-la JP4-DF-l JP4-D-RS-S JPIO-MX-2 JP7-B-RS-9 JPS-RB-lc JP4-WD-l JP4-D-RS-9 JPIO-DF-l JP7-RS-6 JP6-RB-lb JP3-RB-la JP4-RS-7 JPIO-WD-I JPS-RB-lb JP6-RB-Id JP3-RB-Ic JP3 Set Screw SH JP9-RB-Ia JP8-RB-Id JPS-WD-I JP3-RB-2a JP3 Set Screw VS JP9-RB-Ic JPS-RB-2b JP7-RB-2c JP3-D-RS-S JP4 Set Screw SH JP9-RB-2a JPS-RB-2d JP3-IN-4 JP3-D-RS-9 JP4 Set Screw VS JP9-RB-2c JP8-B-RS-8 JP3-MX-2 JP3-RS-6 JP9-IN-4 JP9-G-RS-S JP8-B-RS-9 JP3-DF-I JP4-RB-Ib JP9-MX-2 JP9-G-RS-9 JPS-RO-Id JP9-RS-6 JPIO-RB-Ib JPIO-RB-ld JPIO-RB-2b JPIO-RB-2d JPIO-G-R8-S JPlO-G-RS-9 JPlO-RS-7 JPIS-IN-4 JPIS-lvlX-2 JPIS-DF-I JPIS-WD-l JPI6-IN-4 JP16-MX-2 JPI6-DF-l JP16-WD-I JPIS-RB-la JPlS-RB-lc JPlS-RB-2a JPlS-RB-2c JP15-H-RS-S JP15-H-RS-9 JPlS-RS-6 JP16-RB-lb JP16-RB-ld JPI6-RB-2b JP16-RB-2d JPI6-H-RS-S JP16-H-RS-9 JP16-RS-7 JP3-RB-2c JP7-IN-4 JP7-~1X-2 JP7-DF-l JP7-WD-l JP8-IN-4
~~Reference:~~
BWRVIP-41, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines, EPRI TR-108728. Examination Results: Jet Pump #4 Restrainer Bracket Assembly the wedge was otT center approximately.250" with no visible signs of movement. Acceptable for use_ determined to be original installation per GE Report.(RMS W79 020412 001). Recommendation to perform inspection each outage. Paragraph 7.11.5 Instrument Nozzle Safe-Ends GE SIL-571 Examinations: 1 UT and 7 VT-2 Perfonn UT and visual inspection of the stainless steel level instrumentation nozzle safe ends and stainless steel core differential pressure/standby liquid control (SLC) nozzle safe ends per the recommendation of Sll..-571. The recommendations are to perform a visual leak check of the safe ends during the drywellieak c1:wck effort performed each outage. Insulation removal is not necessary to perform the leak check. A UT inspection of the accessible areas of all the safe end base material shall be perfonned. Per GE Letter No. BFSE 94-005 these stainless steel safe ends should be UT inspected following 15 years of hot operation time andthen at a frequency of once every second 24 month fuel cycle or once every "third 18 month fuel cycle as applicable. The implementation interval shall start with the Unit 3 Cycle 5B refueling outage. Leakage inspections shall be perfonned as described during the Cycle 5B outage and during each subsequent refueling outage. Based on current 16-18 month refueling cycles UT inspection shall be performed during the Cycle 10 refueling outage and then at repeated at every third refueling cycle following Cycle 10. If24 month refueling cycles are utilized UT inspection shall be performed during the cycle 10 refueling outage and then at every second refueling cycle following cycle 10.
~~Reference:~~
GE SIL-577, Instrument Nozzle Safe-End Inspection and GE Letter Number BFSE 94-005
OWNER: TENNESSEE V ALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENl'i'ESSEE 37402 PLANT: BROWNSFERP.I.'r \\').PLANT P.O. B~Y. 2000 DECATUR, ALf~bAi.V1A J)609-2000 UNIT: THREE CERTIFICATE OF AUTHORlZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. Examination Results: UT examinations of Instrumentation Nozzle Safe-Ends N1IA-SE, N1IB-SE, NI2A-SE, NI2B-SE NI6A-SE and NI6B-SE were deferred to cycle IIfor RADCON/ALARA considerations. N10-SE was examined during cycle 10. No Relevant Indications noted on N10-SE. A VT-2 examination was performed on all seven nozzle safe-ends during the system leakage test and revealed no leakage. Paragraph 7.11.7 Weld inspection For Pipe Whip Protection Additional examinations shall be performed each inspection interval on selected circumferential pipe welds to provide additional protection against pipe whip in accordance with TSR 3.4.3.2. The following welds were ultrasonically examined during the cycle 10 refueling outage to locate evidence of pipe whip: TSCS-3-424 GFW-3-09 GFW-3-15 KFW-3-38 THPCI-3-070A GMS-3-06 GMS-3-24 DSRHR-3-04 RWCU-3-00 I-GO 16 RWCU-3-00 I-GO 17 RWCU-3-001-G01S Examination results: The examinations were acceptable.
OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR ~. 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 P.O. BOX 2000 DECATUR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMNtERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR:UNIT: NOT REQUIRED. ATTACHMENT 3 IWE-BFN CONTAINMENT INSERVICE INSPECTION PROGRAM
OWNER: TENNESSEE V f l,LEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATIJR, ALABAMA 35609-2000 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3ClO REFUELING OUTAGE
~~SUMMARY~~
REPORT Unit: BFN Unit 3 Refueling Outage: U3CI0 PeriodlInterval: Second Period of the First Interval Code of Record: ASME Section XI, 1992 Edition/1992 Addenda . Program Procedure: 0-TI-376, Revision 3 Summary of Examinations The records contained within the Unit 3 Cycle 10 Plant Report comprise the Containment Inservice examinations perfonned to implement the requirements of ASME Section XI Subsection IWE. The examinations are summarized as follows: Table lWE-2500-1, Examination Category E-A, Containment Surfaces The General Visual Examination of accessible containment surface areas was completed during U3C 1 O. This examination was perfonned by procedure 3-TI -173; a copy of the examination is incorporated in the plant report. This completes all examinations required by Code Category E-A Item Number E 1.11 for the Second Period. Visual examination of the drywell liner below the moisture seal barrier (MSB) was perfonned in areas where the MSB was excavated for replacement. Table IWE-2500-1, Examination Category E-C, Containment Surfaces Requiring Augmented Examination. During U3ClO, 100% of the Pressure Suppression Chamber exterior air/water interface area was examined. This is the only area currently identified as an augmented area for BFN Unit 3. This completes 50% of the examinations required by Category E-C Item Number E4.11 for the Second Period. Table lWE-2S00-1, Examination Category E-D, Seals, Gaskets, and Moisture Barriers A Pre-service VT -3 visual examination was perfonned on areas where the MSB was repaired. A. Request for Relief 2 / 3-CISI-l was submitted and approved to not perfonn VT-3 visual examinations on Code Category E-D Item ES.I0 (Seals) and Item ES.20 (Gaskets), Table lWE-2S00-1, Examination Category E-G, Pressure Retaining Bolting During U3CI0, a Pre-service VT-l visual examination was perfonned on 208 Drywell Head Flange Washers. 8 of2S bolted connections (32%) were examined in the first period. These were all the bolted connections that were disassembled. Table IWE-2S00-1, Examination Category E-P, All Pressure Retaining Components Appendix J Type B testing was completed on Containment Penetration Bellows and Torus Drain Bolted Connection in accordance with the Containment Leak Rate Program and 3-S1-4.7.A.2.g-2IBLa and 3-S1-4.7,A.2.g-3174h. Appendix J Type B testing was completed on the Drywell Personnel Airlock in accordance "ith the Containment Leak Rate Program and 3-SR-3.6.1.2.1. Appendix J Type B testing was completed on containment seals and gaskets in accordance with the Containment Leak Rate Program and 3-S1-4.7.A.2.g-2/FHa and 3-S1-4.7.A.2.g-2IELa.
OWNER: TENNESSEE VALLEY AUTHORITY OF;8CEOFNUCLEARPOWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: TIIREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CIO REFUELING OUTAGE
~~SUMMARY~~
~~REPORT~~
~~SUMMARY~~
OF INDICATIONS
OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLAt,H P.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COM1v1ERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONT A.IN1vIENT INSERVICE INSPECTION PROGRAM U3CI0 REFUELING OUTAGE
~~SUMMARY~~
REPORT The information contained in this report is provided in accordance with the requirements of IOCFRS0.55a(b)(2)(x)(A), evaluation of inaccessible areas, and IOCFRS0.55a(b)(2)(x)(D), evaluation for additional examinations, as they pertain to containment inservice examinations performed during the BFN . Unit 3 Cycle 10 refueling outage. The subject examinations were performed in accordance with ASME Section XI Subsection lWE, 1992 Editionll992 Addenda. BFN Unit 3 is in the second period of the first examination interval.
~~j~' *** :~.,~~
.~, :e:.~. OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATIANOOGA, TENNESSEE 37402 PLANT: BRO\\VNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COrv1MERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUNIBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CI0 REFUELING OUTAGE
~~SUMMARY~~
REPORT Report No: CISI-310-002 Component: PSC EXT 3-B-2 Conditionllndication: The pipe clamp on pipe support 47A452-808 has made contact with the exterior of . the Pressure Suppression Chamber (pSC). EVALUATION OF INACCESSmLE AREAS 10CFRSO.55a(b)(2)(x)(A) \\ (1) Description of the type and estimated extent of degradation, and the conditions that led to the degradation: The indication consisted of an approximately 2"x 2" area of missing paint caused by the clamp on pipe support 47A452-808 coming in contact with the surface of the PSC. There was no structural damage to the PSC caused by the clamp contact. Examination of the area revealed only damage to the coating of the PSC. (2) Evaluation of each area, and the result of the evaluation: There was no structural damage to the PSC caused by the contact of this clamp. The subject clamp is not in contact with the surface of the PSC. The contact between the PSC and the pipe clamp on this abandoned portion of the Residual Heat Removal system will be corrected by BFPER 02-003131-000. (3) Description of necessary corrective actions: The condition documented by NO! U3CIO-007 is the result of a voluntary examination. The condition of the pipe clamp contacting the PSC is an isolated instance and will be corrected by BFPER 02-003131-000. Therefore, no adverse condition exists that may be present in an inaccessible area. ADDITIONAL EXAMINATIONS 10CFR SO.S5a(b)(2)(x)(D) (1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation: The indication consisted of an approximately 2"x 2" area of missing paint caused by the clamp on pipe support 47A452-808 coming in contact with the surface of the PSC. There was no structural damage to the PSC caused by the clamp contact. Examination of the area revealed only damage to the coating of the PSC. (2) The acceptability of each flaw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components: There was no structural damage to the PSC caused by the contact of this clamp. The subject clamp is not in contact with the surface of the PSC. The contact between the PSC and the pipe clamp on this abandoned portion of the Residual Heat Removal system will be corrected by BFPER 02-003131-000
.~,- . Q~':' ::'R: TENNESSEE VALLEY AUTHORITY ".; T~-,'.,',', OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COM:MERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3C10 REFUELING OUTAGE
~~SUMMARY~~
REPORT (3) A description of the necessary corrective actions: The condition documented by NOI U3C10-007 is the result of a voluntary examination. The condition of the pipe clamp contacting the PSC is an isolated instance and will be corrected by BFPER 02-003131-000.
~~4) The number and type of additional examinations to ensure detection of similar degradation in similar components:~~
No additional examinations warranted.
r ... _,E VALLEY AUTHORITY v': nL;~ V~: NUCLEAR POWER 1101 MARKET STREET CHATIANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTIIORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CIO REFUELING OUTAGE
~~SUMMARY~~
REPORT Report No's: CISI-310-7 through CISI-310-22 Components: PSC EXT-3-B-l through 3-B-16 ConditionlIndication: Randomly chipped areas. Light rust on coated and non-coated surfaces_ Random dings and scratches. EVALUATION OF INACCESSmLE AREAS 10CFR50.SSa(b)(2)(x)(A) (1) Description of the type and estimated extent of degradation, and the conditions that led to the degradation: Random chipping, light rust, dings and scratches in various locations on the exterior surface of the suppression chamber. The conditions noted are expected conditions based on the age and service life of the containment. (2) Evaluation of each area, and the result of the evaluation: There is no degradation that affects the structural integrity or containment function of the vessel. The base metal condition is good with no notable corrosion or wan loss. (3) Description of necessary corrective actions: The subject indications have been evaluated for continued service without repair_ Therefore, no adverse condition exist that may be present in an inaccessible area_ ADDITIONAL EXAMINATIONS 10CFR SO.SSa(b)(2)(x)(D) (1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation: Random chipping, light rust, dings and scratches in various locations on the exterior surface of the suppression chamber. The conditions noted are expected conditions based on the age and service life of the containment. (2) The acceptability of each flaw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components: The subject indications have been evaluated for continued service without repair. The conditions noted are ex-pected conditions based on the age and service life of the containment. (3) A description of the necessary corrective actions: None of the deficiencies noted affect the structural integrity or leak tightness of the containment These deficiencies will be addressed by BFNPER 02-003109-000. (4) The number and type of additional examinations to ensure detection of similar degradation in similar components: NOI U3CIO-006 is the result of voluntary Vf-l examinations performed in areas where coating and irregularities were noted in 3-TI-173 and 0-TI-417. Therefore, additional examinations are not warranted.
OWNER: TENNESSFi";: '.~.~ .:\\..UTHORITY OFFICE OF t. ..' ::., i'OWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COM:MERCIAL SERVICE DATE: MARCH I, 1977 NATIONAL BOARD l-lUMBERFOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM: U3CIO REFUELING OUTAGE
~~SUMMARY~~
REPORT Report No: CISI-310-023 through CISI-310-032 Component: DW LNR-3-IA Condition/Indication: Discoloration, rust and pitting. EVALUATION OF INACCESSmLE AREAS 10CFRSO.SSa(b)(2)(x)(A) (1) Description of the type and estimated extent of degradation, and the conditions that led to the degradation: NO! U3CIO-OIO documents indications noted during the VT -3 examination of the steel containment vessel surface in areas where the moisture seal barrier has been excavated for replacement. This examination was perforined to detennine the condition of the surface in this normally inaccessible area. (2) Evaluation of each area, and the result of the evaluation: The subject indications have been evaluated to be acceptable. There is no degradation which affects the structural integrity or containment function of the steel containment vessel. (3) Description of necessary corrective actions: The conditions noted are expected conditions with respect to the age and service conditions of the component. The Moisture Seal Barrier (MSB) has been examined and defective portions are being replaced. Therefore, no adverse condition exist which may be present in inaccessible areas. ADDITIONAL EXAMINATIONS 10CFR SO.SSa(b)(2)(x)(D) (1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation: NO! U3CIO-OIO documents indications noted during the VT-3 examination of the steel containment vessel surface in areas where the moisture seal barrier has been excavated for replacement. The examination was performed to determine the condition of the surface in this normally inaccessible area. (2) The acceptability of each flaw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components: The subject indications have been evaluated to be acceptable. There is no degradation which affects the structural integrity or containment function of the steel containment vessel. (3) A description of the necessary corrective actions: The condition documented is not considered to be a defective condition with respect to the containment vessel. The condition of moisture intrusion into this area is being corrected by repair of the MSB. (4) The number and type of additional examinations to ensure detection of similar degradation in similar components: The condition of moisture intrusion into this area is being corrected by repair of the MSB. Therefore, additional examinations are not warranted.
r-----------~ --' OWNER: TENNESSEE VALLEY A~i-OFFICE OF NUCLEAR Pu,~. ~L" .~ 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COM:MERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT IN SERVICE INSPECTION PROGRAM U3CI0 REFUELING OUTAGE
~~SUMMARY~~
REPORT Report No: CISI-310-034 Component: DW LNR-3-4 ConditionlIndication: Paint cracked on penetration weld (3-X-16B) . EVALUATION OF INACCESSmLE AREAS 10CFRSO.55a(b)(2)(x)(A) (1) Description of the type and estimated extent of degradation, and the conditions that led to the degradation: A crack in the coating at drywell penetration 3-X-16B weld was identified during the performance of the General Visual inspection (3-TI-173). This examination was performed to satisfy the requirements of IWE 2500(b), examination of coatings prior to removal. (2) Evaluation of each area, and the result of the evaluation: The indication noted consisted of a crack of the applied coating on the penetration weld. The coating was removed and the exposed liner surface and weld in this area was inspected and is in good condition with no reportable conditions. (3) Description of necessary corrective actions: There is no degradation that affects the structural integrity or leak tightness of the steel containment vessel. The conditions noted are expected based on the age and service conditions of the component. Therefore, no adverse condition exists that may be present in inaccessible areas. ADDITIONAL EXAMINATIONS 10CFR 50.55a(b)(2)(x)(D) (1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation: A crack in the coating at drywell penetration 3-X-16B weld was identified during the performance of the General Visual inspection (3-TI-173). This examination was performed to satisfy the requirements of IWE 2500(b), examination of coatings prior to removal.
OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402
~~":vN"S FERRY NUCLEAR PLANT~~
~. tlOX 2000 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMtv1ERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CIO REFUELING OUTAGE
~~SUMMARY~~
REPORT (2) The acceptability of each flaw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components: There is no degradation that affects the structural integrity or leak tightness of the steel containment vessel. The conditions noted are e>..-pected based on the age and service conditions of the component. (3) A description of the necessary corrective actions: Areas of coating failure (e.g., delamination, peeling, etc.) were scraped back until proper coating adhesion (sound coating) was obtained. In areas where the topcoat has been scraped back to sound coating, the zinc primer is intact and will provide corrosion protection for the primary containment boundary. Re-coating will be done in accordance with MAI-5.3 during future outage maintenance work. (4) The number and type of additional examinations to ensure detection of similar degradation in similar components: The condition documented is not considered to be a defective condition with respect to the steel containment vessel. The condition has been addressed by removal of the coating and examination of liner in the affected areas. Therefore, additional examinations are not warranted.
OWNER: TENNESSEE VALLEY AUTHORlTY OFFICE OF NUCLEAR POWER PLANT: BF.f' P.L '\\lUCLEARPLANT 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. CO}..1MERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CIO REFUELING OUTAGE SUM.MARY REPORT Report No: CISI-310-035 Component: DW LNR 3-3 ConditionlIndication: Damage areas to the Drywell Interior Liner surface. . EVALUATION OF INACCESSmLE AREAS 10CFR50.SSa{b)(2)(x)(A) (1) Description ofthe type and estimated extent of degradation, and the conditions that led to the degradation: Several small gouges in the primary containment liner and scratches in the coating. The damage was caused by an HV AC supply duct which ruptured and then the debris repeatedly struck the liner surface due to air flow in the duct. The cause of the duct rupture is unknown. The condition resulted in fretting of the liner surface. (2) Evaluation of each area, and the result of the evaluation: The data collected (mechanical dimensions on gouges and thickness measurements on liner) dated 4/3/02 has been evaluated and found to be acceptable. The evaluation is documented in calculation CD-Q0999-970 114. (3) Description of necessary corrective actions: The gouges in the steel liner have been blended out and the base metal re-coated. The damage to the liner has been evaluated by calculation CD-Q0999-970 114 which concluded that the condition is acceptable without weld repair. ADDITIONAL EXAMINATIONS 10CFR SO.SSa{b)(2)(x)(D) (1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation: Several small gouges in the primary containment liner and scratches in the coating. The damage was caused by an HVAC supply duct which ruptured and then the debris repeatedly struck the liner surface due to air flow in the fluct. The cause of the duct rupture is unknown. The condition resulted in fretting of the liner surface. (2) The acceptability of each flaw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components: The data collected (mechanical dimensions on gouges and thickness measurements on liner) dated 4/3/02 has been evaluated and found to be acceptable. The evaluation is documented in calculation CD-Q0999-970 114. (3) A description of the necessary corrective actions: The gouges in the steel liner have been blended out and the base metal re-coated. The damage to the liner has been evaluated by calculation CD-Q0999-970 114 which concluded that the condition is acceptable without weld repair.
OWNER: 1ENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER 110 1 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY lo** P.O. BOX 2000 DECATIJR, ALABAMA 35602 UNIT: TIIREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COM:MERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. ANT BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3C10 REFUELING OUT AGE
~~SUMMARY~~
REPORT (4) The number and type of additional examinations to ensure detection of similar degradation in similar components: Engineering personnel inspected the remaining HV AC duct work with similar design configuration and determined that no other similar damage has occurred. No further corrective actions are required.
OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PL ~ *.....:j. 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 P.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CI0 REFUELING OUT AGE Sillvflv1ARY REPORT Report No: CISI-310-036 Component: DW LNR 3-6 ConditionlIndication: Areas flaking or delamination . EVALUATION OF INACCESSIBLE AREAS 10CFR50.55a(b)(2)(x)(A) (1) Description of the type and estimated extent of degradation, and the conditions that led to the degradation: NOI U3CI0-016 documents indications noted during the VT-3 examination of the containment vessel surface in areas identified for coating removal. The indications noted consist of areas of flaking or delaminating of the applied coating. This examination was performed to satisfy the requirements of IWE 2500(b), examination of coatings prior to removal. (2) Evaluation of each area, and the result of the evaluation: The exposed liner surface in these areas has been inspected after coating removal and is in good condition with no reportable conditions. There is no degradation that affects the structural integrity or leak tightness of the containment vessel. (3) Description of necessary corrective actions: There is no degradation that affects the structural integrity or leak tightness of the containment vessel. The conditions noted are expected based on the age and service conditions of the component. Therefore, no adverse condition exists that may be present in inaccessible areas. ADDITIONAL EXAMINATIONS 10CFR 50.55a(b)(2)(x)(D) (1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation: NOI U3CI0-016 documents indications noted during the VT-3 examination of the containment vessel surface in areas identified for coating removal. The indications noted consist of areas of flaking or delaminating of the applied coating. This examination was performed to satisfy the requirements. of IWE 2500(b), examination of coatings prior to removal. (2) The acceptability of each flaw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components: There is no degradation that affects the structural integrity or leak tightness of the containment vessel. The conditions noted are expected based on the age and service conditions of the component. (3) A description of the necessary corrective actions: Areas of coating failure (e.g., delamination, peeling, etc.) were scraped back until proper coating adhesion (sound coating) was obtained. In areas where the topcoat has been scraped back to sound coating, the zinc primer is intact and will provide corrosion protection for the primary containment boundary. Re-coating will be done in accordance with MAI-5.3 during future outage maintenance work.
OWNER: TENNESSEE VALLEY AUTHORITY O~CEOFNUCLEARPOWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY 'NtJCLEAR PLANT P.O. BOX 2000 DECA'fUR, ALABAMA 35602 UNIT: TIIREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CI0 REFUELING OUTAGE
~~SUMMARY~~
REPORT (4) The number and type of additional examinations to ensure detection of similar degradation in similar components: The condition documented is not considered to be a defective condition with respect to the containment vessel. The condition has been addressed by removal of the coating and examination of liner in the affected areas. Therefore, additional examinations are not warranted.
OWNER: TENNESSEE VALLEY AUTIIORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHAIT ANOOGA, TENNESSEE 37402 UNIT: TIIREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3ClO REFUELING OUTAGE
~~SUMMARY~~
REPORT Report No: CISI-310-037 Component: DW LNR-3-5 Condition!lndication: Areas flaking or delamination EVALUATION OF INACCESSmLE AREAS 10CFRSO.55a(b)(2)(x)(A) (1) Description of the type and estimated extent of degradation~ and the conditions that led to the degradation: NO! U3CI0-017 documents indications noted during the VT-3 examination of the containment vessel surface in areas identified for coating removal. The indications noted consist of areas of flaking or delaminating of the applied coating. This examination was performed to satisfy the requirements of IWE 2500(b), examination of coatings prior to removal. (2) Evaluation of each area~ and the result of the evaluation: The exposed liner surface in these areas has been inspected after coating removal and is in good condition with no reportable conditions. There is no degradation that affects the structural integrity or leak tightness of the steel containment vessel. (3) Description of necessary corrective actions: There is no degradation that affects the structural integrity or leak tightness of the steel containment vessel. The conditions noted are expected based on the age and service conditions of the component. Therefore, no adverse condition exists that may be present in inaccessible areas. ADDITIONAL EXAMINATIONS 10CF~50.55a(b)(2)(x)(D) (1) Description of each flaw or area~ including the extent of degradation~ and the conditions that led to the degradation: NO! U3CIO-017 documents indications noted during the VT-3 examination of the containment vessel surface in areas identified for coating removal. The indications noted consist of areas of flaking or delaminating of the applied coating. This examination was performed to satisfy the requirements of IWE 2500(b), examination of coatings prior to removal.
I( "~". OWNER: TENNESSEE VALLEY AUTHORITY OBRCEOFNUCLEARPOWER 1101 MARKET STREET CHATIANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH I, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CIO REFUELING OUTAGE
~~SUMMARY~~
REPORT (2) The acceptability of each flaw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components: There is no degradation that affects the structural integrity or leak tightness of the steel containment vessel. The conditions noted are expected based on the age and service conditions of the component. (3) A description of the necessary corrective actions: Areas of coating failure (e.g., delamination, peeling, etc.) were scraped back until proper coating adhesion (sound coating) was obtained. In areas where the topcoat has been scraped back to sound coating, the zinc primer is intact and will provide corrosion protection for the primary containment boundary. Re-coating will be done in accordance with MAI-5.3 during future outage maintenance work. (4) The number and type of additional examinations to ensure detection of similar degradation in similar components: The condition documented is not considered to be a defective condition with respect to the steel containment vessel. The condition has been addressed by removal of the coating and examination of liner in the affected areas. Therefore, additional examinations are not warranted.
OWNER: TENNESSEE VALLEY AUTHORITY OFFICE OF NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 110 1 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COrvlMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3ClO REFUELING OUTAGE
~~SUMMARY~~
REPORT Report No: CISI-310-038 Component: DW LNR 3-4 ConditionlIndication: Areas flaking or delamination . EVALUATION OF INACCESSmLE AREAS IOCFRSO.SSa(b)(2)(x)(A) (I) Description of the type and estimated extent of degradation, and the conditions that led to the degradation: NO! U3ClO-018 documents indications noted during the VT-3 examination of the containment vessel surface in areas identified for coating removal. The indications noted consist of areas of flaking or delaminating of the applied coating. This eXamination was performed to satisfy the requirements of lWE 2500(b), examination of coatings prior to removal. (2) Evaluation of each area, and the result of the evaluation: The exposed liner surface in these areas has been inspected after coating removal and is in good condition with no reportable conditions. There is no degradation that affects the structural integrity or leak tightness of the steel containment vessel. (3) Description of necessary corrective actions: There is no degradation that affects the structural integrity or leak tightness ofthe steel containment vessel. The conditions noted are expected based on the age and service conditions of the component. Therefore, no adverse condition exists that may be present in inaccessible areas. ADDITIONAL EXAMINATIONS 10CFRSO.S5a(b)(2)(x)(D) (1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation: NOI U3CI0-018 documents indications noted during the VT-3 examination of the containment vessel surface in areas identified for coating removal. The indications noted consist of areas of flaking or. delaminating of the applied coating. This examination was performed to satisfy the requirements of IWE 2500(b), examination of coatings prior to removal. (2) The acceptability 'of each flaw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components: There is no degradation that affects the structural integrity or leak tightness of the steel containment vessel. The conditions noted are expected based on the age and service conditions of the component. (3) A description of the necessary corrective actions: Areas of coating failure (e.g., delamination, peeling, etc.) were scraped back until proper coating adhesion (sound coating) was obtained. In areas where the topcoat has been scraped back to sound coating, the zinc primer is intact and will provide corrosion protection for the primary containment boundary. Re-coating will be done in accordance with MAI-5.3 during future outage maintenance work.
, "'ENNESSEE VALLEY AUTHORITY OF8CEOFNUCLEARPOWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COtvfMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3C10 REFUELING OUTAGE
~~SUMMARY~~
REPORT (4) The number and type of additional examinations to ensure detection of similar degradation in similar components: The condition documented is not considered to be a defective condition with respect to the steel containment vessel. The condition has been addressed by removal of the coating and examination of liner in the affected areas. Therefore, additional examinations are not warranted.
OWNER: Tfr> *n:;'s:**'.:V ALLEY AUTHORITY OF I.; '>J Ji'NUCLEAR POWER PLANT: BROWNS FERRY NUCLEAR PLAl"IT P.O. BOX 2000 110 1 MARKET STREET CHATTANOOGA, TENNESSEE 37402 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CI0 REFUELING OUTAGE
~~SUMMARY~~
REPORT Report No: CISI-310-039 Component: DW LNR 3-3 Conditionllndication: Areas flaking or delamination . EVALUATION OF INACCESSmLE AREAS 10CFRSO.55a(b)(2)(x)(A) (1) Description of the type and estimated extent of degradation, and the conditions that led to the degradation: NOI U3C 10-0 19 documents indications noted during the VT -3 examination of the containment vessel surface in areas identified for coating removal. The indications rioted consist of areas of flaking or delaminating of the applied coating. This examination was performed to satisfy the requirements of IWE 2500(b), examination of coatings prior to remova1. (2) Evaluation of each area, and the result of the evaluation: The exposed liner surface in these areas has been inspected after coating removal and is in good condition with no reportable conditions. There is no degradation that affects the structural integrity or leak tightness of the steel containment vessel. (3) Description of necessary corrective actions: There is no degradation that affects the structural integrity or leak tightness of the steel containment vessel. The conditions noted are expected based on the age and service conditions of the component. Therefore, no adverse condition exists that may be present in inaccessible areas. ADDITIONAL EXAMINATIONS 10CFR SO.SSa(b)(2)(x)(D) (1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation: NOI U3CI0-019 documents indications noted during the VT-3 examination of the containment vessel surface in areas identified for coating removal. The indications noted consist of areas of flaking or' delaminating of the applied coating. This examination was performed to satisfy the requirements of IWE 2500(b), exatpination of coatings prior to removal. (2) The acceptability of each flaw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components: There is no degradation that affects the structural integrity or leak tightness of the steel containment vessel. ~e conditions noted are expected based on the age and service conditions of the component. (3) A description of the necessary corrective actions: Areas of coating failure (e.g., delamination, peeling, etc.) were scraped back until proper coating adhesion (sound coating) was obtained. In areas where the topcoat has been scraped back to sound coating, the zinc primer is intact and will provide corrosion protection for the primary containment boundary. Re-coating will be done in accordance with MAl-5.3 during future outage maintenance work.
OWNER: TENNESSEE VALL,".' AIJ,!-Tf"\\RlTY OFFICE OFNUC. J~Fr.: 1101 MARKET STREriT CHATTANOOGA, TENNESSEE 37402 PLANT: BROWNS FERRY NUCLEAR PLANT P.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMMERCIAL SERVICE DATE: MARCH 1, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CI0 REFUELING OUTAGE
~~SUMMARY~~
REPORT (4) The number and type.of additional examinations to ensure detection of similar degradation in similar components: The condition documented is not considered to be a defective condition with respect to the steel containment vessel. The condition has been addressed by removal of the coating and examination of liner in the affected areas. Therefore, additional examinations are not warranted.
OWNER: TENNESSEE VALLEY AUTHORIT' n; OFJ8CE OF NUCLEAR POWER 1101 MARKET STREET CHATTANOOGA, TENNESSEE 37402 . '.~. BROWNS FERRY NUCLEAR PLANT F.O. BOX 2000 DECATUR, ALABAMA 35602 UNIT: TIIREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COrvlMERCIAL SERVICE DATE: MARCH I, 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CIO REFUELING OUTAGE
~~SUMMARY~~
REPORT (4) The number and type of additional examinations to ensure detection of similar degradation in similar components: The condition documented is not considered to be a defective condition with respect to the steel containment vessel. The condition has been addressed by removal of the coating and examination of liner in the affected areas. Therefore, additional examinations are not warranted. I I
OWNER: TENNESSEE VALLEY AUTHORITY PLA}r ERr" 'NS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER 'J.... 2000 1101 MARKET STREET uEC_f'UR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT: THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED. COMrvlERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED. BFN CONTAINMENT INSERVICE INSPECTION PROGRAM U3CIO REFUELING OUTAGE
~~SUMMARY~~
REPORT (4) The number and type of additional examinations to ensure detection of similar degradation in similar components: The condition documented is not considered to be a defective condition with respect to the steel containment vessel. The condition has been addressed by removal of the coating and examination of liner in the affected areas. Therefore, additional examinations are not warranted. I I I
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), SECTION XI, REPAIR AND REPLACEMENTS PROGRAM
~~SUMMARY~~
REPORT (NIS-2) FOR CYCLE 10 OPERATION (SEE ATTACHED)
BROWNS FERRY NUCLEAR PLANT UNIT 3 CYCLE 10 ASME SECTION XI NIS-2 DATA REPORT
OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS APPENDIX I ______ Summary of Repair and Replacement Activities APPENDIX II ______ Form NIS-2 Owner's Report For Repairs or Replacements I I I
Owner: TENNESSEE VALLEY AUlHORITY 1101 Market Street Chattanooga, TN 37402-2801 Unit: Three Commercial Service Date: March 1, 1977 National Board Number for Unit: Not Required Plant: Browns Ferry Nuclear Plant P. O. Box 2000-Decatur, AL 35609-2000 Certificate of Authorization: Not Required APPENDIX I
~~SUMMARY~~
OF REPAIR AND REPLACEMENT ACTIVITIES
Owner: TENNESSEE VALLEY AUTHORITY 1101 Market Street Chattanooga, TN 37402-2801 Unit: Three Commercial Service Date: March 1, 1977 Plant: Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, AL 35609-2000 Certificate of Authorization: Not Required National Board Number for Unit: Not Required WID SYS ORG CLASS ACTIVITY 00-004454-000 1 MAINT 2 REPAIR 95-022749-001 75 MAINT 2 REPLACEMENT 01-005329-000 3 MAINT 1 REPLACEMENT 01-005496-000 1 01-005497-000 1 01-005498-000 1 01-005499-000 1 01-005500-000 1 00-004415 -000 74 MAINT 2 REPLACEMENT 01-005376-000 2 01-005386-000 2 01-005388-000 2 01-005505-000 2 01-005502-000 75 MAINT 1 REPLACEMENT 01-005504-000 1 99-006554-000 1 MAINT 1 REPLACEMENT 01-007381-000 1 01-007370-000 1 MAINT 2 REPLACEMENT 02-003703-000 2 02-003225-000 69 MAINT 1 REPLACEMENT 02-003382-000 1 01-008132-000 73 MAINT 2 REPLACEMENT
O"vner: TENNESSEE VALLEY AUTHORITY 1101 Market Street Chattanooga, TN 37402-2801 Unit: Three Commercial Service Date: March I, 1977 Plant: Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, AL 35609-2000 Certificate of Authorization: -Not Required National Board Number for Unit: Not Required . WID SYS ORG CLASS ACTIVITY 01-008135-000 71 MAINT 2 REPLACEMENT 99-003420-000 63 MAINT 2 REPLACEMENT T40978 77 TVA 2 REPLACEMENT 98-014466-000 02-002122-000 74 MAINT 2 REPAIR 00-003996-000 3 MAINT 1 REPLACEMENT 50729A 85 TVA 2 REPLACEMENT 01-005501-001 01-005501-002 01-005501-005 50287A 73 TVA 2 REPLACEMENT 01-012431-000 NIS-2 OWNER'S REPORT FROM U3C9 99-0 I 00 16-000 69 MAINT 1 REPLACEMENT 99-010069-000 1
Owner: TENNESSEE VALLEY AUTHORITY 1101 Market Street Chattanooga, TN 37402-2801 Unit: Three Commercial Service Date: March 1, 1977 National Board Number for Unit: Not Required LEGEND WID - Work Implementing Document Plant: Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, AL 35609-2000 Certificate of Authorization: -Not Required Example: A99999A or SOOOOA refers to a Design Change Notice 99-999999-999 refers to a Work Order SYS-System 1 - Main Steam 3 - Reactor F eedwater 8 - Turbine Drains 10 - Reactor Drains, Vents and Blowdown 63 - Standby Liquid Control 68 - Reactor Water Recirculation ORG - Organization which performed the WID MAINT - TVA's Maintenance Organization GE - General Electric Company 69 - Reactor Water Cleanup 71 - Reactor Core Isolation Cooling 73 - High Pressure Coolant Injection 74 - Residual Heat Removal 75 - Core Spray 85 - Control Rod Drive 92 - Neutron Monitoring TVA - Work performed by Stone and Webster Engineering Corporation utilizing TVA's Quality Assurance Program and procedures CLASS - Refers to ASNIE Code Class 1 or 2 ACTIVITY - Classifies work activity as being repair or replacement as denoted on NIS-2 Form
Owner: TENNESSEE VALLEY AUTHORITI 1101 Market Street Chattanooga, TN 37402-2801 Unit: Three Commercial Service Date: March 1, 1977 National Board Number for Unit: Not Required Plant: Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, AL 35609-2000 Certificate of Authorization: Not Required APPENDIX II FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~OWner Tennessee Valley Authority (TVA) Date January 26, 2001 Name 1101 Market Street Chattanooga, TN 37402-2801 Sheet of Address~~
2.
~~Plant Browns Ferry Nuclear Plant (BFN) Unit 3 Name P. O. Box 2000, Decatur, Al 35609-2000 Work Order eNO) 00-004454-0OO Address Repair Organization P.O. No.* Job No.* etc.~~
3.
~~Work Performed by TVA-BFN Type Code Symbol Stamp N/A~~

~~~N~am-e-----------------~~

~~P. O. Box 2000, Decatur, Al 35609-2000 Authorization No. N/A Address Expiration Date N/A~~
4.
~~Identification of System System 001, Main Steam System~~
~~5. (a)~~
~~Applicable Construction Code USAS B31.1.0 19 67'~~
~~Edition, N/A (b)~~
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 ~~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components Name of Component Name of Manufacturer Manufacturer Serial No. Main Steam piping Installed by TVA N/A~~
7.
~~DesCription of Work Repaired indication in weld.~~
8.
~~Tests Conducted: Hydrostatic 0 other 0 Pneumatic 0 Pressure N/A psi National Board Other Identification No. N/A 1" Main Steam piping to 3-PT -001-OO16B Nominal Operating Pressure 181 Test Temp. N/A OF~~
Addenda, N/A Code Case ASME Code

Repaired, Stamped Year Replaced, or (Yes or Built Replacement No)
N/A Repaired No ~ NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 through 6 on this report Is included on each she'3t, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. 'as amended by additIonal quality assurance requirements found in Design Criteria BFN-S0-7001 and BFN-S0-C-71OS.
FORM NIS-2 (Back)
9.
Remarks Repaired indication in toe of weld. Applicable Manufacture(s Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI.
~~-,-re",pa~ir_--,-__ conforms to the rules of the repair or replacement Type Code Symbol Stamp~~
......;..;N;.;.,/A.:..-_______________________________ _ Certificate of AuthOrization No. ~;:..;...;.._;__--+---------.Expiration Date......;..;N;.;.,/A-'--___________ _ Date ,20QL CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of rl:/.!~E5li:Y and employed by 1t5li Z C'b of C have inspected the components described in this Owner's Report uring the period ~ to y,q4D , and state that to the best of my knowledge and belief, the Owner h s performed examinations and taken correctiv 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, 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 arising from or connected with this inspection. Commissions Inspectofs Signature National Board, State, Province, and Endorsements Date 2cO,:.,£V __
\\ FORM NIS-2 OWNER'S ~.EPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
Owner Tennessee Valley Authority (TVA) Date August 23, 2000 Name 1101 Market Street Chattanooga, TN 37402-2801 Sheet of Address Unit 3 $<.('] ¢S"4l.c mCr/;~kl WorkOrder0NO) 95-0227.1 .2. Plant Browns Ferry Nuclear Plant (BFN) Name P. O. Box 2000, Decatur, AL35609-2OOO Address Repair Organization P.O. No.* Job No.. etc.
3.
~~Work Performed by TVA-BFN~~

~~~N~am-e--------~-------~~

~~Type Code Symbol Stamp N/A P. O. Box 2000, Decatur, AL 35609-2000 Authorization No. N/A Address Expiration Date N/A~~
4.
~~~dentiflcation of System System 075, Core Spray System~~
~~5. (a)~~
Applicable Construction Code USAS B31.1.0 19 67 *
Edition, NlA

Addenda, N/A Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, stamped Name of Component~~
. Name of Manufacturer Board Other Id~ntification Year Replaced, or (Yes or Manufacturer Serial No. No. Built Repl~cement No) 3A Core Spray Pump Powell N/A N/A 3-SHV-075-0512A N/A -Repaired No Suction Drain Valve Rez,/<<.L ~ Uri" UtoI~fo ,,/,6h~ ~J
7.
~~Description of Work Replaced two body to bonnet studs and nuts.~~
8.
Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 181 Other 0 Pressure N/A psi Test Temp. N/A OF NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 through 6 on this report Is inclUded on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
~~as amended by additional quality assurance requirements found in Design Criteria BFN-50-7075 and BFN-50-C-71 05.~~
I
FORM NIS-2 (Back)
9.
Remarks . Replaced two body to bonnet studs and nuts because of inadequate thread engagement. Applicable Manufacture(s Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. _~~re""p",la:.:c;;::e~m:;:e:..;.nt~__ conforms to the rules of the repair or replacement Type Code Symbol Stamp .....:..:Nl:.;,.A.:....-_______________________________ _ Certificate of Authorization No. Expiration Date -=-:N;.:,/A.:..-___________ _ Date ,20 <!O .',I...,; CERTIFICATE OF INSERVICE INSPECTION ,// I, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State &I '2 ~ or Province of AUf"".!? 1m TJfNP. and employea by IIAI1£4ID 1'T<<A'd1 4PdO of ,) IlAlrl"All!D. CT have inspected.the components described in this OWner's Repolfduring the period ___."':-ll.~:._ to 8-/8-po , and state that to the best of my knowledge and belief, ttd L**,{j',!)r nas perT:;,r,~e(j examinations and taken corrective measures described in this OWner's Report In accordance with the requiremt."llts of tne ASME Cooe. S action XI. By Signing thIs certIficate neither the Inspector nor his employer makes any warranty, expressed or implied, conceming trie 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 ariSing from or connected with this inspection. Commissions TA/.illa£ Z Ii S /VA Inspecto(s Signature National Board, State, Province, and Endorsements Date 200"

~~~-~-------~~

1.
~~Owner~~
2.
Plant ~. \\ FORM NIS-2 OWNER'p REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI _.J:!;: Tennessee Valley Authority (TVA) Name 1101 Market Street Chattanooga, -fN 37402-2oCJl Address Browns Ferry Nuclear Plant (BFN) Date May 14, 2002 Sheet --- Unit 3, of 2 P. O. Box 2000 Decatur AL 35609-2000 Address
3.
Work Performed by TVA-BFN*.",.:':'.1t.' Work Orders (WO) 01-005329-000, 01-005496-000, 01-005497-000,01-005498-000,01-005499-000 and 01-005500-000 f' Repair Organizati.on p,o, No,. Job No,. etc. I." Type Code Symbol Stamp 'N/A Name .' ",' OS;, ' P. O. Box 2000, Decatur, AL,35609~'206(l~ Authorization No. N/A Address Expiration Date N/A
4.
~~Identification of System System 003, Reactor Feedwater System~~
~~5. (a)~~
Applicable Construction Code USAS B31.1.0 19 67 *
Edition, N/A

Addenda, N/A Code Case c;~'
~~(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year~~
~~~placed, or (Yes or Manufacturer Serial No. No. Built 'Replacement No) / .f' !' Support (Snubber) / Bergen-Paterson Serial No. " N/A 3-SNUB-Q03-5021/ N/A Replaced / No 3-47B415-25~~
~~',,' 1.~q~~,:~_~~~
pins v nin,:: Support (Snubber),./ Bergen-Paterson TVA Serial No. N/A 3-SNUB-003-5017/ N/A Replaced No 3-47B415-21 M0042 Support (Snubber),,/ Bergen-Paterson TVA Serial No. N/A 3-SNUB-003-5017 c./' N/A Replacement No 3-47B415-21 M0468 Component listing continued on Sheet 2
7.
~~Description of Work Replaced the attachment pins on 3-SNUB-003-5021 (snubber was not replaced). Replaced the remainder of the snubbers with like-for-like replacements.~~
8.
~~Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure D~~
See Remarks Other IZI'*
~~Pressure N/A psi Test Temp, N/A OF~~
~~... J!:IIfIIt..~."...~~
NOTE: supplemental Sheets in form of lists, sketches,oraraWings rhay be used, provided (1) size is 8Y. in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) e~ch sheet is numbered and the number of sheets is recorded at the top of this form.
~~as amended by additional quality assurance requirements found in Contract 68C37-91602 and Design Criteria BFN-50-7003 and BFN-50*C-71 OS,~~
~~FORM NlS..;2 (Back)~~
9.
Remarks WO 01-005329-000 (3-SNUB-003-5021) Applicable Manufacture(s Data Reports to be attached Attachment pin replacement. The original snubber (SN 18039) was removed, functionally tested and returned to the same location. WO 01-005496-000 (3-SNUB-003-5017) The original snubber (TVA SIN M0042) was removed due to 10 percent sample per snubber test program and stored as a spare. The replacement snubber (TVA SIN M0468) was previously removed from 2-47B415S0014 (2-SNUB-003-5029), under WO 00-004854-000 and kept as a spare. The replacement snubber (TVA SIN M0468) was rebuilt per MPI-O-000-SNB002 and then functionally tested per 3-SI-4.6.H-2B. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. replacement conforms to the rules of the repair or replacement TypeCodeSymbolS~mp ~N~/A~ ________________________________________________________________ ___ Certificate of Authorization No. Expiration Date ~N;.;.;/A-,-____________ _ Signed sJ 17 I ,20~ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of re 1/ Pes 'fie E and employed by .Ii fill t:' r of H ItA Ut2/{ p. C C have inspected the components described in this Owner's Report during the period Ii *6 - Cl ;1 to 1- ;0. c;J ~ ,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 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 arising from or connected with this inspection. Inspecto(s Signature I(~. ?2" 'r."'~./ ~ V Commissions ~ t:"J.. i2.' _ a National Board. State. PrO'lince. and Endorsements T~/35' Date 20 0-......::2 __
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS SUPPLEMENTAL SHEET
1.
~~Owner~~
2.
~~Plant Tennessee Valle'/ Authorjtv (TV.A,) Name 1101 Marke! Street Chattanooga TN 37402-2801 Address Browns Eerry Nyclear Plant (BEN) Name P.O. 80x 2000 Decatur AL 35609-2000 Address~~
3.
~~Work Performed by --LT.... V""A.o>-8o/J.E..J.N:L.-~----------_ Name p 0 80x 2000 Decatyr AL 35609-2000 Address~~
4.
Identification of System System 003 Reactor Eeedwater System Date May 14 200? Sheet -..s...2 __ of ~2 ____________________ _ Unit~ -><3 ________________ _ Work Orders 0NO)' 01-005329-000,01-005496-000, 01-005497:000, 01-005498-000, 01-005499-000 and 01-005500-000 . Repair Organization P.O. No.* Job No.* etc. Type Code Symbol Stamp -UNLLL/A:l...-_______ _ Authorization No. -UNLLL!A:l...-__________ _ Expiration Date -uNu;;/A.>.-___________ _
~~5. (a)~~
~~Applicable Construction Code USAS 83110 19 ~ Edition, __ -'N""I.,.;A>--___ Addenda, N/A Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Manufacturer Board Year Replaced, or (Yes or Name of Component Manufacturer Serial No.~~
No. Other Identification Built Replacement No) Support (Snubber) / Bergen-Paterson TVA Serial NO,/" /' N/A 3-SNUB-003-5018/ N/A Replaced No 3-47B415-22 M0279 Support (Snubber) / Bergen-Paterson TVA Serial No. N/A 3-SNUB-003-5018../ N/A Replacement No 3-47B415-22 M0186 r" support(Snubbe~ Bergen-Paterson TVA seriali' N/A 3-SNUB-003-5025/ N/A Replaced No 3-47B415-59 M0334 Support (Snub~. Bergen-Paterson TVAserial/ N/A 3-SNUB-003-5025/, N/A Replacement No 3-47B415-59 M0439* support(Snubb~ Bergen-Paterson TVA Serial", N/A 3-SNUB-003-502~ N/A Replaced No 3-478415-24 M0156 Support (SnUbb~ Bergen-Paterson TVA Serial 0/ N/A 3-SN UB-003-5020/ N/A Replacement No 3-478415-24 M0289 Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-SNUB-003-5019./ N/A Replaced No 3-47B415-23 )' MOO58v' Support (SnUbber)/ Bergen-Paterson TVA Serial N)' N/A 3-SNUB-003-5019 N/A Replacement No 3-47B415-23 M0478 ,./
FORM NIS-2; SUPPLEMENTAL SHEET(8ack)
9.
Remarks WO 01-00S497-000 (3-SNUB-003-S018) The original snubber (TVA SIN M0279) was removed due to 10 percent sample per snubber test program and stored as a spare. The replacement snubber (TVA SIN MOI8S) was previously located in 2-47B41SSooo1 (2-SNUB-003-S01S). removed by WO 00-00S30S-000 and kept as a spare. The replacement snubber (TVA SIN MOI8S) was rebuilt per MPI-0-000-SNB002 and then functionally tested per 3-S1-4.S.H-2B. WO 01-00S498-000 (3-SNUB-003-502S) The original snubber (TVA SIN M0334) was removed due to 10 percent sample per snubber test program and stored as a spare. The replacement snubber (TVA SIN M0439) was previously located in 2-47B41SS0oo3 (2-SNUB-003-5017). removed by WO 00-00S273-000 and kept as a spare. The replacement snubber (TVA SIN M0186) was rebuilt per MPI-0-000-SNB002 and then functionally tested per 3-S1-4.6.H-2B. WO 01-005499-000 (3-SNUB-003-5020) The original snubber (TVA SIN M01S6) was removed due to 10 percent sample per snubber test program and stored as a spare. The replacement snubber (TVA SIN M0289) was previously located in 2-47B452ROOS3N (2-SNUB-074-S01S). removed by WO 00-00S309-000 and kept as a spare. The replacement snubber (TVA SIN M0186) was rebuilt per MPI-0-000-SNB002 and then functionally tested per 3-S1-4.6.H-2B. WO 01-00SS00-000 (3-SNUB-003-5019) The original snubber (TVA SIN MOOS8) was removed due to 10 percent sample per snubber test program and stored as a spare. The replacement snubber (TVA SIN M0478) was previously located in 2-47B452ROOS3E (2-SNUB-074-S016). removed by WO 00-00S312-000 and kept as a spare. The replacement snubber (TVA SIN M0186) was rebuilt per MPI-0-000-SNB002 and then functionally tested per 3-SI-4.6.H-2B.
1.
~~Owner~~
2.
Plant FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI . Tennessee Valley Authority (TVA) Date May 16, 2002 Name 1101 Market Street Chattanooga, TN 37402-2801 of 1-Address Browns Ferry Nuclear Plant (BFN) Unit 3 Name . - P. O. Box 2000, Decatur, AL Address 35609-2000 Work Orders rNO), 00-004415-000, 01-005376-000, 01-005386-000,01-005388-000, 01-005505-000 Repair Organization P.O. No.. Job No.* etc.
3.
Work TVA-BEN Type Code Symbol Stamp -..,;....N...;../A _______ -_ Name Authorization No. N/A ......;..;..,;.;.....------~..:...;... ::.:.. P. O. Box 2000. Decatur, AL 35609-2000 Address Expiration Date N/A ------------
4.
~~Identification of System System 074, Residual Heat Removal System~~
~~5. (a)~~
Applicable Construction Code USAS B31.1.0 19 67*
Edition, N/A

Addenda, N/A Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code. National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or Manufacturer Serial No.~~
No. Built Replacement No) Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-SNUB-074-5035 N/A Replaced No 3-47B452-1491 M0287 Support (Snubber) Bergen-paterson TVA Serial No. N/A 3-SNUB-074-5035 N/A Replacement No 3-47B452-1491 M0039 Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-SNUB-074-5038 N/A Replaced No 3-47B452-1557 M0039 Support (Snubber) AnchorlDarling ADH-3000 868 N/A 3-S N U B-074-5038 N/A Replacement No 3-47B452-1557 Support (Snubber) Anchor/Darling ADH-300-2040 N/A 3-SNU B-074-5040 N/A Replaced No 3-47B452-129 Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-SNUB-074-5040 N/A Replacement No 3-47B452-129 MOO33 Support (Snubber) Anchor/Darling ADH-300-2041 N/A 3-SNUB-074-5039 N/A Replaced No 3-478452-129 Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-SNU8-074-5039 N/A Replacement No 3-478452-129 M0393 Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-S N U B-074-5065 N/A Replaced No 3-47B452-105 M0061 Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-SNUB-074-5065 N/A Replacement No 3-47B452-105 M0327
7.
~~Description of Work Replaced the referenced snubbers with either new or rebuilt, like-for-like snubbers.~~
8.
~~Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0~~
See Remarks Other t83 **
Pressure N/A psi Test Temp. N/A NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y. in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
~~as amended by additional quality assurances requirements found in contract 68C37 -91602, BFN-50-7074 and BFN-SO-C-7105 melO~~
~~-'FORM NIS-2 (Back)~~
9.
Remarks WO 00-004415-000 (3-SNUB-074-5035) Applicable Manufacture(s Data Reports to be attached The original snubber (TVA Serial No. M0287) was removed due to 10 percent sample per snubber program and stored as a spare. The replacement snubber(TVA Serial No. M0039) was previously located at 3-47B452-1557 (3-SNUB-074-5038). and was removed by WO 01-005376-000 and kept as a spare. The replacement snubber (TVA Serial No. M0039) was rebuilt per MPI-0-OOO-SNB002 and then functionally tested per 3-S1-4.6.H-2B. WO 01-005376-000 (3-SNU8-074-5038) The original snubber (TVA Serial No. M0039) was removed due to 10 percent sample per snubber program and stored as a spare. The replacement snubber (Serial No. ADH-3000 868) was purchased under contract 00009753. The replacement snubber (Serial No. ADH-3000 868) was functionally tested by the manufacturer and found acceptable. prior to installation. WO 01-005386-000 (3-SNUB-074-5040) The original snubber (Serial No. ADH-300-2040) was removed due to 10 percent sample per snubber program and stored as a spare. The replacement snubber(TVA Serial No. MOO33) was previously located at 3-47B456-97 (3-SNUB-071-5011). and was removed byWO 99-003436-020 and kept as a spare. The replacement snubber (TVA Serial No. MOO33) was rebuilt per MPI-0-000-SNB002 and then functionally tested per 3-SI-4.6.H-2B. WO 01-005388-000 (3-SNUB-074-5039) The original snubber (Serial No. ADH-300-2041) was removed due to 10 percent sample per snubber program and stored as a spare. The replacement snubber (TVA Serial No. M0393) was previously located at 2-47B452-1206 (2-SNUB-074-5010). and was removed by WO 01-002102-000 and kept as a spare. The replacement snubber(TVA Serial No.M0393) was rebuilt per MPI-0-000-SNB002 and then functionally tested per 3-SI-4.6.H-2B. WO 01-005505-000 (3-SNUB-074-5065) The Original snubber (TVA Serial No. M0061) was removed due to 10 percent sample per snubber program and stored as a spare. expiration. The replacement snubber(TVA Serial No. M0327} was previously located 2-47B452-451 (2-SNUB-074-5045). and was removed by WO 00-005369-000 and kept as a spare. The replacement snubber (TVA Serial No.M0327) was rebuilt per MPI-0-000-SNB002 and then functionally tested per 3-SI-4.6.H-2B. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this __ --"re.,..pla.;;;.c~e"'_m;.;.e""'n'_'t...,...-- conforms to the rules of the repair or replacement ASME Code Section XI. Type Code Symbol Stamp ...;...:N~/A.;..... ________________________________ _ Expiration Date -'-N:;.:/A-=-____________ _ ineer Date S--.?..d ,20t2L CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or P.rovince of t:"")/foIE SEE and employed by It 58 C T of T? C r have inspected the components described in this Owner's Report during the period
v t'.. t

l P to iJ -.] CI -d,?
, 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 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 pro erty damage or a loss of any kind arising from or connected with this inspection. Commissions National Board. State. Province. and Endorsements Date
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~Owner Tennessee Valley Authority (TVA) Date May 20, 2002 . Name 1101 Market Street Chattanooga, TN ~7402-2801 . Sheet of Address~~
2.
~~Plant Browns Ferry Nuclear Plant (BFN) Unit 3 P. O. Box 2000, Decatur, AL 35609-2000 Work Orders 01-005502-000 and 01-005504-000 Address Repair Organization P.O. No.. Job No., etc.~~
3.
~~Work Performed by TVA-BFN Type Code Symbol Stamp N/A~~

~~~N~a-m-e-----------------~~

~~P. O. Box 2000, Decatur, AL 35609-2000 Authorization No. N/A Address Expiration Date N/A~~
4.
~~Identification of System System 075, Core Spray (CS) System~~
~~5. (a)~~
Applicable Construction Code USAS B31.1.0 19 67 *
~~Edition, (b)~~
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
Identification of Components Repaired or Replaced and Replacement Components National Name of Component Name of Manufacturer Board Manufacturer Serial No. No. Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-47B458-558 MOO05 Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-47B458-558 M0322 Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-47B458-567 M0101 Support (Snubber) Bergen-Paterson TVA Serial No. N/A 3-47 B 458-567 M0339 ~-

~

7.
Description of Work Replaced snubbers with like-for-like replacements Replaced one bolt lost during Installation. N/A Other Identification 2-S N U B-075-5024 2-SNUB-075-5024 2-SNUB-075-5021 2-SNUB-075-5021
8.
~~Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Other ~"" Pressure N/A psi Test Temp. N/A OF~~
Addenda, N/A Code Case ASME Code

Repaired, Stamped Year Replaced, or (Yes or Built Replacement No)
~~N/A Replaced No N/A Replacement No N/A Replaced No N/A Replacement No~~
See Remarks NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y. in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
"as amended by "dditional quality assurance requirements found in Contract 68C37 -91602 and Design Criteria SF N-50-7075 and BFN-50-C-71 05. I I
FORM NIS-2 (Back)
9.
Remarks WO 01-005502-000 (3-SNUB-075-5024) Applicable Manufaclure(s Data Reports to be atta~hed The original snubber (TVA Serial No. MOOOS) was removed due to 10 percent sample per snubber program and stored as a spare. The replacement snubber{TVA Serial No. M0322) was previously located at 2-47B452 R0052 (2-SNUB-074-5014), and was removed by WO 00-005313-000 and kept as a spare. The replacement snubber (TVA Serial No. M0322) was rebuilt per MPI-0-000-SNB002 and then functionally tested per 3-S1-4.6.H-2B. WO 01-005504-000 (3-SNUB-075-5021) The original snubber (TVA Serial No. M0101) was removed due to 10 percent sample per snubber program and stored as a spare. The replacement snubber{TVA Serial No. M0339) was previously located 2-47B452-988 (2-SNUB-074-5023), and was removed by WO 00-005371-000 and kept as a spare. The replacement snubber (TVA Serial No. M0339) was rebuilt per MPI-0-000-SNB002 and then functionally tested per 3-S1-4.6.H-2B. During installation of the replacement snubber an end fitting attachment bolt was lost and was replaced. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp ~N~/A~ ____________________________________________________________________ ___ Expiration Date --!..N~/A~ _____________________ _ Date ,20 r12-CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of T e-J/ AI P ~ SFe: and employed by Ii sli C T of r ~ D C have inspected the components described in this Owner's Report during the period
/-
- 4) 2 to ':/-£- (2 ~ , 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 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 arising from or connected with this inspection. ~~ Commissions Inspecto(s Signature National Board. State. Province. and Endorsements Date
FORM NIS-2 OWNER'S REPORT FOR REPA1RS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~Owner Tennessee Valley Authority (TVA) Date May 20, 2002 Name 1101 Market Street Chattanooga, TN 37402-2801 Sheet *1 of Address~~
2.
~~Plant Browns Ferry Nuclear Plant (BFN) Unit 3 Name P. O. Box 2000, Decatur, AL 35609*2000 Address Work Orders (WO) 99*006554-000.01-007381*000 Repair Organization P.O. No.* Job No., etc.~~
3.
~~Work Performed by TVA*BFN Type Code Symbol Stamp N/A~~

~~.-N~a~m~e------------------~~

~~P. O. Box 2000, Decatur; AL 35609*2000 Authorization No. N/A Address Expiration Date N/A~~
4.
~~Identification of System System 001, Main Steam System ASME Section III, Article 9, 1965 and~~
~~5. (a)~~
~~Applicable Construction Code ASME Section III 19 68~~
Edition, Summer 1970

Addenda, N/A Code Case (b)
~~'Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or Manufacturer Serial No.~~
No. Built Replacement No) Main Steam Relief Valve Target Rock Corp. 1059 N/A 3*PCV*001*0019 1968 Replaced Yes 7567F*000*10 Main Steam Relief Valve Target Rock Corp. 1085 N/A 3-PCV*001*0019 1968 Replacement Yes 7567F*Ooo*10 ~.. ". ~ "or !. ~
7.
Description of Work Replaced Mal~ Ste~m Relief valve m?in bofjly with.a rebuilt valye. previously used on Unit 3: Rebuild included replacement of the main disc and a body stud and nut. All inlet and outlet bolting was replaced.
8.
Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 181 Other 0 Pressure N/A psi Test Temp. N/A OF NotE: Suppl~;;'entili Sheets in form of Ii~ts, sketc'hes, 'or'drawings may be used, provided (1) siz'e is 8% in. X f1 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. "as amended by additional quality assurance requirements found in GE P. O. 205AJ600, and Design Criteria BFN-5Q.7oo1 and BFN*50*C*7105.
FORM NIS-2 (Sack)
9.
Remarks The main valve body was replaced with a rebuilt valve body (same manuf9cturer/model number) previously used at BFN. Applicable Manufacture~s Data Reports to be attached This valve Is being replaced as part of the regularl'y sCheduled valve inspection required by Tech Specs. 3-PCV-001-oo19 WO 01-007381-000 removed the existing valve body (SIN.1059) from the 3-PCV-001-OO19 location and replaced it with a with a rebuilt valve (SIN 1085) previously used in BFN Unit 3 (3-PCV-001-0041). The replacement valve was removed from Unit 3 by WO 99-006555-000 and rebuilt by WO 99-006554-000. Rebuild included replacement of the main disc and a body stud and nut galled during disassembly. All inlet and outlet bolting was replaced during installation for ease of maintenance and ALARA considerations CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. --'-r-?ep""l,:;:.ac.:.,;e"'m:..;.e;;;,,;n""t....,..__ conforms to the rules of the repair or replacement Type Code Symbol Stamp ....:,;N:;.:./A..:..... _________________________________ Certificate of Authorization No.....:.;N::.,:/A..:....-I-____...--______ _ Expiration Date....:,;N:;,,:/A..:.... ____________ _ Date ,20~ CERTIFICATE OF INSERVICE INSPECTION I, the undersi:=ed, hOI~?i:lid commission issued by the National Boar of Boiler and Pressure Vessel Inspectors and the State or Province of LI?JlNd,Se£ and employed by of "II have inspected the components described in this Owner's Report during the period to t'. 7*0; , and state that to the best of my knowledge and belief, the Owner as 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 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 arising from or connected with this inspection. Commissions 'l'"f/S/d,!t Z; $'p,sA National Board. State. PrO'Jince. and Endorsements Date 200 ;a
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~Owner Tennessee 'Jalley Authority (TVA) Date May 24, 2002 Name 1101 Market Street Chattanooga, TN 37402*2801 Address~~
2.
Plant Browns Ferry Nuclear Plant (BFN) Name ~ Sheet Unit of 3 P. O. Box 2000, Decatur, AL 35609*2000 Work Orders (WO) 01-007370-000 and 02*003703*000 Address -, Repair Organization P,O, No.* Job No,. etc.
3.
~~Work Performed by TVA*BFN Type Code Symbol Stamp 'N/A~~

~~~N~a-m-e-----------------~~

~~P. O. Box 2000, 'Decatur, AL -35609*2000 Authorization No. N/A Address Expiration Date N/A~~
4.
~~Identification of System System 001, Main Steam System~~
~~5. (a)~~
Applicable Construction Code USAS B31.1.0 19 67 *
Edition, N/A

Addenda, N/A Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or Manufacturer Serial No.~~
No. Built Replacement No) Main Steam to Off* Gas Durabla E966A*1*5 N/A 3*SHV*001*0742 N/A Replaced No Preheater Check V1v Main Steam to Off* Gas Durabla E966A*1*3 N/A 3*CKV*001*0742 N/A Replacement No Preheater Check Vlv Main Steam to Off* Gas Durabla E966A*1-4 N/A 3-SHV -001-07 44 N/A ", Replaced No Preheater Check Vlv j .,~ Main Steam to Off* Gas Durabla E966A*1*6 N/A 3-CKV*001-0744 NJJII Replacement No Preheater Check Vlv I:. ~..
7.
~~Description of Work Replaced check valves with like*for like replacements from the same vendor.~~
8.
Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure t8J Other 0 Pressure N/A psi Test Temp. N/A.' OF NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y. in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
~~as amended by additional quality assurance requirements found in Contract 1365888, Design Criteria BFN-50-7001 and BFN-50-C-71 05.~~
~~. FORM NIS-2 (Back).~~~
9.
Remarks Replaced check valves with like-for like replacements from the same vendor. Applicable Manufacturers Oata Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this. __ -.:.re;Jp:.:.la::;c:.:,e:;;m:.:;e:.:.n!:,t-:-__ repair or replacement ASME Code Section XI. conforms to the rules of the Type Code Symbol Stamp ~N~/A~ ________________________________________________________________ ___ Expiration Date -.,;.N"'IA;..:... ____________ _ Date ,20~ CERTIFICATE OF INSERVICE INSPECTION I, the undersigne,wIding a ~lid commis~on issued by the National Board oi.BPiler and Pressure Vessel Inspectors and the State or Province of J: -e. and employed by !:L~8 CT of have inspected the components described in this Owne.r's Report durin the period to £= R.06 , 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 warranty, expressed or implied, conceming 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 arising from or connected with this inspection. Commissions Inspectors S,gnature Date
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~Owner Tennessee Valley Authority (TVA) Date May 24, 2002 Name 1101 Market Street Chattanooga, TN 37402*2801 Sheet of Address~~
2.
~~Plant Browns Ferry Nuclear Plant (BFN) Unit 3 Name P. O. Box 2000, Decatur, AL 35609*2000 Work Orders 02-003225-000 and 02*003382*000 Address Repair Organization P.O. No., Job No.* etc.~~
3.
~~Work Performed by TVA*BFN Type Code Symbol Stamp N/A~~

~~~N~am-e-----------------~~

~~P. O. Box 2000, Decatur, AL 35609*2000 Authorization No. N/A Address Expiration Date N/A~~
4.
Identification of System System 069, Reactor Water Cleanup (RWCU) System (valve) ASME Section III Class 1,1986 Edition, less N*stamp S. (a) Applicable Construction Code (piping) USAS B31.1.0 19 67 *
Edition, NfA

Addenda, N/A Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or Manufacturer Serial No.~~
No. Built Replacement No) RWCU Sys Return Anchor/Darling EZ862*1*1 N/A 3*C KV-069*0628 1997 Replaced No Check Valve 4"*900# Lift Check. t".1-disc ~.. "' .,. ~ 'il"4-RWCU Sys Return Anchor/Darling EZ862*1*2 N/A 3*CKV*069*0629. .. 1997.. Replac~~ No Check Valve 4".~OO#.lif! Ch~k
~~\\.~~
~~disc J, ~ "~~
~~. -.f f *.* ~.~~
7.
~~Description of Work Replaced valve discs. One new disc from the vendor and one refurbished.~~
8.
Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure t8l Other 0 Pressure N/A psi Test Temp. N/A OF NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is ey. in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. 'as amended by additional quality assurance requirements found in P*97N2R*204635 and P*92ZMB*45195C Release 1451197 and Design Criteria BFN*50*7069 and BFN*50-C*71 OS. U3elD.
~~FORM NIS-2 (Back) 1-~~
9.
Remarks Replaced valve discs. One new disc from the vendor and one refurbished. Applicable Manufacture(s Data Reports to be attached WO 02-003325-000 removed the disc from 3-CKV-069-0628 and installed a new disc. The disc removed from 3-CKV-069-0628 was refurbished in WO 02-003382-000 and placed in 3-CKV-069-0629. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp ....;.;N""/A..:....-________________ ~ Expiration Date -=.,N:;.:/A-'-____________ _ Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board OVoiler and Pressure Vessel Inspectors and the State or Provi e of -:e: and employed by a.58 C r of have inspected the components described in this wner's Report duri 9 the period to At. 7.".2 , 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 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 arising from or connected with this inspection.' Commissions National Board. State. Province. and Endorsements
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~Owner Tennessee Valley Authority (TVA) Date May 24, 2002 Name 1101 Market Street I Chattanooga, TN 37402-2801 . Sheet 1 of Address~~
2.
~~Plant Browns Ferry Nuclear Plant (BFN) Unit 3 P.O. Box 2000, Decatur, AL 35609-2000 Work Order 01-008132-000 Address , Repair Organization P.O. No.. Job No.* ete.~~
3.
~~Work Performed by TVA-BFN .. Type Code Symbol Stamp N/A~~

~~.-:-N~a-me---------~~

~~P. O. Box 2000,. Decatur, AL 35609-2000 Authorization No. N/A Address Expiration Date N/A~~
4.
~~Identification of System System 073, High Pressure Coolant Injection (HPCI) System~~
~~5. (a)~~
Applicable Construction Code USAS B31.1.0 19 67 *
Edition, N/A

Addenda, N/A Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or Manufacturer Serial No.~~
No. Built Replacement No) HPCI Turbine Exhaust Fike Metal Products Lot # N/A 3-RPD-073-0713 1997 Replaced No Inner Rupture Disc 16-CPV-C-BT 9723640 HPCI Turbine Exhaust Fike Metal Products Lot # N/A 3-RPD-073-0713 1997 Replacement No Inner Rupture Disc 16-CPV-C-BT 9723640 00,
7.
~~Description of Work Replaced rupture disc on turbine exhaust.~~
8.
Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 181 Other 0 Pressure N/A psi Test Temp. N/A OF NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 through ( on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. 'as amended by additional quality assurance requirements found in Contracts 70C53-92291-7, 221688 and Design Criteria BFN-50-7073 and BFN-50-C-71 05.
9.
Remarks This activity is a normal, periodic replacement and inspection of the rupture disc reguired by ASME/ANSI OM-10 and controlled by Applicable Manulactu,e(s Data Reports to be attached the BFN Preventive Maintenance Program. No degradation was identified during inspection of the rupture disc removed during this subject activity. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp ~N~/A~ __________________________________________________________________ _ Certificate of Authorization No. Expiration Date -.:..N;;.;/A-'-____________ _ Date ,1~-.2.. CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of 'LGNa<lTB -and employed by Ii S"d C l of -.,.....,-:--:--o:--u~'::!'-~w.:'.4.:'ILI-.-:"'--~-:--__ -:::--.".r"'4=,~~L-__..,------ have inspected the components described in this Owner's Report during the period to .1 --/),," ;? , 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 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 arising from or connected with this inspection. ~ Commissions National Board. Slale. Province. and Endorsements Date
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~Owner Tennessee Valley Authority (TVA)~~
2.
~~Plant Name 1101 Market Street Chattanooga, TN 37402-2801 Address Browns Ferry Nuclear Plar't(BFN) P. O. Box 2000, Decatur, Al. 35609-2000 Address~~
3.
~~Work Performed by TVA-BFN~~

~~'~Na~m~e------------------~~

P. O. Box 2000, Decatur, Al 35609-2000 Date May 24, 2002 Sheet of Unit 3 Work Order 01-008135-000 Repair Organization P.O. No.. Job No.. ete. Type Code Symbol Stamp NfA Authorization No. NlA Address Expiration Date NfA
4.
~~Identification of System System 071, Reactor Core Isolation Cooling (RCIC) System~~
~~5. (a)~~
Applicable Construction Code USAS B31.1.0 19 67*
Edition, NfA

Addenda, NfA Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or Manufacturer Serial No.~~
No. Built Replacement No) RCIC Turbine Exhaust Fike Metal Products NfA N/A 3-RPD-071-0011 A Replaced No Rupture Disc 8-CPV-C-BT RCIC Turbine Exhaust Fike Metal Products NfA N/A 3-RPD-071-0011A Replacement No Rupture Disc 8-CPV-C-BT ~
7.
~~Description of Work Replaced rupture disc on turbine exhaust.~~
8.
Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 181 other 0 Pressure N/A psi Test Temp. N/A OF NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y:. in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. 'as amended by additional quality assurance requirements found in Contracts 70C53-92291-7 & 89NJl-80177B (ref. PEG pkg 9600000598), and Design Criteria BFN-SO-7071 and BFN-50-C-71 OS.
FORM NIS-2 (Back)
9.
Remarks This activity is a normal, periodic replacement and inspection of the rupture disc required byASMElANSI OM-tO and controlled by Applicable Manufacture(s Data Reports to be attached the BFN Preventive Maintenance Program.* No degradation was Identified during inspection of the rupture disc removed during this subject activity. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. replaced repair or replacement conforms to the rules of the T~eCodeSymbolStamp ~N~/A~ ____________________________________________________________________ ___ Expiration Date -'-N"'/A...;... ____________ ___ Date ,19QL CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of T E.k~ ~ S.s~ E and employed by H S B C r of T Po D C have inspected the components described in this Owner's Report during the period to 3 -b - 0 :J , 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 warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall b~ liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Commissions TN 3/35 "T" ~ /I ~/S"'i9'I~ 1/ National Board. State. Province. and Endorsements Date ~ /0
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~Owner Tennessee Valley Authority (TVA) Date May 28, 2002 Name 1101 Market Street . 'Chattanooga, TN 37402-2801 Sheet of Address~~
2.
~~Plant Browns Ferry Nuclear Plant *(BFN). Unit 3 Name P. O. Box 2000, Decatur, AL. 35609-2000 "Work Order (WO) 99-003420-000 Address Repair Organization P.O. No.* Job No.. etc.~~
3.
~~Work Performed by. TVA*BFN Type Code Symbol Stamp N/A~~

~~N~a-m~e------------------~~

~~P. O. Box 2000, Decatur, AL 35609-2000 .Authorization No. N/A Address Expiration Date N/A~~
4.
~~Identification of System System 063. Standby liquid Control (SLC) System~~
~~5. (a)~~
~~Applicable Construction Code USAS B31.1.0 19 67* Edition. N/A~~
~~Addenda, N/A Code Case (b)~~
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board~~
~~. Other Identification Year Replaced, or (Yes or Manufacturer Serial No. No. Built Replacement No) SLC Pump3A Velan Valve Corp. N/A N/A 3-SHV*063-0506 No Suction Shutoff Valve B9-054B-13MS~~

~~reo laced valve bonnet boltin~~~
studs Velan N/A N/A 3-SHV*063-0506 Replaced No studs Nova Machine N/A . N/A 3-SHV*063-0506 Replacement No Products nuts . Velan N/A N/A 3-SHV*063-0506 Replaced No - ~--- .~ nuts Allied But 8. Bolt N/A N/A 3-SHV-063-0506 Replacement No
7.
~~Description of Work Replaced bonnet bolting. --~----------~----------------------------------------------------------~~
8.
Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 181 Other 0 Pressure N/A psi Test Temp. N/A OF NOTE: Supplemental Sheets in form of lists. sketches, or drawings may be used, provided (1) size is B% in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
~~as amended by additional quality assurance requirements found in Design Criteria BFN-50-7063 and BFN-50-C-71 05.~~
~~I I~~
9.
Remarks Replaced bonnet bolting. FORM NIS-2 (Back) Applicable Manufacture(s Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp -..:..::N:.;./A.:....-________________________________ _ Certificate of Authorization No. Expiration Date ...!.:N~/A..!-_____ -.--______ _ 6/2/ Date ,20~ / CERTIFICATE OF INSERVICE INSPECTION I, the undersi!;!!1ed, holdin] a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of T e i!-.. c"/!- and employed by of --:--:7-:---=-_~-=--~,..-:'-~--:--:---_>>~:coi#. ...... *:c..:_4L.:~:..;;1.~:__---~----_:__ have inspected the components described in this Owner's Report during the period
~~cJ.,~~
to Y -kf,7;) , anq state that to the best of my knowledge and belief, the Owner lias 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 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 ariSing from or connected with this inspection. Commissions 7" tV 7/ z r Z S,v /!J /J National Board. State. Province. and Endorsements Date
j'" . ~ *. >t.
1.
Owner FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Tennessee Valley Authority (TVA) Date May 28, 2002 Name 1101 Market Street 37402*2801 Sheet Chattanooga, TN Address of 2 ~---------------
2.
~~Plant Browns Ferry Nuclear Plant (BFN) Name P. O. Box 2000. Decatur. AL 3S609~20OO Address~~
3.
~~Work Performed by TVA*BFN Name P. O. Box 2000, Decatur, AL 35609-2000 Address~~
4.
Identification of System System 071, Radwaste System Unit 3 Design Change Notice (DCN) T40978, Work Plan T40978-001 Work Order (WO) 98-014466-000 Repair Organization P.O. No.* Job No.* etc. Type Code Symbol Stamp N/A Authorization No. N/A Expiration Date -..:..:N;,:./A.:-____________ _ (valves) ASME Sec III, Class 2,1989 Edition (Equivalent)
~~5. (a)~~
~~Applicable Construction Code (piping) USAS 831.1.0 19 67' Edition N/A~~
~~Addenda, N/A Code Case (b)~~
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired orReplaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Manufacturer Board Other Identification Year Replaced, or (Yes or Serial No.~~
No. Built Replacement No) Drywell Equip Drain Velan N/A N/A 3-FCV-071*0015A NtA Replaced No Sump Inbd Isol Valve 810-0648-2TS 8502*2WW Drywell Equip Drain Canadian Worchester NOO-OO39*2 N/A 3-FCV-077-0015A 2000 Replacement No Sump Inbd Iso I Valve 1<7913 C KN45-0262 Drywell Equip Drain Velan N/A NtA 3-FCV-071*001S8 N/A Replaced No SumpOutbd \\so\\ Valve 810*0648*2TS 8502-2WW Drywell Equip Drain Canadian Worchester Noo-OO39*1 N/A 3-FCV-077-00158 2000 Replacement No SumpOutbd Isol Valve 1<7913 C KN45*0262 See Page 2
7.
Description of Work Replaced Drywell Equipment Drain Sump Inboard and outboard primary containment isolation valves with a new design. Replaced some associated piping. Modified the pipe support between the valves.
8.
~~Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure [8]'~~
~~- Reference Code Case N-416*1 Other 0 Pressure Nt A psi Test Temp.~~
N/A OF NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Yi in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. 'as amended by additional quality assurance requirements found in Contracts 250534 & 1364025 and Design Criteria BFN-50-7077 and BFN-50-C-710!:
(. FORM NIS-2 (Back)
9.
Remarks Replaced Drywell Equipment Drain Sump inboard and outboard primary containment isolation valves (3-FCV-077-0015A & -(0158) Applicable Maoutacture(s Data Reports to be attached with a new design. Replaced some associated piping. Modified the pipe support between the valves. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp ~N~/A~ __________________________________________________________________ _ Expiration Date -'-N;;.;/A...;... _______________ _ Date .20tJ.k. CERTIFICATE OF INSERVICE INSPECTION I, the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of If ,A/P£S"Se C and employed by Hs dec of - Fi. C have inspected the components described in this Owner's Report during the period -0/ to - ~ -0 ,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 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 ariSing from or connected with this inspection. Commissions National Board. State. Province. and Endorsements Date 20&2.2
.I FORM NIS-2 OWNER1S REPORT FOR REPAIRS OR REPLACEMENTS SUPPLEMENTAL SHEET Owner Tennessee Valley Authority ayA)
2.
Plant Name l1Ql Market Street Chattanooga TN 37402-2801 Address Browns Ferry Nuc/ear plant (BEN) Name Date May 28 2002 Sheet _2 __ of 2 _______________ _ Unit _3",~ ______________ _ Design Change Notice (DeN) T40978, Work Plan P. O. Box 2000, Decatur, AL 35609*2000 . T40978-001, Work Order ('-NO) Sa*014466*000 Address
3.
Work Performed by --I.T..xV.!:lA~-B~F;.J.N1_...,..,..------_-_ Name POBox 2000 Decatur AL 356Q9-2OOO Address Repair OrganizaMn P.O. No.. Job No.* etc Type Code Symbol Stamp -tlN'"IAl....-____________ _ Authorization No. ....,N""IA"--_________________ _ Expiration Date --"'N""/A""-_____________ _
4.
~~Identification of System System on Radwaste System valves: ASME Sec 11\\ Class 2, 1989 Edition (Equivalent)~~
~~5. (a)~~
~~Applicable Construction Code piping' USAS B31 16 19 ~~~
Edition, NIA

Addenda, NIA Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Manufacturer Board Year Replaced, or (Yes or Name of Component Manufacturer Serial No.~~
No. Other Identification Built Replacement No) Pipe unknown N/A N/A N/A NfA Replaced No Pipe Consolidated Power NIA N/A NIA NfA Replacement No Supply Pipe Support TVA NfA N/A 3-47B482-103 NIA Replaced No Pipe Support TVA NfA N/A 3-47B482-103 NfA Replacement No
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~Owner Tennessee Valley Authority (TVA) Date May 29, 2002 Name 1101 Market Street Chattanooga, TN 37402-2801 Sheet of Address~~
2.
~~Plant Browns Ferry Nuclear Plant (BFN) Unit 3 Name P. O. Box 2000, Decatur, AL 35609-2000 Work Order (WO) 02-002122-000 Address Repair Organization P.O. No.. Job No., etc.~~
3.
~~Work Performed by TVA-BFN Type Code Symbol Stamp N/A~~

~~N~a-m-e------------------~~

~~P. O. Box 2000, Decatur, AL 35609-2000 Authorization No. N/A Address Expiration Date NI A~~
4.. -Identification of System System 074, Residual Heat Removal (RHR) System

5. (a)
~~Applicable Construction Code ASME Section III, Class C 19 65 "~~
~~Edition, (b)~~
~~Applicable.Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components National Name of Component Name of Manufacturer Board Manufacturer Serial No. No. 3B RHR Heat Exchanger PERFEX 07001-2 4199~~
7.
~~Description of Work Removed surface indication on N3 nozzle. N/A Other Identification 3-HEX-074-0900B~~
8.
~~Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Other 0 Pressure N/A psi Test Temp. N/A OF~~
Addenda, N/A Code Case ASME Code

Repaired, Stamped Year Replaced, or (Yes or Built Replacement No) 1970 Repaired Yes
" - No pressure testing required because minimum wall was not viOlated. NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. "reference also additional quality assurance requirements found in Design Criteria BFN-50-7074 and BFN-50-C-71 05. I I
FORM NIS-2 (Back) ~
9.
Remarks Removed surface indication on N3 nozzle. No pressure testing was reguired because minimum wall thickness was not violated. Applicable Manufacturets Data Reports to be attached NDE (surface exam) was performed following repair. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. repair repair or replacement conforms to the rules of the TypeCodeSymbolStamp ~N~'A~ ________________________________________________________________ ___ Expiration Date -.:..N""'A-'-____________ _ Date ,£=-2 9 ,20 O?- CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of rtf PIIITSGEc and employed by liS t5 e r of tllll{ fFe#lJ,C T. have inspected the components described in this Owner's Report during the period 3 - I;) - ;; tn? a to 3 0 t' , 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 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 arising from or connected with this inspection. Commissions Inspecto(s Signature National Board. State. Province, and Endorsements Date
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~Owner Tennessee Valley Authority (TVA) Name 1101 Market Street Chattanooga, TN 37402-2801 Address .2. Plant Browns Ferry Nuclear Plant (BFN) Name P. O. Box 2000, Decatur, AL 35609-2000 Address~~
3.
~~Work Performed by TVA-BFN~~

~~~N~a-m-e-----------------~~

P. O. Box 2000, Decatur, AL 35609-2000 Address Date May 29, 2002 Sheet of Unit 3 Work Order (WO) 00-003996-000 Repair Organization P.O. No., Job No., etc. Type Code Symbol Stamp Authorization No. N/A Expiration Date N/A N/A
4.
~~Identification of System System 003, Reactor Feedwater (RFW) System~~
~~5. (a)~~
~~Applicable Construction Code USAS B31.1.0 19 67'~~
Edition, N/A

Addenda, N/A Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or Manufacturer Serial No.~~
~~No. Built Replacement No) Outboard RFW Check Atwood and Morrill NlA N/A 3-CKV-003-0554 NfA No Valve - A line 20788-H~~
~~valve disc replaced valve disc Atwood and Morrill N/A N/A 3-CKV-003-0554 NJA replaced No 20788-H valve disc Atwood and Morrill NJA N/A 3-CKV -003-05S4 N/A replacement No 20788-H~~
7.
~~Description of Work Replaced valve disc with a new disc from original valve manufacturer.~~
8.
Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure ~ Other 0 Pressure N/A psi Test Temp. N/A OF NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y. in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. Was amended by additional quality assurance requirements found in Contra,ct 90744 and Design Criteria BFN-SO-7003 and BFN-SO-C-71 OS. U3CIO I I
FORM NIS*2 (Back) -
9.
Remarks Replaced valve disc with a new disc from original valve manufacturer. Applicable Manufacture~s Data Reports to be attactled CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. replacement repair or replacement conforms to the rules of the Type Code Symbol Stamp ~N::.:./A-=--_________________________________ _ Certificate of Authorization No. Expiration Date.....:..;N:;.:/A..:....-____________ _ Date ,20(22-CERTIFICATE OF INSERVICE INSPECTION . lid cgp1mission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State e e and employed by t-I 5i} C r of -+'=-T:~-:::'~'--'----- ~ have inspected the components described in this Owner's Report during the period to - tJ , 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 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 arising from or connected with this inspection. Commissions Inspecto~s Signature National Board. State, Province, and Endorsements Date 20#!?.1
.. ~.~"
1.
~~Owner~~
2.
Plant FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Tennessee Valley Authority (TVA) Date May 30, 2002 Name 11 01 Market Street Chattanooga, TN 37402-2801 Sheet of 2 Address Browns Ferry Nuclear Plant (BFN) Unit 3 Name Work Orders (WO) 01*005501-001, 01-005501-002 and 01-005501-005 P. O. Box 2000. Decatur AL 35609-2000 Address
3.
~~Work Performed by TVA-BFN~~

~~~N~am-e-----------------~~

P. O. Box 2000, Decatur, AL 35609-2000 Design Change Notice (DCN) 50729 Stage 1 Repair Organization P. O. No.* Job No.. etc. Type Code Symbol Stamp Authorization No. N/A N/A Address Expiration Date N/A
4.
~~Identification of System System 085, Control Rod Drive (CRD) System (valves) ASME Sec. III 1989 Edition (less N-stamp)~~
~~5. (a)~~
~~Applicable Construction Code (piping) USAS 831.1.0 19 67' Edition N/A~~
~~Addenda, (b)~~
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
Identification of Components Repaired or Replaced and Replacement Components National Name of Component Name of Manufacturer Board Other Identification Year Built Manufacturer Serial No. No. Root Valve to Kerotest N/A N/A 3-RTV -085-0277 N/A LS~85-45D (Bottom) Root Valve to Flowserve E488T-1-2 N/A 3-RTV-085-0277 2002 LS-85-45D (Bottom) Z'-800#-Gate-SW Root Valve to Kerotest N/A N/A 3-RTV -085-0278 NIA LS-85-45C (Bottom) Root Valve to Flowserve*
~~E488T-1-1 N/A 3-RTV-085-0278 2002 LS-85-45C (Bottom) 2" -800#-Gate-SW See Sheet 2 for continuation of component listing~~
7.
~~Description of Work Replaced valves and piping on inlet side of level switches with larger diameter components Modified CRD support 3-478468-241 N/A Code Case ASME Code~~
~~Repaired, Stamped Replaced, or (Yes or Replacement No)~~
~~Replaced No Replacement No Replaced No Replacement No~~
8.
~~Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure [81'~~
~~- Reference Code Case N-416-1 Other 0 Pressure N/A psi Test Temp.~~
NJA OF NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8Y2 in. X 11 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. 'as amended by additional quality assurance requirements found in Contracts 90744,1721-00075 and Design Criteria BFN-50-708S and BFN-SO-C-710S. f I f U3CIO
FORM NIS-2 (Backf
9.
Remarks Replaced valves and piping on inlet side of level switches 3-LS-085-45C, -450, -45E and -45F with larger diameter components. Applicable Manu'acture~s Data Reports to be attached Modified CRD support 3-478468-241 CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. -=-re=.lp;:.:la::;c::.:e;;.m:.:;e;:.:n;.:.t-,-__ conforms to the rules of the repair or replacement Type Code Symbol Stamp -'-'N'-'-'A"'--_________________________________ _ Expiration Date --=.;N"-'/A..;.... ____________ _ Date ,20t!L CERTIFICATE OF INSERVICE INSPECTION I, Ihe undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of rt:A-'/l/FS'SFE and employed by /15 Ii cT' of p ]) have inspected the components described in this Owners Report during the period to - 0. , 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 warranty, expressed or implied, conceming 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 arising from or connected with this inspection. Commissions Inspecto(s Signature National Board, State, Provinee, and Endorsements Date
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS SUPPLEMENTAL SHEET
1.
~~Owner Tennessee Valley Authority (TVA)~~
2.
~~Plant Name 1101 Market Street Chattanooga TN 37402-2801 Address Browns Eerry Nuclear Plant (BEN) Nam~ P. O. Box 2000, Decatur, AL 35609-2000 Address~~
3.
~~Work Performed by --LT.... VcA~-B.... E..LN'_~------_---- Name P Q Box 2000 pecatyr AL 35609-2000 Address~~
4.
Identification of System System 085 Control Rod Drive (eRD) System Date May 30 2002 Sheet ---..2 __ of 2 ____________________ __ Unit I ->1,3 ______________________ --'-______ _ Work Orders (WO) C1-005501-001, 01-005501-002 and 01-005501-005 Design Change Notice (DeN) 50729 Stage 1 Repair Organization P.O. No., Job No., etc. Type Code Symbol Stamp -uNIU:IA:>..-___________ _ Authorization No. ....,NL!.J:fA:>..-________________ _ Expiration Date N/A (valves) ASME Sec. III 1989 Edition (less N-stamp)
~~5. (a)~~
Applicable Construction Code (piping) USAS 831.1.0 19 67 *
Edition, N/A

Addenda, N/A Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Built Replaced, or (Yes or Manufacturer Serial No.~~
No. Replacement No) Root Valve to Kerotest N/A NfA . 3-RTV-085-0286 NfA Replaced No LS-85-45E (Bottom) Root Valve to Elowserve E488T-1-3 N/A 3-RTV-085-0286 2002 Replacement No LS-85-45E (Bottom) 2" -800#-Gate-SW Root Valve to Kerotest N/A N/A .3-RTV-085-0288 N/A Replaced No LS-85-45E (Bottom) Root Valve to Elowserve E488T-1-4 N/A 3-RTV-085-0288 2002 Replacement No LS-85-45F (Bottom) 2" -800#-Gate-SW Piping Unknown N/A NfA N/A N/A Replaced No Piping Consolidated N/A N/A N/A N/A Replacement No Power Supply CRD Pipe Support TVA N/A N/A 3-47B468-241 N/A Replaced No CRD Pipe Support TVA NfA N/A 3-47B468-241 NfA Replacement No U3CIO I
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
1.
~~Owner Tennessee Valley Authority (TVA) Date May 3D, 2002 Name I 1101 Market Street Chattanooga, TN 37402*2801 Sheet of Address~~
2.
Plant Browns Ferry Nuclear Plant (BFN) Unit 3 Name Work Order (WO) 01-012431*OQO Address DeSign Change Notice (DCN) 50287A Stage 6 P. O. Box 2000. Decatur. AL 35609*2000 R"pair Organization P.O. No.* Job No.. etc.
3.
~~Work Performed by TVA*BFN Type Code Symbol Stamp NfA~~

~~~N~am-.. ------------------~~

~~P. O. Box 2000, Decatur, AL 35609*2000 Authorization No. NfA Address Expiration Date NfA~~
4.
~~Identification of System System 073, High Pressure Coolant Injection (HPCI) System~~
~~5. (a)~~
Applicable Construction Code USAS 831.1.0 19 67 *
Edition, NfA

Addenda, NfA Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or Manufacturer Serial No.~~
~~No. Built Replacement No) HPCI Pipe Support TVA N/A N/A 3-47B455*635 N/A Replacement! No Modification~~
7.
~~Description of Work Modification to HPCI Pipe Support 3*47B455*635.~~
8.
~~Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Other (8]- Pressure NfA psi Test Temp. N/A OF~~
See remarks NOTE: Supplemental Sheets In form of lists, sketches, or drawings may be used, provided (1) size is 8Y. in. X 11 in., (2) information in ~tems 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of thiS form
'as amended by additional quality assurance requirements found in Design Criteria BFN-SO-7073 and BFN-SO-C-71 05. r..:3C J I J
FORM NIS-2 (Back{
9.
Remarks Modification to HPCI Pipe Support 3-47B455-635 (DCN 50287A Stg 6) to reduce loading on HPCI Turbine inlet nozzle. Applicable Manufacture(s Data Reports to be attached Visual exam (VT-3) performed following modification. CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this ASME Code Section XI. replacement lepair Of replacement. conforms to the rules of the TypeCodeSymbolStamp ~N~/A~ __________________________________________________________________ _ Expiration Date -:.;N""/A..:.-_______________ _ Date ,20°2 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of
~~rE NJVe 55C&::~~
and employed by Ii 5/3 kC of Ii tJ II Tf"ryfn C r have inspected the components described in this Owner's Report duri~ the period /- 2 _ '-' =2 to ¥. 'I - 0 i2 , 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 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 arising from or connected with this inspection. Commissions 7#313:[' I' § /l/ /3/9 Inspecto(s Signature National Board. State. Province. and Endorsements Date I
ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN) UNIT 3 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME), SECTION XI, REPAIR AND REPLACEMENTS PROGRAM OMITTED NIS-2 REPORT FOR CYCLE 9 OPERATION (See Attached) I I I
1-
2.

3.
Owner Plant FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI Tennessee Valley Authority (TVA) Date March 7, 2001 Name 1101 Market Street Chattanooga, TN 37402-2801 Shef!t c: Address Browns Ferry Nuclear Plant (BFN) Unit 3 Name P. O. Box 2000, Decatur, AL 35609-2000. Work Orders 99-010016-000 and 99-010069-000 Address Repair Organization P.O. No.* Job No., etc. Work Performed by TVA-BFN Type Code Symbol Stamp N/A Name P. O. Box 2000, Decatur, AL 35609-2000 Authorization No. N/A Address Expiration Date N/A
4.
~~Identification of System System 069, Reactor Water Cleanup (RWCU) System (valve) ASME Section 111 Class 1,1986 Edition, less N-stamp~~
~~5. (a)~~
Applicable Construction Code (piping) USAS B31.1.0 19 67 *
Edition, N/A

Addenda, N/A Code Case (b)
~~Applicable Edition of Section XI Utilized for Repairs or Replacements 19 89~~
6.
~~Identification of Components Repaired or Replaced and Replacement Components ASME Code National~~
~~Repaired, Stamped Name of Component Name of Manufacturer Board Other Identification Year Replaced, or (Yes or Manufacturer Serial No.~~
No. Built Replacement No) RWCU Sys Retum Anchor/Darling EZ862-1-1 N/A 3-CKV-069-0628 1997 Replacement No Check Valve 4"-900# Uft Check RWCU Sys Retum Anchor/Darling EZ862-1-2 N/A 3-CKV-069-0629 1997 Replacement No Check Valve 4*-900# un Check
7.
~~Description of Work Repraced valve discs with new discs from the vendor.~~
8.
Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure rEI Other 0 Pressure N/A psi Test Temp. N/A NOTE: Supplemental Sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% In. X 11 in., (2) information in items 1 through 6 on this report Is Included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
~~as amended by additional quality assurance requirements found In P-97N2R-204635 and P-92ZMe.45195C Releases 1361103 & 1294333 and Design Criteria BFN-50-7069 and BFN-SO-C-7105.~~
I I I
FORM NIS-2 (Back)
9.
Remarks Replaced valve discs with new discs from the vendor. Applicable Manufacturer's Oata Reports to be attached CERTIFICATE OF COMPUANCE We certify that the statements made in the report are correct and this ASME Code Section XI. ~r~el::pla:::;c:::e:;.:m.:.:e::.::nt:.....,.__ conforms to the rules of the repair or replacement T~eCodeS~IStamp ~N~M~ ___________________________________________________________ __ Expiration Date...:.::N:.,:;/A.!-... __________________ _ Certificate of Authorization No. -:.;N::.;/A-=--___________ _ Signed,~~/d? //~ System Engineer ~ Otmeror~ ,2O~ Date CERTIFICATE OF INSERVICE INSPECTION d of Boiler and ressure V ssellnspecto :iand the State ~, flr c.c, of I, the undersigned, tloldlng a valid commission Issued by the National B or PrOvince of I and employed by ~~~r..LJ~~'--~-===!u;.~-~~-~----:-------_:__--_y-..,. have Inspected the components described in this Owner's Report during the period it _ &l z, t QDr.) to .3 *.20#./ , 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 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 arising from or connected with this inspection. Commissions National 8oarcI, State, ProW1ce. and Endorsements Date ...1-23 20 01}}

ML021980176

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