ML20199F272

ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation

ML20199F272
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1998
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18039A670	List: ML20199F272 ML20199F279
References
NUDOCS 9901210271
Download: ML20199F272 (100)

Text

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ENCLOSURE 1 l

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)

UNIT 3 l

AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME),

(

SECTION XI, INSERVICE INSPECTION (ISI), AND AUGMENTED EXAMINATIONS PROGRAM

SUMMARY

REPORT (NIS-1) FOR CYCLE 8 OPERATION (SEE ATTACHED) 9901210271 990112 PDR ADOCK 05000296 PDR q

OWNER: TENNESSEE VALLEY AlmiORITY PLANT. BROWNS FERRY NUCLEAR PLAST OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAhM 39602 CHATTANOOGA, TENNESSEE 37402 UNIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED.

COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED l'

INSERVICE INSPECTION

SUMMARY

REPORT 1

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OWNER: TENNESSEE VALLEY AUTHORITY PLANT: BROWNS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 3000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402

)

UNIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED TABLE OF CONTENTS i

APPENDIX I COVER SHEET j

l APPENDIX II FORM NIS-1 APPENDIX III SCOPE INTRODUCTION APPENDIX IV EXAMINATION

SUMMARY

ASME CODE CASES UNIT 3 INTERVAL STATUS PERSONNEL AND EQUIPMENT CERTIFICATIONS APPENDIX V MEniOD OF CALCULATING EXAMINATION COVf. RAGE EXAMINATION COVERAGE LIMITATIONS APPENDIX VI EXAMINATION PLAN (SECTION XI)

EXAMINATION PLAN OF CLASS 1 AND 2 COMPONENTS COMPONENTISOMETRIC DRAWINGS APPENDIX VII

SUMMARY

OFINDICATIONS ADDITIONAL SAMPLES ATTACHMENT 1 APPENDIX IWE - BFN CONTAINMENT INSERVICE INSPECTION PROGRAM ATTACHMENT 2 EXAMINATION PLAN (AUGMENTED) AND

SUMMARY

ATTACHMENT 3 SUPPLEMENTAL SUBMTITAL (CORRECTED INFORMATION-BFN UNIT 3 RPV EXAMINATIONS FROM THE INSIDE SURFACE CONDUCTED IN 1993)

ATTACHMENT 4 BFN UNIT 3 CYCLE 8 SCAN PLAN i

i l OWNER: TENNESSEE VAILEY AUTHORITY PLANT: BROWNS FERRY NUCLEAR PLANT l

OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 l

UNIT.

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED.

l COMMERCIAL SERVICE DATE: MARCH 1,1977

., N ATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED l

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APPENDIX I 1

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OWNER: TENNESSEE VALLEY AUTHORITY PLANT: BROWNS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT THREE CERTIFICATE OF AUlHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED COVERSHEET The followmg mformanm is provided in acw.h with the ASME Boder and Pressure Vessel Code Section XI,1989 Edince, paragraph IWA-6220.

1. Date of document complenen. October 15,1998 l

2. Name of owner and address of principal offices:

T-~ Valley Authority Office OfNuclear Power 1101 Market Street O-* 7. Tennessee 37402-2801

3. Name and address of the nuclear generstmg plant Browns FerryNuclear Plant PO Bax 2000 Decatur, Alah=== 35602 l

4. Name or number asagned to the nuclear power unit by TVA-l

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l Browns Ferry Nuclear Plant, Unit 3 l

5. Commercial operanon date ofunit March 1,1977 1

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OWNER: TENNESSEE VALLEY AUTHORTI'Y PLANT: BROWNS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 3000 110i MARKET STREET DECATUR, ALABAMA 35602 l

CHATTANOOGA, TENNESSEE 37402 l

UNIT.

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT NOT REQUIRED l

APPENDIX II l

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l FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules l

1. Owner Tenneasee Vallev Authority. 1101 Market St. Chattanoona. TN. 37402 (Name and Address of Owner)

2. Plant: Browns Ferry Nuclear P! ant PO Box 2000 Decatur. AL. 35602 (Name and Address of Plant)

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3. Plant Unit:

3

4. Owner Certificate of Authorization: Not Reauired

5. Commercial Senice Date: 03/01/77 6. National Board Number for Unit: Not Reauired

7. ComponentsInspected:

Manufacturer Component or Manufacturer or Installer State or National Acourtenance or Installer Serial No.

Province No.

Board No.

Reactor Pressure Contract No.

Vessel General Electric 67C21-91750 N/A N/A Various systems and components

( See Annandir VI)

TVA N/A N/A N/A l

The NIS-1 Owners Reoort for Inservice Inanections includa= Annandica= L IL IIL IV. V. VL and VII.

(excludino anomantad araminations)_

l Note: Supplemental sheets in form oflists, @*e% or drawings may be used provided (1) size is 8.5 in. X 11 in.,

I (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.

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FORM NIS-1 (brek) l

8. Exammation Dates:

08/21/1998 to 10/15/1998 f

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9. Inspection Period Identification:

First Insoection Period extendinn from 11/19/1996 to 11/18/1999.

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10. Inspection Interval Identification: Second 10-Year Interval extendina from 11/19/1996 l

to 11/18/2005.

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11. Applicable Edition of Section XI:

1989 Addenda: No Addenda

12. Date/ Revision ofInspection Plan-10/03/1998. Revision 2

13. Abstract of Exammations, Include a list of exammations and a statement concerning status of work required for current interval. See Appendix m. IV. V. VI. and VII. Examinations comolete the second outane of the first oeriod of the second insoection interval.

14. Abstract of Results of Examinations: See Accendix III. IV. V. VI. and VII.

15. Abstract ofCo Tective Measures: See Anoendix VII i

We certify that the statements made in this report are correct and the exammations and corrective measures taken conform to the rules of the ASME Code, Section

• 9-r Date lE '5el18 Signed Tennessee Vallev Authority Bf owner U'

Certificate of Authorization No.

Not Aoplicable Expiration Date Not Apolicable CERTIFICATE OF INSERVICE INSPECTION 1 The undersigned, holding a valid commisman issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Prmince of Tennessee and employed by HSBI & I of Hanford.CT.

have ia==*d he 9 m= = desented in this Owners' Data Report dunng the t

period 8/21/98 to 10/15/98, and state that to the best of my knowledge and belief, the Owner has perfor'ad ernminarians and taken correcuve measures desenbed in this Owners' Data Report in awders with the reqmrmnents of the ASME Code Section XI.

By signing this certificate nether the fa==*ar nor his employer makes any warranty, expressed or implied, concermng the exammations and correcuve measures desenbed 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 ansing from or connected with this inspection.

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Commissions TV 3/35 A)' ^7 "

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Inspectors Signature National Board, State, Province and No, r

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OWNER. TENNESSEE VALLEY AlmiORITY PIANT: BROWNS FERRY NUCLEAR PLANT

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OFFICE OF NUU. EAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 W.

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 j

NATIONAL BOARD NUMBElt FOR UNIT: NOT REQUIRED i

APPENDIX III l

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j OWNER.: TENNESS.IE VALLEY AUTHORITY PLANT. BROWNS l'ERRY NUCLEAR PLANT

[

OFFICE Of' NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602

{

CHA'ITANOOGA, TENNESSEE 37402 i

UNIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED f

l COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED j

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SCOPE This AppaaAv prendes an overnow of the inservice inspections (ISI) performed durms the unit 3, 4

i cycle 8 scheduled refuelmg outage on Class 1 and 2 n- ;-=- - for ASME Section XI Code credit j

and other ang=a*ad erammanans I

INTRODUCTION l

The exammations were performed durmg the unit 3, cycle 8 scheduled refueling outage in j

accordance with implemennng plant Survedlance Instruction, 3-SI-4.6.G " Inservice Inspection Program Unit 3." 3-SI 4.6.G is orgammed to comply with the ISI reqmrements of the 1989 Edition, s

no Addaada of the American Socuty of Mechamcal Fa_maaa s (ASME) Boiler and L we Vessel Code, Sectan XI, Division 1, Articles IWX-1000, IWX-2000, IWX-3000, and IWX-6000 in ash with Title 10 Code of Federal Regulaanna (CFR) Part 50, 50.55a(g); to implamant the Browns Ferry Nuclear Plans (BFN) Tach = cal Reqmrummit, TR.3.4.3, and to fulfill the reqmraments of SPP-9.1, and ASME Secnon XI.

Survedlance Instruction 3-SI4.6.G reflects the built-in lumtations of the origmal plant design, geometry, construccon, en=pana* matenals and the currers technology or state-of-the-art anada*uctive -.. lo techmques. The Survedlance Instruction specifies the nnadestructrve methods to be used and prendes schedule tables frcan winch specific items were selected for exammannn durms this outage The nondestrucave erammannas were performed in accordance with the ASME Boder and Pressure Vessel Code, Secnon XI,1989 Edraon, no Addaada and witnessed or venfied by an Authonzod Nuclear Inservice la=a-*ar (ANII)

The exammanana were perfonned by TVA ro_.a-*aa Services Orgamzation (ISO) under the direction of Browns Ferry Component F=i-

-mg. Augmentation of nondestructive exammation personnel was prended by ABB Combusnan Fa.m Nuclear Power NDE Services, GTS/Duratsk, Southwest Research Insnture, and General Electric Nuclear Energy (GENE)

Services.

An overnew ofISI actrwnes conasts of the followmg ASME Seccan XI Class 1, RPV Nozzle-to Shell Welds & Nozzle Inner Radii ASME Seccan XI Class 1 and 2 Piping Exammations e

ASME Section XI Class 1 and 2 Support Frammannna e

ASME Section XI RPV In Vessel Visual Inspection (IVVI) e An.===*ad fagna Activities 1

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OWNER: TENNESSEE VALLEY AUTHORRY PLANT: BROWNS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 3000 1101 MARKET STREET DECATUR, ALABAMA 35602 i

CHATTANOOGA, TENNESSEE 37402 UNIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT NOT REQUIRED.

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APPENDIX IV 1

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' OWNER: TENNESSEE VALLEY AUTHORITY PLANT: BROWNS PERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 3000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 I

UNIT:

THREE CERTIFICATE OF AUTHORI7.ATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED EXAMINATION

SUMMARY

The umt 3, cycle 8 ISI was the second scheduled refueling outage dunna the first inspection period of the second ASME Secnon XI 10-year inspection interval. A total of 35 ultrasonic,31 visual,17 magnetic particle, and 12 liquid ps.is exanunations were performed in support of code credit c%-:=-

, including additional samples and re ammmations (see Appendix VI, Exanunation Plan). Preservice inspections (PSD included 7 ultrasonic, 3 magnetic particle, 8 liquid ps.zit, and 7 visual exammations. Eleven Notification of Indications (NOO were issued to h=ar*

unacceptable conditions idennfied dunng the performance of the erammati=n. He NOl of the imace-phie conditions were evaluated by engmeermg and dispostooned (see Appendix VII, Summary of Tarkestman).

Additmaal erammatians were performed in awd-.cc with BFN's ="===*M inspection program I

and are included for infonnanon in Attachmars 2. A total of 144 ultrasome, 8 magnetic particle, 4 visual, and I liqmd penetrant erammannna were performed in accordance with the angm=*M l

Progrant l

Other ernmmatmas included In-Vessel Visual faWan (IVVD on unit 3 RPV internals and ultrasonic iaW= of the core shroud.

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1 OWNER: TENNESSEE VALLEY AtJTHORITY PLANT; BROWNS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 i

UNIT, THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED 1

COMMERCIAL SERVICE DATE: MARCH 1,1977 i

NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED ASME CODE CASES The following code cases were unhzed durmg the unit 3, cycle 8 outage:

i N-307-1 Revised Ultrasonic Exammanon Volume for Class 1 Bolting, Table IWB-2500-1, Exammanon Category B-G-1, When the Exammations Are Conducted From the Center Dnlled Hole,Section XI, Division 1 N-435-1 Alternanve Frammations Reqmrements for Vessels With Wall Thickness 2 in. or l

Less,Section XI, Division 1 N-457 Quah6 canon Specunen Notch Location for Ultrasonic Exammation of Bolts and Studs, Secuce XI, Division 1.

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N-460 Alternanve Exammation Coverage for Class I and Class 2 Welds,Section XI, Division 1 1

N-461 Alternanve Rules for Piping Calibranon Block Thickness,Section XI, Division 1 i

With thefollowing qualiper; Thickness measurements and weld contour of the l

pipe / component must be known and used by the inspector who conducts the UT l

examination.

N-491 Alternanvc Rules for Frammatinn of Class 1, 2, 3, and MC C -..;=m Supports of Light-Water Cooled Power Plants, Soccan XI, Dmsum 1.

N-503 Linuted Certificanca of Nondestnienve Exammation Personnel,Section XI, l

Dmsson 1 N-524 Alternate Frammatv= Requirements for Longitudinal Welds in Class 1 and 2 l

Pipmg - Socnon XI, Division 1 N-532 Alternative Rogarenants to Repair and Replacement Documentation Reqmramants and Inservice Summary Report Preparanon and Submission as Reqmrod by IWA-4000 and IWA-6000,Section XI, Division 1

)

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OWNER: TENNESSEE VALLEY AUTHORITY PLA. T: BROWNS FERRY NUCLEAR PLANT V

OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECAUJR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED l

UNIT 3 INTERVAL STATUS The BFN unit 3, cycle 8, ISI was performed durmg the second scheduled refueling outage of the first period of the second mterval. The component quantities mmi=i were determmed from 3-SI-l 4.6.0, Table A (Unit 2 Class I and 2 components) and from applicable BFN unit 3 relief requests.

l Table I summarues code credited exammations by category and percentage completed to date and l

demonstrates compliance mth ASME Section XI percentage regarements TABLE 1 ASME SECTION XI EXAMINATION

SUMMARY

FOR THE FIRST PERIOD OF THE SECOND TEN-YEAR INSFECTION INTERVAL CATEGORY

% COMPLETE COMMENTS B-A 33 %

B-B N/A B-D 32 %

B-E Damed to rystem hwho B-F 29%

B-O-1 33 %

B-O-2 28%

B-H N/A B-J 32 %

B-K-1 26 %

B-L-1 N/A B-L-2 100 %

B-M-1 N/A B-M.2 Deferral onmianihte B-N-1 Fach nened B-N-2 Deferral nemi==hle l

B-O Dererral nemianible B.P Refer to oressure test oronram B-O N/A C-A 25 %

C-B 33 %

C-C 27%

C-D N/A C-F-1 31 %

C-F-2 34 %

C.O N/A l

C-H Refer to cressure test oromm i

D-B 29%

l F-A 34 %

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l OWNER. TENNESSEE VALLEY AUTHORITY PLANT. BROWNS FERRY NUCLEAR PLANT l

OFFICE OF NUCLEAR POWER PO BOX 20C0

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l 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 l

UNIT:

THREE CERTIFICATE OF AlmiORIZATION: NOT REQUIRED.

COMMERCIAL SERVICE DATE: MARCH 1,1977 I

l NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED l

l PERSONNEL AND EQUIPMENT CERTIFICATIONS l

l NDE personnel cern6 cation records for TVA and contractor employees are mamtamed by TVA Nuclear Fnginemg Corporate, Inspection Senices Orgamzation (ISO). These records are maintamed as pernmnet QA records for the forty year plant life. Detads or specifics regarding NDE cernfication records should be directed to ISO IncatM at the Sequoyah Trammg Center in l

Soddy-Daisy, Tennessee at telephone number (423) 843-4026.

l NDE equipment certification records are mintainM by the TVA ISO staff. Detads or specifics regarding NDE equipment certification records should be directed to ISO located at the Sequoyah Trammg Center in Soddy Daisy, Tennessee at telephone number (423)843-4026.

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OWNFA TENNESSEE VALLEY AUTHORTTY PLANT. BROWNS FERRY NUCLEAR PLAST OFFICE OF NUCLEAR POWER PO BOX 2000 l

1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT:

THREE CERTIFICATE OF ALTIBORIZATION: NCrr REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED APPENDIX V l

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a OWNER; TENNESSEE VALLEY AlmiORITY PLAST. BROWNS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602

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CHATTANOOGA, TENNESSEE 37402 1

l UNIT:

THREE CERTIFICATE OF AlmiORIZATION: NOT REQUIRED l

COMMERCIAL SERVICE DATE MARCH 1,1977 l

l NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED.

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i METHOD FOR CALCULATING EXAMINATION COVERAGE

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The ASME Section XI Code 1989 Edition, no =ddaada requires that essentially 100% of the exanunation area / volume be completed. To msure compliance with this requirement during the i

perfonnance of the ISI volumetric exammations, the beam path angles and technique parameters

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were optmuzed to maximim coverage. The information is necessary where there is interference i

and/or linutations causing a reduction in the exammation volume which requires calculating the i

coverage achieved.

I Surface exammations are conW on 100% of the weld length plus a defmed amount of base material adjacent to the weld. Surface areas are calculated in those instances where there may be j

interference and/or limitations causing a reduction in the exammation area. The Code required surface exanunation area coverage is generally the weld plus 1/2-inch of base material adjacent to the weld.

The Code required volumetric exammation volume area coverage for each type of piping weld or j

nozzle-to-vessel weld is illustrated in the figures of IWB-2500 or IWC-2500. For piping welds, the t

volume width generally includes the weld plus 1/4-inch on each side while volume thickness 4

generally includes the lower 1/3t of the piping thwkaans for the length of the weld. For nozzle-to-l vessel welds, the volume wukh generally includes the weld plus 1/2t (ts/2) on each side of the weld j

while volume thickness generally includes the acre component thickness (i.e., full volume). The i

volume changes with vanaticos in weld " '--Man (e.g., transinon between diLise pipe j

thickness or nozzle-to-vessel configuranon). Therefore, it is necessary to determine the required volume for each group of similar welds to facilitate scanner positionag for v_4==ad ultrasonic f

exarnmations and scan paths for mamial ultrasonic exammations.

Paragraph IWA-2232 of ASME Secuan XI, requires that the ultrasonic exammations be conducted l

in accordance with App-d-I of ASME Section XI. App-d= I requires that the ultrasonic exammation of piping systems be conducted in accordance with App-Av III of ASME Section l

XI, and the nozzle-to vessel welds be enaawted in accvidw with Article 4 of ASME Section V, j

1989 Edman as supplemented by Apa=4v I of ASME Section XI. Appendix III and Article 4 l

defme the applicable -

.... methods (e.g., exammation angles, scan directions) to be used oo g

durmg erammarian Paragraphs IWA 2221 and IWA-2222 of the ASME Section XI, requires that j

surface erammatinas be ennawted in accordance with Article 6 or 7, as applicable, of ASME Section V,1989 Edinon.

j TVA developed procedure N GP-28 to provide a standardized method for calculation of 2

exammation coverage in those mstances where configuration or int dmoce from other j

ComipGim.ans restricts the eYRmmatian and Cause an exammation Coverage linutation.

Cor.pGs-..Jwelds with exammation coverage knutations were evaluated in terms of the feasibility j

of other NDE tad =L=2a= or methods to increase exammation coverage or for Code Case N-460

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applicability.

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OWNER: TENNESSEE VALLEY AUTHORITY PLANT: BROWNS FERRY NUCLEAR PLANT i

OPTICE OF NUCLEAR POWER PO BOX 2000

)

1101 MARKET STREET DECATL%, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT HIREE CERTIFICATE OF ALTTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED EXAMINATION COVERAGE LIMITATIONS A tabulatw= of NDE exm===tinns receiving less than the required essermally 100% exammation l

coverage durmg the unit 3, cycle 8 ISI are contamed in this Appenda.

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'The followag items / components had crammatum limitatiana causing erammatinn coverage to bc less than 100%. TVA elected to use Code Case N-460 which states that when the entire exammatum area or volume cannot be exammad due to interference by another U-q== or part l

geometry, a rMan in er==== nan coverage for Class 1 or 2 welds may bc arramad provided l

the reduction in coverage for that weld is less than 10%.

1 EXAMINATION METHOD &

SYSTEM COMPONENT ID COVERAGE CALCULATED REPORT NO RIiRS DSRiiR 3-06 UT >90%

R-024' RWCU RWCU-3-001-043 UT >90%

R 101 (PSI)

RWCU RWCU-3-001-044 UT >90%

R-l02 (PSI)

RPV N4B-SE MT >90%

R-104 RPV N4BSE UT >90%

R-142 RPY NM-1R UT >90%

R 217 causmg a reduction in l

The followmg seems/campan-en had h===twma on the NDE er== manna coverage that arcaadad the <10% allowed by Code Case N-460. The Surveillance Instruenon, 3-SI-4.6.G, Inservice Inspecnon Program will be revuod to ir-ij~i.m these j

exammation coverage lan*=*w== in the form of Requests for Relief (RFR). Pro rem revisions, includmg RFR's, will be subautted to the NRC.

EXAMINATION METHOD &

j SYSTEM COMPONENT ID COVERAGE CALCULATED REPORT NO.

RFR NO.

RPV NIA Noxtle4o Vem! Weld UT 72%

R 203 3-ISI-7 RPV N2B Nostle-to Vem! Weld UT 77%

R 206 3 151-7 RPV N2D Nostle-to-Vem! Weld UT 77%

R 207 3-151-7 RPV N2F Noxnte-to Vem! Wald UT 77%

R-208 3-ISI-7 RPV N3B Nostle-to-nsnel Weld UT 75%

R-209 3-151-7

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RPV N4B Nostle40-Vem! Weld UT 68%

R-211 3-ISI-7 l

RPV N4C Nostle4o-nmi Weld UT 68%

R-212 3-15l-7 RPV NSA Noale4o-Vem! Weld UT 64%

R 216 3-151-7 RPV NM Nonfe4o-Vem! Weld UT 71 %

R-217 3-151-7 l

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OWNER: TENNESSEE VALLEY AUTHORITY PLANT: BROWNS FERRY NUCLEAP. PLAST OFFICE OF NUCLEAR POWER PO BOX 2000 l

1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 l

UNIT.

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED.

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COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED.

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APPENDIX VI i

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OWNER: TENNESSEE VALLEY AIREORITY PLANT: BROWNS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UhTT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED.

COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED f

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l EXAMINATION PLAN OF CLASS 1 AND 2 COMPONENTS i

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OWNER: TENNESSEE VALLEY AUTHORITY PLANT. BROWHS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 39602 CHATTANOOGA, TENNESSEE 37402 l

UNIT:

THREE CERTIFICATE OF AUIRORIZATION: NOT REQUIRED.

COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED l

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EXAMINATION PLAN The following prmtout is the outage ISI report designed to meet the reporting requirements of the ASME Section XI Code,1989 Edition, no AMenda, Anicle IWA-6000. The report contams unit 3, cycle 8 ISI data for Class 1 and Class 2 components selected for ASME Section XI credit.

Class 3 data and reports are enntsiW in the Browns Ferry ISI Final Plant Report.

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CSS TCS-3-417 ISI-0331-C 01 B-F B5.10 UT BF45 19900924 R179 P

CSS TCS-3-426 ISl4331-C 01 B4 B9.11 PT 19900921 RO11 P

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CSS TSCS-3-418 IS14331-C 01 84 80.11 PT 19000922 R014 P

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1ST ADolTKNeAL SAAAPLE FOR NOI U3C4011 FWS 3-47B415-38 ISI-0336-C 01 F-A F1.10C VT-3 19900929 R059 P

FWS 3-478415-38-IA IS84336-C 01 54-1 810.10 MT 19900928 R042 P

REPAIRED AND REEXAA490E0 UNDER R194 i

FWS 3-478415-42-IA IS44336-C 01 B K-1 B10.10 MT 19981007 R133 P

1ST AD0lTIONAL SARAPLE FOR U3C8411 FWS 3478415 47-IA IS84336-C 01 BK-1 B10.10 MT 19981004 R108 P

1ST AD00TIONAL 5AAGPLE FOR NOl u3C8411 FWS 3-478415-584A IS4-0336C 01 BK-1 B10.10 MT 19901007 R134 P

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MSS 3-478400483-IA IS14338-C 01 B-K-1 810.10 MT 19900929 R056 P

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OWNER: TENNESSEE VAI. LEY AITIHORIlY FLANT: BROWNS FERRY NUCLEAR PLANT NUCLEAR POWER GROUP P.O. BOX 2000 1881 MARKET STREET DECATUR. ALABAMA 35602 CHATTANOOGA. TENNESSEE 37402 CERTIFICATION OF AITIllORIZATION: NOT REQUIRED EXAM REQUIREMENT 89E-82 UNIT:THREE CYCLE:8 COMMERCIAL SERVICE DATE: MARCH I.1977 N ATIONAL BOARD NUMBEF F(Mt UNIT: NOT REQUIRED Syeesm Congsonant ISO Dummeng Caespory amm Emmm Cantwaton Exam Emam Emam Conunenes Nweer Numeer SeeaWed Semeant Deen Report Reeds MSS DMS4-29 IS84354 4 01 C.F-2 C5 81 MT 19981003 R005 P

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MSS HPAS-344-10 ISI-0355-C 02 F-A F1.20C VT-3 19981002 R120 P

MSS KMS-3-114 ISI-03294 02 B-J 89.11 MT 19981006 R136 P

MSS KMS-3-114 ISl4329C 02 BJ 89.11 UT BF-104 19981007 R146 P

MSS MS-34+49 IS84355-C 01 F-A F1.20C VT-3 19981011 R200 P

PART OF ADDITIONAL SAMPLE FOR NOf-26 MSS MS-344-12 ISl4355-C 01 F-A F1.20C VT-3 19981002 R119 P

MSS MS-344-13 IS84355-C 01 F-A F1.20C VT-3 19981011 R150 P

REINSP. REPORT R201 SETTING PASSED MSS MS-3-H-13-IA ISl4355C 01 C-C C3.20 MT 19981002 R088 P

MSS MS-3+1-15-IA IS84355 C 01 C-C C3.20 MT 19981002 R089 P

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MSS MS-344-17 IS84355C 01 F-A F1.20C VT-3 19981002 R097 P

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MSS PCV1-3418 IS84313 4 01 B-G-2 B7.70 VT-3 19981005 R138 P

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RPV 3-SI-3.3.1 A 8-P B15.80 VT-2 19981013 R226 P

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RPV 3-St-3.3.1.C C-H C7.70 VT-2 19981015 R227 P'

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RPV 3-SI-3.3.2.B C-H C7.30 VT-2 19981006 R228 P

RPV 3-S4-332.8 C-H C7.70 VT-2 19981006 R228 P

RPV 3-SI-3 3.4 C-H C7.30 VT-2 19980926 R231 P

RPV 3-S8-3.34 C41 C7.50 VT-2 19980926 R231 P

RPV 3-S1-334 C-H C7.70 VI-2 19980926 R231 P

RPV 3-S1-3 3 5 C-H C7.30 VT-2 19980923 R232 P

RPV 3-S1-335 C-H C7.70 VT-2 19900923 R232 P

RPV 3-S1-337 C41 CT.30 VT-2 19900909 R233 P

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I OWNEIL-TENNE %EE VALLEY AUIHO8tITY PLANT: BROWNS FERRY NUCLEAR PLANT NUCLEAR POWER GROUP P.O. DOX 2888 1988 MARKET S11tEET DECAlllR, ALABAMA 3M82 CHATTANOOGA, TENNESSEE 37482 CERTIFICATION OF AUTHORIZATRON:NOT REQUIREp EXAM REQUIREMENT 89E42 UNIT:THREE CYCLE:8 COMMEltCIAL SERVICE DATE: MARCH I,1977 NATBONAL BOARD NUMBER FOR UNIT: NOT REQUIRED syssum CongsaneM ISO Osameng Casmoory asm Enam Cameramon Enam Enam Esem Comunents i

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RPV INTERIOR IS84220C 02 B-N-1 B13.10 VT 19981003 R218 P

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RPV NSA ISl4331-C 01 B-D B3.90 UT BF-t8 19981006 R216 P

EXAnd PEGORasED BY GE NUCLEAR ENERGY RPV NSA-IR ISl4331-C 01 B-D B3.100 UT BF-18 19981008 R216A P

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MSS HPAS4-H-02 ISI-0355-C 02 P0742 F-A F1.20C VT4 19981002 Rt27 P

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l OWNER: TENNESSEE VALLEY AtJIHORITY PLANT: BROWNS FERRY NUCLEAR PLANT l

OFFICE OF NUCLEAR POWER PO BOX 2000 i

1101 MARKET STREET DECARJR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED I

l l

APPENDIX VII l

1 I

l 1

l l

l l

___. _ __.. -.. _ _ __ _ __ _ _. _._ _._ =__. _ _ _ _ _ _ - -- _... _.___ _ ___ _._.

l i

OWNER; TENNESSEE VALLEY AUTHORITY PLANT. BROWNS FERRY NUCLEAR PLANT I

OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT:

THREE CERTIFICATE OF AUTHOR!fATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED

SUMMARY

OF INDICATIONS i

Indications detected durms the performa-of the ISI for Browns Ferry Nuclear Plant unit 3, cycle i

8 were evaluated in accordance with approved wntten procedures Generally, exanunation results yielded either No Recordable Indications (NRI) or Recordable Indications.

l Recordable Indications were evaluated to deternune their origin. Indications d-W to be of a

)

geometric, metallurgical, or sinular origin were dispositioned as non-relevant. Indications dsm ed to be of a non-geometric, non-metallurgical, or similar origin were dispositioned as relevant and required additional measures such as further evaluation in accordance with ASME Section XI acc+;=== standards, engmeenng analysis, repair, or rephw The following list is a summary of unacceptable indications detected and corrective measures taken dunng the unit 3, cycle 8 outage Not CODE CoMPONMT WDD DON RESOLUDON ADDITIONAL no.

CAT.

LDanr1En DEsC> tenon SauPin U3Cs.

FA 3-s7Bo63 301 muCTUa PRErfounTEvauATED NOT 00e Distortion ACCEPTABuASG REQUIRED U3Cs.

F4 3-41 Boss 303 SinUCTUa PRa7oU1TEVALUATED NOT 009 DIS 70RT10N ACCOTAB2ASG REQUIRED

• U3CS.

BJ GR.3 63 IGSCC EvALUATEDACCEPTARGFDR NOT ojo NRRBO MW. 3 PT!El.CTCZB APPLICAB2 0313C 100 %

EXAMWED

\\

THISCTCW v3Co-B-K 1 3-47B42 3 LNEAR WDICATIONREMOVED TES(4) of1 M

WDXADON PER SSP-730 APPENDLTU U3Co.

C-C MS-bH-11 M LSEAR EVALUATED ACCEPTABUAS G NOT 013 WDD DON FDR CONTWLED SDtVXE REQUIRED U3Co-CC MS3H13-M LlhEAR EVALUA1EDACCEPTABWASLS NOT 016 WDICADON FDR CONTNUED SERVICE REQUIRED U3CB.

F4 RPAS-3-N-03 SETIING OUTOF EVALUATED ACCEPTABMASIS NOT 019 RANGE FDR CONTWLED SER51CE PEQUIRED USCS-F4 MS-3 H 17 LOOSENUT EVMUATEDACCEPTABGASIS NOT 011 FOR CONTWLE SERB 7CE REQUERED U3CS-CC MS-3-H 16 M LNEAR EVALUA1EDACCEPTABMASIS NOT 020 INDGTION FOR CONTWLED SERF 1CE '

PEQUIRED U3CB.

BJ TJtmt 3-191

f. BEAR ACCRPTABU UTlll2 LNG NOT 021 WDiCATION SUPPILMENTAL Fol EYAM REQUIRED U3Co.

F4 MS 3 H 13 SET!1NG OUTOF RESET 10 CORItECTSETTING NOT 026 RANGE APPUCAB2 100 %

EXAM 1hED THISCTCG

' Weld GR 3-63 was exanuned/ evaluated and the readts subautted to the NRC in accordance with NUREG 0313 and was not presented to the AIA for concurrence for ASME Section XI Code credit.

OWNER. TENNESSEE VALLEY AI.TTHORITY PLANT. BROWNS FERRY SICLEAR PLAST OFFICE OF NUCLEAR POWER FO BOX 2000 1101 MARKET STREET DECATUR, ALARAMA 35602 CHATTANOOGA, TEbHESSEE 37402 UNIT; THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED.

i l

ADDITIONAL SAMPLES i

SYSTEM COMPONENT CATEGORY ITEM NO.

EXAM FEEDWATER 3-47B415-36-IA B-K-1 B10.10 MT FEEDWATER 3-47B415-42-IA B-K-1 B10.10 MT FEEDWATER 3-47B415-47-IA B-K-1 B10.10 MT FEEDWATER 3-47B415-58 IA B-K-1 B10.10 MT MAIN STEAM F-A Fl.20C VT-3

• 100% population of Category F-A, Item Number Fl.20C wu scheduled for exammation durmg Unit 3 Cycle 8 outage l

l I

i

OWNER: TENNESSEE VALLEY Al/THORITY PLANT. BROWNS tTRRY NUCLEAR PLANT OFTICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, /LABAMA 35602 j

CHATTANOOGA, TENNESSEE 37402 UbTT:

THREE CERTIFICATE OF AIITHORIZATION: NOT REQUIRED.

COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED ATTACHMENT 1 i

i l

l

APPENDIX IWE BFN CONTAINhENT INSERVICE INSPECTION PROGRAM AShE SECTION XI SUBSECTION IWE The information contained in this Appendix is provided in accordance with the requirements of 10CFR 50 55a(b)(2)(x)(A), evaluation ofinaccessible areas, and 10CFR50.55a(b)(2)(x)(D), evaluation for additional examinations, as they pertain to containment inservice examinations performed during the BFN Unit 3 Cycle 8 refueling outage.

The subject exammations were performed in accordance with ASME Section XI Subsection IWE,1992 Edition /1992 Addenda. BFN Unit 3 is in the first period of the i

first examination interval.

i i

i l

l i

l APPENDIX IWE Page 1 of14

APPENDIX IWE l

l Report No: CISI-004 Component: Torus Hatch 3 X 223 (Bolting)

Condition / Indication: VT-1 exammation determined that 2 of the 20 torus hatch boss had deformed threads.

EVALUATION OFINACCESSIBLE AREAS 10CFR50.55a(b)(2)(x)(A)

(1) Description of the type and estimated extent of degradation, and the conditions that led l

to the degradation:

l Minor thread deformity was noted. No thread deformity ns noted in the area of thread l

engagement He indications were most hkely caused by handling during the disassembly process, and had no impact on the functional capability of the component.

(2) Evaluation of each area, and the result of the evaluation:

No degradation was noted which could be present in inaccessible areas.

l (3) Description of necessary corrective actions:

No corrective action necessary, the condition was determmed not to be a defective condition.

The engmeering evaluation concluded that the bolts could be replaced as a maintenance good practice, and they subsequently were replaced.

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:

2 of 20 bolts had minor thread deformity. No damage existed in the thread engagement area, and the nuts still turned freely on the studs. He mdications were most likely caused by handling durmg the disassembly process.

(2) The acceptability of each flaw or ares, and the need for additional examinations to verify that similar degradation does not exist in similar components:

The condition had no impact on the structural mtegrity or seahng capability of the component, and was determined not to be a defective condition. Therefore, additional exammations are not warranted.

(3) A description of the necessary corrective actions:

No corrective action necessary, the condition was determmed not to be a defective condition, ne engmeenng enluation concluded that the bolts could be replaced as a mamtenance good practice, and they subsequently were replaced.

(4) The number and type of additional examinations to ensure detection of similar degradation in similar components:

No additional exammations required.

l APPENDIX IWE Page 2 of 14

-. - ~

APPENDlX IWE t

I l

Report No: CISI-002 Component: Torus Hatch 3-X-200B (Boltmg)

Condition / Indication: Durmg VT-1 exanunation, 5 of 30 bolts were found to have deformed threads.

EVALUATION OFINACCESSIBLE AREAS 10CFR50.55a(b)(2){r)(A)

(1) Description of the type and estimated extent of degradation, and the conditions that led to the degradat*on:

Minor thread deformity was noted. No thread deformity was noted in the area of thread engagement. The indications were most likely caused by handhng durmg the disassembly l

process, and had no impact on the functional capability of the wop (2) Evaluation of each area, and the result of the evaluation:

No degradation was noted which could be present in inaccessible areas.

(3) Description of necessary corrective actions:

No corrective action necessary, the condition was determmed not to be a defective condition.

The engmeering evaluation concluded that the bolts could be replaced as a maintenance good practice, and they subsequently were replaced.

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:

5 of 30 bolts had minor thread deformity. No damage existed in the thread engagement area, and the nuts still turned freely on the studs. 'Ihe indications were most likely caused by handling durmg the disassembly process.

(2) The acceptability of each flaw or area, and the need for additional esaminations to verify that simdar degradation does not exist in similar components:

'Ihe condition had no impact on the structural mtegnty or seahng capability of the component, and was determmed not to be a defective condition. Therefore, additional exammations are not warranted.

(3) A description of the necessary corrective actions:

No corrective action nemanry, the condition was determmed not to be a defective condition.

The engmeermg evaluation concluded that the bolts could be replaced as a maintenance good practice, and they subsequently were replaced.

(4) The number and type of additional examinations to ensure detection of similar degradation in sindar components:

No additional exammations required l

l l

I I

APPENDIX IWE Page 3 of 14

APPENDIX IWE Report No: CISI-011 Component: Drywell Head Flange Bolts Condition / Indication: Dunng VT-1 exanunation,2 bolts exhibited deformed threads, I nut contamed an axial indication, and I bolt was cut off dunng flange disassembly. All 208 drywell head flange bolts and nuts were enmiad F. VALUATION 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:

Minor thread deformity of 2 bolts and a mmor axial indication of I nut was noted. These indications were mmor and did not affect the seahng capability of the bolting. nese indications were most likely caused by handling dunng disassembly. Additionally, I bolt was cut off i

during disassembly to facihtate removal of the drywell head.

l (2) Evaluation of each area, and the result of the evaluation-De noted conditions were not defective conditions with respect to the structural integrity or l

sealing capability of the component, excepting the bolt which was purposely cut during l

removal. Therefore, no defective conditions exist which may be present in inaccessible areas.

(3) Description of necessary corrective actions:

The bolt cut out dunng head removal was replaced as a Section XI Repair / Replacement. No other corrective actions were warranted l

\\

j ADDITIONAL EXAMINATIONS 10CFR50.55a(b)(2)(x)(D) i (1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation:

l Minor thread defonsty of 2 bolts and a minor axial indication of I nut was noted. Rese l

indications were most likely caused by handimg dunng disassembly. Addhlly, I bolt was l

cut off durmg disassembly to facihtate removal of the drywell head.

(2) The acceptability of each flaw or area, and the need for additional examinations to verify that sindar degradation does not exist in similar components:

l None of the subject flaws affected the structural integnty or seahng capability of the component ne bolt which was cut was not a service related problem. He indications were evaluated not to be defects. Herefore, addrtional exammations are not warranted.

(3) A description of the necessary corrective actions:

De bolt cut out durms head removal was replaced as a Section XI Repair / Replacement. No other corrective actions were warranted (4) The number and type of additional examinations to ensure detection of similar degradation in similar components:

No additional exammanons reqmred-l APPENDIX IWE Page 4 of14 i

l I

APPENDIX 1%T.

Report No: CISI-013 Component: CRD Hatch Bolting Condition / Indication: Durmg VT-1 exarmnation, I stud / nut could not be disassembled due to seizure.

l EVALUATION OF INACCESSIBLE AREAS 10CFR50.55a(b)(2)(x)(A) l (1) Description of the type and estimated extent of degradation, and the conditions that led to the degradation:

Additional exammation determmed that there was no degradation of the component. Oil penetrant was used to unsetze the nut, and subsequem exanunation was acceptable. There was no galling of threads or other condition which would impact the component function. The capability of the component to perform its function ofleak tightness was not affected by the subject condition.

i (2) Evaluation of each area, and the result of the evaluation:

Since no degradation was found durmg re-inspection, no degradation exists which could be present in inaccessible areas.

(3) Description of necessary corrective actions:

he condition was corrected by mamtenance and the exammation satisfactorily completed. No other corrective action is warranted 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:

There was no degradation of the v-.;;== Oil paved was used to unsetze the nut, and subsequent exammation was acceptable.

(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:

)

Here was no galhng of threads or other condition which would impact the component function.

The capability of the en=nnnent to perform its function ofleak tightness was not affected by the subject condition. Therefore, no =AAMan=1 exammations are warranted (3) A description of the necessary corrective actions:

He condition was corrected by mamtenance and the exammation satisfactorily completed. No other corrective action is warranted.

(4) The number and type of additional examinations to ensure detection of similar degradation in similar components:

No addMr=1 exammations are required.

APPENDIX IWE Page 5 of14

APPENDIX TWE Report No: CISI-017 Component: Pressure Suppression Charnher Ext:rior Stuface Condition / Indication: Indications were noted dunng the VT-1 exanunation of the Pressure Suppression Chamber (PSC) Exterior Surface air / water interface region.

EVALUATION OF INACCESSIBLE AREAS 10CFR50.55a(b)(2)(x)(A) l (1) Description of the type and estimated extent of degradation, and the conditions that led i

to the degradation:

1 The mdications consist of numerous areas of coatmgs distress, rangmg from minor scratches l

and nicks to areas of ba e metal. The condition of the base metal ranges from no oxidation to light oxidation in the areas of coatmgs distress. De conditions are pnmanly due to the age of the coatmgs and mechanical wear caused by trafHe in the area.

l (2) Evaluation of each area, and the result of the evaluation:

The conditions noted do not impact the structural integnty or leak tightness of the PSC, and are expected conditions based on the age and semce condition of the wog The pnmary reason this area is being inspected is due to the conditions which could potentially affect the interior surface There is no accelerated degradation exhibited by this 0- ;==* nerefore, no degradation exists which may be present in inaccessible areas..

l (3) Description of necessary corrective actions:

No corrective actions are required The coatmgs may be repaired as part of the routme coatmgs mamtenance program.

i ADDITIONAL EXAMINATIONS 10CFR 50.55a(b)(2)(x)(D) l (1) Description of each Raw or area, including the extent of degradation, and the l

conditions that led to the degradation:

He indications consist of numerous areas of contags distress, rangmg from minor scratches and nicks to areas of bare metal De ma<htion of the base metal ranges from no oxidation to l

light oxidation in the areas of contags distress The conditions are pnmarily due to the age of l

the coatings and machan cal wear caused by trafHe in the area.

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(2) The acceptability of each fisw or area, and the need for additional examinations to verify that similar degradation does not exist in similar components:

)

~

l The degradatien is not a defective condition with respect to the com,nanant function of pressure boundary or structural mtegnty. Herefore, additional exammations are not warranted.

(3) A description of the necessary corrective actions:

No correenve acuans are required. The coatmgs may be repaired as part of the routine coatmgs mamtanance program.

(4) The number and type of additional examinations to ensure detection of similar degradation in sindar components:

l 100% of the PSC exterior surface was==ined in the air / water sterface area on this report.

l Based on the above evaluation, no additional exammations are wariius d.

i APPENDIX IWE Page 6 of14 i

I APPENDLX IWE Report No: CISI-022 Component: Drywell Interior Surface Condition / Indication: Coui.tions noted durms the VT-3 exammation of the drywellinterior surface, in various areas on elention 563 ft. He areas enmmai had been idenufied for coatmg repairs, and this exammation was performed prior to surface preparation to satisfy the requirements of IWE-2500(b), exun nation of coatings prior to removal.

EVALUATION OF INACCESSI.9tE AREAS 10CFR50.55a(b)(2)(x)(A) j (1) Description of the type and estimated extent of degradation, and the conditions that led to the degradation:

he indications consisted of numerous nicks, gouges, and some tightly adherms rust. The condition of the base metal is good, with no indications of significant base metal loss. He conditions noted do not impact the structural mtegnty or leak tightness of the steel contamment vessel, and are expected conditions based on the age and service condition of the component.

There a no accelerated degradation exhibited by this component (2) Evaluation of each area, and the result of the evaluation:

There is no degradation which affects the structural mtegnty or contamment function of the steel contamment vessel. The conditions noted are WM conditions with respect to the age and service conditions of the m 3 =--= nerefore, no adverse condition exists which may be present in inaccessible areas.

(3) Description of necessary corrective actions:

l This exammation was performed to document the condition of the base metal prior to coating repair. He area was re i-a~*M followmg contag repair as required by IWE 2600. No

=dAsan) corrective actions are warranted.

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ADDITIONAL EXAMINATIONS 10CFR 50.55a(b)(2)(xXD)

(1) Description of each flaw or area, including the extent of degradation, and the l

conditions that led to the degradation:

The indications consisted of numerous nicks, gouges, and some tightly adhenng rust. He condition of the base metal is good, with no indications of significant base metal loss. The indications are due to the age of the coatmgs and mechanical wear caused by traffic in the area.

(2) The acceptability of each Asw or area, and the need for additional examinations to verify that siradar degradation does not exist in similar components:

The conditions noted do not impact the structural mtegnty or leak tightness of the steel contamment vessel Therefore, no additional examinations are warranted Q1 A description of the necessary corrective actions:

T tis exammation was ; L d to document the condition of the base metal prior to coating rqair. The area was re-i=g+::M followag coating repair as required by IWE-2600. No Alitional corrective actions are warranted (4) The number and type of additional examinations to ensure detection of similar j

degradation in sindar components:

l No additional exammations are warranted APPENDIXIWE Page 7 of14 l

APPENDIX IWE Report No: CISI 026 Component: Drywell Interior Surface Condition / Indication: Indications noted durmg the VT-1 exammation of the drywell interior surface, at the concrete floor to steel liner interface on elevation 550 ft, in areas where the moisture seal barrier (MSB) had been excavated for replacamee ne area exammed is normally maccessible, and this exammation was performed to assess the condition of the steel contamment vessel base metal prior to MSB replacement 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:

The indications consist of general rust and intemuttent pitting, with some flakmg of the protective coatings at the liner interface with the MSB. Some moisture was noted in the crevice area. Pit depth measurements were taken in areas of appreciable wall loss, with pit depth rangmg from 18 mils to 35 mils. De conditions noted are resultant from moisture intrusion below the MSB, which has been completely inspected durmg the current outage, with areas of degradation designa:ed for replacamam his will preclude further moisture intrusion into the affected area. We moisture noted in the crevice area was further aggravated by a washdown performed at the be inning of the outage for decomtamination purposes.

(2) Evaluation of each area, and the result of the evaluation:

The maxunum pit depth was.035 inch, which corresponds to 3% of the design base metal thickness of 1.125 inches Recent UT thickness readmgs of the area imm~U *aly above th:

MSB indicated that the exterior surface has not experienced significant degradation. He conditions noted do not impact the structural irwyisy or leak tigha= of the steel contamment vessel, and are --~M conditions based on the age and service condition of the component There is no accelerated degradation exhibited by this 9- ;-:--= ne concrete to floor interface does not exhibit signs of oxidation relief paths to the surface, which would be indicative ofliner

~

plate corrosion beneath the concrete. He Moisture Seal Barner has been exanuned and defective portions are being replaced. Herefore, no adverse condition exists which may be present in inaccessible areas.

(3) Description of necessary corrective actions:

The conditions noted do not reqmre further corrective action.

ADDITIONAL EXAMINATIONS 10CFR 50.55a(b)(2)(x)(D)

(1) Description of each Asw or area, including the extent of degradation, and the conditions that led to the degradation:

De indications consist of general rust and internuttent pittmg, with some flaking of the protective coatmgs at the liner interface with the MSB. Some moisture was noted in the cresice area. Pit depth measurvents were taken in areas of appreciable wall loss, with pit depth rangmg from 18 mils to 35 mils. The conditions noted are resultant from moisture mtrusion below the MSB, which has been completely inpai dunng the current outage, with areas of degradation designated for reph~=am His will preclude further moisture intrusion into the affected area. De moisture noted in the crevice area was further aggn:vated by a washdown performed at the b--V.g of the outage for decomtammation purposes caao nem pne.

APPENDIX IWE Page 8 of 14

APPENDDC IWE i

I (2) The acceptability of each flaw or area, and the need for additional examinations to i

verify that similar degradation does not caist in similar components:

1 The maximum pit depth was.035 inch, which corresponds to 3% of the design base metal thickness of 1.125 inches. Recent UT thickness readmgs of the area immMiately above the MSB indicated that the exterior surface has not experienced significant degradation. The conditions noted do not impact the structural in:egrity or leak tightness of the steel contamment vessel, and are expected condt' ions based on the age and service condition of the component.

There is no accelerated degradation exhibited by this g+y==

100% of the affected area was examined, and additional exammations s re not warranted (3) A description of the necessary corrective actions:

No corrective actions are warranted (4) The number and type of additional examinations to ensure detection of similar degradation in similar components:

No =dditian=1 exammations are warranted.

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t APPENDLX IWE Report No: CISI-029 Component: Pressure Suppression Chamber Interior Surface Condition / Indication: Indications noted dunng the VT-1 exammation of the Pressure Suppression Chamber (PSC) intenor surface, air / water interface area, elevation 536 ft. to elevation 538 ft.

This exammation was performed to satisfy the requirements of Table IWE-2500, Exammation Category E-C, item No. E4.11.

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:

The indications consist of numerous areas of coatmgs distress, rangmg from discoloration to 1

minor locahzed corrosion. He con & tion of the base metal ranges from no oxidation to localized pitting with base pit depth ofless than 20 mils in all but one area of coatmgs distress.

s i

With coating dry film thickness average of 17 mils, base metal loss is 3 mils or less in these i

affected areas. One indication measured 28 mils (bay Il), which correlates to 15 mils of base metal loss. He conditions noted are expected conditions based on the age and service condition of the component.

(2) Evaluation of each area, and the result of the evaluation:

He overall loss of base metal is mmunal in the affected areas. He area is exposed to demmerahzed water during service. He con &tions noted do not impact the structural mtegrity 2

or Icak tightness of the torus, and there is no accelerated degradation exhibited by this component _ ne conditions noted are WM con &tions based on the age and service

}

condition of the e-q = =. and there are no defective con &tions which may exist in maccessible areas.

3 (3) Description of necessary corrective actions:

No corrective actions are required 1

l ADDITIONAL EXAMINATIONS 10CFR 50.55a(b)(2)(x)(D) j (1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation:

The indications consist of numerous areas of coatmgs distress, rangmg from discoloration to

(

minor IWi=i corrosion. The condition of the base metal ranges from no oxidation to 4'

locahzed pitting with base pit depth ofless than 20 mils in all but one area of coatings distress.

With coatmg dry film thickness average of 17 mils, base metal loss is 3 mils or less in these affected areas. One indicanon measured 28 mils (bay 11), which correlates to 15 mils of base a

j metal loss. De conditions noted are WM conditions based on the age and service condition of the e - ------ - Dese c=l*6= are not considered to be defective.

(2) The acceptability of each flaw or area, and the need for additional examinations to 3

j verify that similar degradation does not exist in similar components:

The conditions noted do not impact the structural integrity or leak tightness of the torus, and there is no accelerated i,.ddion exhibited by this ++; = e 100% of the air / water j

interface area was==iwi nerefore, no additional exammations are warranted.

i Ccaused on nest pass 4

APPENDIX IWE 3.

Page 10 of 14 a

'T

1 APPENDIX IWE (3) A description of the axessary corrective actions:

j No corrective actions an warranted.

t (4) The number and type of additional examinations to ensure detection of similar degradation in similar components:

No additional exammations are wstranted l

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APPENDIX IWE Page 11 of 14

APPENDIX IWE

)

Report No: CISI-030 Component: Drywell Equipment Hatch 3-X-IA Condition / Indication: Indications noted durmg the VT-1 exammation of the drywell equipment hatch. His exammation was performed to satisfy the exammation of bolted connections per Table IWE 2500 Categery E.G.

EVALUATION OFINACCESSIBLE 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:

Numerous indications of denting in the o-ring mating surface were noted. The majonty of the indications appear to be old indications that are shallow dimples and minor dents less than 1/32 inch in depth, with no sharp edges or gouges. The indications are a result of mechanical damage, due to heavy traffic durmg outages.

(2) Evaluation of each ares, and the result of the evaluation:

ne indications are not defective with respect to the functional capability of the hatch. None of these indications will impact the seahng capability of the component. Herefore, there are no adverse conditions which may be present in inaccessible areas.

(3) Description of necessary corrective actions:

No corrective actions are warranted.

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:

Numerous indications of dentmg in the o-ring matmg surface were noted. The majority of the indications appear to be old indications that are shallow dimples and minor dents less than 1/32 inch in depth, with no sharp edges or gouges. He indications are a result of mechanical damage, due to heavy traffic durmg outages.

(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:

l ne indications are not defective with respect to the functi=1 capability of the hatch. None of these indications will impact the sealmg capability of the component. Herefore, there are no adverse conditions which require sti-J exammations.

(3) A description of the necessary corrective actions:

No corrective actions are warranted (4) The number and type of additional examinations to ensure detection of similar degradation in similar components:

No additional exammations are warranted l

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APPENDIX IWE Page 12 of 14 l

APPENDIX IWE Report No: CISI-034 Component: Equipment Hatch 3 X-1B Condition / Indication: Indications noted during the VT-1 exammation of the drywell equipment hr.tch. His exammation was performed to satisfy the exammation of bolted connections per Table IWE-2500 Category E.G.

EVALUATION OFINACCESSIBLE 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:

Numerous indications of denting and minor corrosion in 2 locahzed areas of the o-ring mating surface were noted. He majority of the indications appear to be old indications that are shallow dimples and minor dents less than 1/32 inch in depth, with no sharp edges or gouges.

The indications are a result of mechanical damage, due to heavy traffic during outages, and exposure to moisture at some point in the past. nread damage was noted in 2 of 12 bolt holes.

This damage is due to mechanical wear during assembly / disassembly.

(2) Evaluation of each area, and the result of the evaluation:

ne indications in the flange surface are of minimal depth and will have no affect on the sealing capability of the component. The thread damage is not significant since it is nummal and the force of the pressure differential between the drywell and the reactor building pro 5 ides the actual sealmg force for the joint. Herefore, there are no areas of degradation which may exist in inaccessible areas..

(3) Description of necessary corrective actions:

No corrective actions are warranted ADDITIONAL EXAMINATIONS 10CFR 50.55a(b)(2)(s)(D)

(1) Description of each flaw or area, including the extent of degradation, and the conditions that led to the degradation:

Numerous indications of dentmg and minor corrosion in 2 locahzed areas of the o-ring mating surface were noted. He majority of the indhations appear to be old indications that are shallow dimples and mmor dents less than 1/32 inch in depth, with no sharp edges or gouges.

He indications are a result of mechanical damage, due to heavy traffic dunng outages, and exposure to moisture at some point in the past. nread damage was noted in 2 of 12 bolt holes.

His damage is due to muhanical wear durmg assembly / disassembly.

(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:

ne indications in the flange surface are of mmunal depth and will have no affect on the sealing capability of the comycee.at. He thread damage is not significant since it is minimal and the force of the pressure differential between the drywell and the reactor building pro 5 ides the actual sealing force for thejoint. Herefore, adAManal exammations are not warranted.

(3) A description of the necessary corrective actions:

No corrective actions are warranted.

(4) The number and type of additional examinations to ensure detection of similar degradation in similar components:

No additional exammations are warranted.

l APPENDIX IWE Page 13 of 14

APPENDDC IWE l

Report No: CISI-035 Component: Equipment Hatch O rings Condition / Indication: Durms VT-3 exammation of O rings for Drywell Equipment Hatch 3-X-18, the O rings were found to be cut and torn.

EVALUATION OFINACCESSIBLE AREAS 10CFR50.55a(b)(2)(x)(A)

(I) Description of the type and estimated extent of degradation, and the conditions that led to the degradation:

The inner and outer O ring were found to be cut and torn. His damage was done when the O rings were removed from their grooves.

(2) Evaluation of each area, and the result of the evaluation:

The O rings were adequately performmg their sealing function prior to removal, as evidenced by the results of the as-found LLRT performed just prior to openmg the hatch. The condition is attributed to damage resultant from removal of the O rings, and is not a defective condition with respect to the inservice condition. Herefore, there is no degradation which may be present in inaccessible areas.

(3) Description of necessary corrective actions:

The O rings were being replaced as a routme mamtenance practice. No additional corrective action is warranted.

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:

The inner and outer O ring were found to be cut and torn. His damage was done when the O rings were removed from their grooves.

(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 O rings were =M=*dy performmg their seahng function prior to removal, as evidenced by the resuhs of the as-found LLRT performed just prior to opemng the hatch. He condition is attributed to damage resultant from removal of the O rings, and is not a defective condition with respect to the insenice condition. Therefore, additional exammations are not warranted (3) A description of the necessary corrective actions:

He O rings were being replaced as a routine mamtmance practice. No additional corrective action is warranted.

(4) The number and type of additional examinations to ensure detection of similar degradation in similar components:

No additiarmi exammations are warranted.

APPENDIX IWE Page 14 of 14

OWNER: TEbHESSEE VALLEY AU1110RITY PLANT; BRO %KS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATLP, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED.

COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT NOT REQUIRED i

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ATTACHMENT 2 i

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i OWNER; TENNESSEE VALLEY AUTHORITY PLANT: BROWNS FERRY NUCLE / R PLANT OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT.

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED.

1 AUGUMENTED EXAMINATION PLAN The following prmtout is the unit 3 cycle 8 outage ISI plan for ="=an'M exammations as identi6ed in 3-SI-4.6.G.

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EXAM REQUIREMENTS gel-e2 OWNER: TENNEMEE val LEY AtrIMORi1Y PLANT: BROWNS FERRY NUCLEAR PLANT 302-02 NUCt. EAR POWER GROUP P.O. DOX 2000 2

IISI MARKET STREET DECATUR, ALABAMA 3S642 M2 CHA1TANOOGA, TENNESSEE 37402 CERTIFICATION OF AUDlottlZATSON: NOT REQUIRED UNIT:THREE CYCLE:8 COMMERCIAL SERVICE DATE: MARCH I,1977 NATIONAL WOARD NUMBER FOR UNIT: NOT REQUIRED System C

1801 %

Enam Caengary som Emem Cateremon Enam Esam Enem e-kneer Recpuement Nwseer Scssoeusse Semnemsd Does Report Residen i

CRDS RCRD-3-33 ISl4332402 802-02 C

NUO313 UT BF40 19981003 R135 P

CRDS RCRD 3-33 ISl4332-C 02 802-02 C

NUO313 UT BF-76 19901003 R135 P

CRDS RCRD-3-44 IS14332-C 02 B0142 7112 V0141 UT BF41 19981005 R147 P

CRDS RCRD-3-45 IS14332-C 02 B0142 7112 V0141 UT BF-29 19981006 R149 P

CROS RCRD-3-49 ISl4332 C 02 80242 C

NUO313 UT BF-29 19981006 R143 P

CRDS RCRD-3-50 IS64332-C 02 80242 C

NUO313 UT BF-29 19961006 R144 P

CRDS RCRD-3-52 ISl4332-C 02 802-02 C

NUO313 UT BF-29 199R1006 R145 P

CRDS RCRDS-3-03 ISl4332-C 02 901-02 7112 V01-01 UT BF-35 19901004 R148 P

CSS DCS-344 ISl4331-C 01 902-02 C

NUO313 UT BF-79 19900022 R121 P

CSS DCS-345 ISl4331-C 01 B0242 C

NUO313 UT BF-79 19000923 RIOT P

CSS DCS-3-13 ISI-0331-C 01 B02-02 C

NUO313 UT BF-79 19000924 R040 P

t CSS DCS-3-14 IS84331-C 01 802-02 C

NUO313 UT BF-79 19000623 RIOS P

CSS DSCS-341 IS$4331-C O1 90242 C

NUO313 UT BF-79 19900923 R191 P

l CSS DSCS-342 IS84331-C 01 80242 C

NUO313 UT BF-79 19000023 R190 P

CSS DSCS-347 ISl4331-C 01 80242 C

NUO313 UT BF-79 19900923 R199 P

f CSS DSCS-348 ISI-0331-C 01 B0242 C

NUO313 UT BF-79 19000923 R039 P

CSS DSCS-3-09 ISl4331-C 01 80242 C

NUO313 UT BF-79 19000924 R192 P

f CSS TCSW3-405 ISl4331-C 01 B02-02 C

NUO313 UT BF-75 19000926 R066 P

CSS TCS:3-406 ISI-0331-C 01 B0242 C

NUO313 UT BP-75 19900926 R047 P

i CSS TCS-3-410 ISI-0331-C 01 802-02 C

NUO313 UT BF-75 19900930 R069 P

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CSS TCS-3-421 ISI-0331-C 01 B02-02 C

NUO313 UT BF-75 19900927 R045 P

CSS TCS-3-422 ISl4331-C 01 B02-02 C

NUO313 UT BF-75 19900927 R067 P

i l2/\\7198 Page I of 9 t

- - - - ~

EXAM CEQUIIEMENTS 908-92 OWNER: TENNESSEE VAll EY AUTHORITY PLANT: BROWNS FERRY NUCLEAR PLANT 882-82 NUCLEAR FOWER GROUP P.O. ROX 2000 2

1101 MARKET STREET DECATUR. ALABAMA 39602 M2 CHATTANOOGA.TENNES$EE 37482 CER11HCA110N OF ALTIl00RIZATION: NO T REQUfRkD UNIT:THREE CYCLE:8 COMMERCIAL SERVK'E DATE: MARCH I.1977 NATIONAL BOARD NUMBER FOR UNIT: MOT REQUIRED V

2 Syeese C-_

ISO Droudng Enam Casagory ham Enam Camramon Emam Enam Enam Commeses Nunter Respamment Nweeer Sdiseded Sammend Does Rapest Ameds CSS TCS-3-426 IS$4331 C 01 B0242 C

NUO313 UT BF-75 19900924 R046 P

CSS TSCS-3 408 IS44331-C 01 80442 84 TS40G MT 19900927 R017 P

CSS TSCS4408 ISHD31-C 01 80442 B4 TS40G UT BF-75 19981001 R107 P

CSS TSCS4-423 IS443314 Of 90442 84 TS46G MT 19900923 R016 P

CSS TSCS4-423 IS84331 C 01 B0442 B4 TS46G UT BF-75 19981001 R111 P

FWS GFW-3-12 IS84327-C 01 80442 B4 TS46G MT 19900927 R038 P

FWS GFW-3-12 IS84327-C 01 80442 B,J TS46G UT BF-75 19900930 R000 P

FWS GFW-3-26 IS84327-C 01 804-02 B4 TS46G MT 19900927 R037 P

[

FWS GFW-3-26 ISI-0327-C 01 804-02 B-J TS46G UT BF-75 19000930 R079 P

FWS KFW-3-39 ISl4327-C 01 B0442 BJ TS46G MT 19900928 R057 P

FWS KFW-3-39 IS84327-C 01 B0442 B4 TS46G UT BF-75 19980930 R078 P

I HPCIS 3-47845H26 CHM-24134 02 P07-02 F-A F1.20C VT-1 19981003 R103 P

tFCIS HPCI-M1H09 CHM-2407-C 02 P0742 C-F C5.51 MT 19961003 R091 P

HPCIS HPCI-3419L000 ctg 4-2407-C 02 P07-02 C-F C5.51 UT BF-42 19981003 R098 P

tP CIS HPCI-3419010 CHM-2407-C 02 P07-02 C.f-2 C5.51 MT 19980921 R003 P

HPCIS HPCI-3419-010 CHM-2407-C 02 P07-02 C-F-2 C5.51 UT BF-42 19900824 R004 P

ifCIS HPCI-3-019-011 Cted-2407-C 02 P0742 C-F C5.51 MT 19981003 R002 P

t IPCIS HPCl-3-019-011 CHM-2407 C 02 P0742 C-F C5 51 UT BF-42 19981004 R099 P

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HPCIS THPCI-3-070 ISl4333-C 01 80442 B-J TS46G MT 19900929 R052 P

HPCIS THPCI-3-OF0 ISI-0333-C 01 B04-02 B4 TS46G UT BF-05 19981005 R053 P

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MSS GMS-3-15 ISt-0329-C 02 B04-02 B-J TS46G MT 19900927 ROSO P

MSS GMS-3-15 ISI-0329-C 02 804-02 B-J TS46G UT BF-104 19981006 R132 P

i 12/17/9N Perc 2 aff l

s EXAM REQUI'J_MENIS 301C2 OWNElt-TENNESSEE VALLEY ALTH90RITY PLANT-BROWNS FERRY NUCLEAR PLANT B0242 NUCLEAR POWER GROUP P.0 B O X 3000 2

BBGE MARKETSHEET DECATUR, ALARAMA JStel 2

CHATTANOOGA. TENNESSEE 37402 CER11FICATION OF ALTHOORIZATION: NOT REQUIRED g,y UNIT:THREE CYCLE:S COMMERCIAL SERVICE DATE: MAltCH 5,1977 NATIONAL BOARD NUMBER FOR LMIT NOT REQUtRED system e

Isolkemus Exam Cassemy amm Enem Castramon Exam Esam Enam Comuneven temeer Regwamare nunner smesses sanneurs pues Report answas MSS GMS-3-32 IS84329 C 01 804-02 84 TS48G MT 19980929 R051 P

MSS GMS-3-32 IS64329 C 01 B0442 B-J TSeeG UT BF-104 19981004 R110 P

MSS IPAS-3-H-02 ISl4355C O2 P0742 F-A F1.20C VT-3 19981002 R127 P

MSS HPAS-3-H47 IS64356 C 02 P0742 F-A F1.20C VT-3 19981002 R128 P

MSS PCV1-3418-PBC IS64313-8 01 P0742 B-G-2 87.50 W-3 19981005 R139 P

MSS PCV1-3-1794C ISl4313-8 01 P07-02 EMI-2 B7.70 VT-3 19981005 R140 P

MSS PCV1-3-179-PBC IS84313 4 01 P0742 842 87.50 VT-1 19981003 R126 P

MSS PCV1-3-179-VBC IS84313 4 01 P0742 B-G-2 87.50 VF-1 19981003 R125 P

RECR 3-478465-2048 IS64337-C 01 V0142 F-A F1.10C VT-1 19981004 R122 P

RECR GR-341 IS8432SC 01 80242 C

NUO313 LTT BF-57 19900929 R160 P

RECR GR 342 IS84328-C 01 80242 C

NUO313 UT BF-57 19000929 R170 P

RECR GR-3-04 ISl432SC 01 B0242 C

NUO313 UT BF-02 19000929 R082 P

RECR GR-3-07 ISI-0328-C 01 80242 C

NUO313 UT BF-02 19000930 R081 P

RECR GR-3-28 ISl432SC 02 80242 C

NUO313 UT BF-57 19000927 R167 '

P RECR GR-3-29 IS84328-C 02 802-02 C

NUO313 UT BF-57 19900926 R176 P

RECR GR-3-30 IS8432&C 02 B0242 C

NU0313 UT BF-02 19900025 R071 P

RECR GR-3-33 IS84328C O2 B0242 C

NUO313 UT BF-02 19900926 R073 P

RECR GR-3-55 IS84328-C 01 B02-02 C

NUO313 UT BF-57 19900930 R159 P

RECIR GR-3-56 ISl4328-C 01 B0242 C

NUO313 UT BF-57 19900930 R157 P

RECIR GR-3-58 IS84328-C 01 802-02 C

NUO313 UT BF-57 19000930 R175 P

RECIR GR-3-59(OL)

IS14328 C 02 B0242 E

NUO313 UT BF43 19960929 RO44 P

PER 8FPER970437 RECIR GR-341 IS14328C O2 B02-02 C

NUO313 UT BF-57 19900929 R164 P

12/I7/98 Page 3 ef 9

_____J

. ~ - - - ~..... ~. -

- -.. -. -. ~

- - - ~ - ~.

EXAM REQUIREMENTS 301-02 OWNER: 1ENNESSEE VALLEY AUTHORITY PLANT: BROWNS FERRY NVCLEAR PLANT y

98242 NUCLEAR POWER GROUP P.O.SOK 2000 303-42 gg,gg4gggg. STREET DECATUR, ALARAMA 3%82

[

30442 mg CHATTANOOGA, TENNESSEE 37402 CERTIFICATION OF AtrIMORIZATION: NOT REQUIRED UNIT:THREE CYCLE:O COMMERCIAL SERVICE DATE: MARCH l.1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED Syenom Compensee IS0 0routng Emern Camagery hem Enem Cettwesen Enam Enem Emem Coneesses temuner moveremare souneer smeeused soundens Does Report noeums L

RECR GR442 IS84328 C 02 80242 C

NUO313 UT BF-57 19901006 R171 P

RECR GR443 IS4-032SC O2 80242 C

NUO313 UT BF-57 19901004 R172 P

RESOULTIOse DATA ON Rest RECR GR-343A IS8432SC 02 80242 C

NUO313 UT BF-59 19000926 R074 P

RECR GR443B IS84320-C 02 80242 C

NUD313 UT BF-59 19000026 R070 P

RECR KR-341 ISl4320-C 01 80242 C

NUO313 UT BF-59 19000929 R063 P

i RECR KR442 ISl43264 01 802-02 C

NUO313 UT BF-57 19900330 R174 P

l RECR KR-344 IS84320-C 01 802-02 C

NUO313 UT BF-59 19900930 R064 P

RECR KR4-23 IS84326 4 02 B0242 C

NUO313 UT BF-59 19900928 R075 P

RECR KR-3-24 ISl4328-C 02 80242 C

NUO313 UT BF-57 19900927 R165 P

RECR KR-3-26 IS84328-C 02 802-02 C

NUO313 UT BF-59 19900926 R072 P

RECR KR-3-45 IS8432SC Of B02-02 C

NUO313 UT BF-57 19900926 R161 P

l I

RECR KR-346 ISI-03284 01 802-02 C

NUO313 UT BF-57 19981002 R156 P

RECR KR447 ISl4328-C 01 80242 C

NUO313 UT BF-57 19900930 R162 P

i RECE KR-348 IS84328 4 01 80242 C

NUO313 UT BF-57 19900929 R173 P

RECR KR-349 IS84326 4 01 B0242 C

NUO313 UT BF-59 19900929 R065 P

RECR KR-3-50 IS84328 4 02 B0242 C

NUO313 UT BF-57 19900929 R163 P

RECR KR-3-51 ISI-03284 02 B02-02 C

NUO313 UT BF-57 19900927 R166 P

RECR KR-3-52 IS84328-C 02 90242 C

NUO313 UT BF-57 19900927 R166 P

j RECR KR-3-53 ISI-03264 02 80242 C

NUO313 UT BF-59 19900927 R060 P

i

[

REC 41 RWR-3-017-004 ISI-0320 C 01 P07-02 B-J R9 20 PT 19901014 R204 P

Rf.CIR RWR-3-017-005 IS14326-C 01 P07-02 B-J 89 20 PT 19901014 R203 P

fuiCIR RWR-3-017-007 ISl43284 01 P07-02 B-J 89 20 PT 19901014 R204 P

I2/I7/98 Page 4 of 9

EXAM CiQUIIEMEN13 Bel 42 OWNER: TENNESSEE VALLEY AtrIMORITY PLANT: BROWNS FERRY NUCLEAR PLANT B0242 NUCLEAR POWER GROUP P.O. BOX 2000 30342 litt MARKETSIREET DECATUR, ALABAMA 35682 M2 CHATTANOOGA. TENNESSEE 37482 CERTIFICATION OF AUDOORIZATION: NOT REQUIRED

-82 UNIT:I14REE CYCLE:8 COMMERCIALSERYBCE DATE: MARCH 8. 3977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED 43 Syeese Ce w ISO Diestig Enem Cateemy eum Enem Casarecen Enem Enem Enem Commeses senseer naqueement souneer sdisease seenesse Dean neport nemme RECIR RWR-3417-000 IS8432SC 01 P0742 B-J B0.20 PT 19981014 R204 P

RHRS 3-478452-3179 IS8434SC 01 V01-02 NIA NIA VT-1 19981005 R137 P

RHRS DRHR442 IS84383 4 10 80242 C

NUO313 UT BF-102 19980921 R178 P

RHRS DRHR-343 IS84330C 01 80242 D

NUO313 UT BF-57 19981002 R004 P

LESS THAN 50% COVERAGE RHRS DRHR-343B IS84330 C 01 80242 G

NUO313 VT-2 19961013 R202 P

RHRS URHR444 IS84330C 01 B0242 C

NUO313 UT BF-57 19980930 R006 P

RHRS DRHR-345 ISl43304 01 80242 C

NUO313 UT BF-57 19981002 P

RHRS DRHR-346 IS64330-C 01 80242 C

NUO313 UT BF-57 19981006 R155 P

RHRS DRHR 3-07 ISl4330C 01 80242 C

NUD313 UT BF-57 19981003 R158 P

RHRS DRHR-3-11 ISI-0393C 11 80242 C

NUO313 UT BF-102 19980919 R177 P

RHRS DRHR-3-12 IS84330 4 01 80242 D

NUO313 UT BF-57 19981005 R130 P

LESS THAN SO% COWERAGE RHRS DRHR-3-13 IS84330 C 01 802-02 C

NUO313 UT BF-57 19981003 R124 P

RHRS DRHR-3-13B IS84330 C 01 B0242 G

NUO313 VT-2 19981013 R202 P

f RHRS DRHR-3-14 IS84330C 01 802-02 C

NUO313 UT BF-57 19981004 R116 P

RHRS DRHR-3-15 ISl4330-C 01 80242 C

NUO313 UT BF-57 19981002 R186 P

RHRS DRHR-3-16 1584330C 01 80242 C

NUO313 UT BF-57 19981003 R182 P

RHRS DRHR-3-19 1S84330C 01 80242 C

NUO313 UT BF47 19981004 R113 P

RHRS DRHR-3-21 ISl4330C Of B02-02 C

NUO313 UT BF-87 19981006 R197 P

RHRS DRHR-3-22 ISI-0330-C 01 B0242 C

NUO313 UT SF47 19981006 R196 P

RHRS DRHR-3-23 ISI-033GC 01 B02-02 C

NUO313 UT BF47 199810C6 R195 P

i RHRS DSRHR-3-01 ISI-0330-C 01 B02-02 C

NUO313 UT BF-57 19981005 R185 P

RHRS' DSRHR-3-02 ISI-0330 C 01 B0242 C

NUO313 UT BF-57 19981005 R184 P

l l

12/17/98 Page 5 ef f

e.

~.

EXAM CEQUIREMENTS Bel 42 OWNER: TENNESSEE VALLEY ALTillORil'Y PIANT: BROWNS FERRY NUC1h R PLANT 882-82 NtICEEAR POWER GROUP P.O. BOX 2W98 303-42 1I01 mal 1ET STREET DECA 11)R. AlaRAMA 35682 39442 N2 CHATTANOOGA.TENNLSSEE 37442 CERTIFICATION OF AUTilORIZATSON: NOT REQUIRED UNIT:THREE CYCLE:8 COMMERCIAL SERVICE DATE: MARCH I.1977 NATIONAL BOARD NtlMBER FOR UNIT: NOT REQUIRED y

3 System Canyonome NiO Dreams Enam Casagery hem Emam Centreenn Exam Enam Ezam Cakw NwNear Requremert Nunter SMM Standard Date Report Reeuna PJES DSRHR-303 IS84330-C 01 80242 C

NUO313 UT BF-57 19981005 R160 P

RHRS DSRHR-344 ISI-0330 C 01 B0242 C

NUO313 UT BF-57 19981001 R084 P

RHRS DSRHR-344A IS84334C 01 80242 C

NUO313 UT BF-57 19900930 R083 P

RHRS DSRHR-345 IS84330C 01 B02-02 C

NUO313 UT BF-57 19981004 R115 P

RHRS DSRHR-345A IS84330-C 01 80242 C

NUO313 UT BF-57 19981004 R114 P

RHRS DSRIR-346 ISI-0330 C 01 804-02 BJ TS48G PT 19981002 R093 P

RHRS DSRHR-3-06 IS84330-C 01 B0442 84 TS46G UT BF-57 19981002 R183 P

RHRS DSRHR-3-06 IS84330-C 01 80242 C

NUO313 UT BF-57 19981002 R183 P

RHRS DSRHR-347 ISI-0330-C 01 B02-02 C

NUO313 UT BF-57 19981001 R181 P

RHRS DSRHR-3-08 1544330C 01 B02-02 C

NUO313 UT.

BF47 19900925 R024 P

RHRS DSRHR-349 ISI-0330C 01 802-02 C

NUO313 UT BF-8T 19981006 R194 P

RHRS DSRHR-3-10 IS8433SC 01 B0242 C

NUO313 UT BF-87 19981006 R193 P

RHRS FCV7448 IS84330-C 01 VD142 8-G-2 B7.70 VT-1 19981001 R061 P

RtRS TRHR-3-191 158-0330C 01 90242 C

NUO313 UT BF-99 19981007 R151 P

RPV ACCHCOV-1 IWIEXAM B06-02 SIL462 71145 UT 19981007 R221E P

EKM4 PERFORh4ED BY GE NUCLEAR ENERGY RPV ACCHCOV-2 IWIEXAM B0642 SIL462 71145 UT 19981007 R221F P

EXM4 PERFORAGED BY GE NUCLEAR ENERGY RPV COREStR-3+1-1 IWIEXAM B06-02 SIL572 71144 UT 19981006 R221 P

EKM4 PERFORMED BY GE NUCLEAR ENERGY RPV CORESHR-3#2 IWIEXAM B06-02 SR 572 71144 UT 19981007 R221A P

EXM4 PERFORMED BY GE NUCLEAR ENERGY RPV CORESHR-3#3 IWIEXAM B0642 SIL572 71144 UT 19981007 R2218 P

EXM4 PERFORA4ED BY GE NUCLEAR ENERGY RPV CORESHR-3-H-4 IWIEXAM B06-02 SIL572 71144 UT 19981007 R221C P

EXM4 PERFORa4ED BY GE NUCLEAR ENERGY I

RPV CORESHR-3#5 IWI EXAM B0642 SIL572 71144 UT 19981007 R221D P

EXM4 PERFORA4ED BY GE NUCLEAR ENE RGY RPV CS4N4CMRA-4A IWI EXAM B0342 SIL289 71141 UT 19981002 R222 P

EKM4 PERFORa4ED BY GE NUCIEAR ENE RGY I2/I7/98 Pege 4 of 9

EXAM CEQUICEMEN15 33142 OWNER-TENNESSEE VALLEY AirlHOltITY PLANT: BROWNS PT.RRY NUCLEAR PtANT 30242 NUCLEAR POWER GROUP P.O. BOE 2005 M2 IlotMARKET$1REET DECA 1FR, ALABAMA 35402 30442 m2 CHA1TANOOGA. TENNESSEE 37402 CERTIFICATION OF AITI140RIZATSON: NOT REQUIRED UNIT:11 TREE CYCLE:8 COMMERCIAL SERVICE DATE: MARCH I 1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED V

2 Syseum e--

ISO Dramag Enam Caengary Rom Enem Cataramon Enam Enam Enem Canumenes scisseur Regumement lessear Seimehene Semndant Dean Report Rennsta RPV CS-DNCMRA-48 IWI EXAM B0342 SIL200 71141 UT 19981002 R222 P

EMas PEMOpmIED SY GE leUCLEAR E9EERGY RPV CS-DNCMRA-4C IWI EXAM B0342 SIL289 71141 UT 19981002 R222 P

Emes PEMORbsED SY GE feUCLEAR ENERGY RPV CS-DNCANLA 4D IWl EXAM B034:2 SIL299 71141 UT 19981002 R222 P

Emes PEMORadED BY GE 8eUCLEAR EteERGY RPV CS-DNCMRA4 IWIEXAM B0342 SIL200 71141 UT 19981002 R222 P

EMAI PEMOmsED BY GE peuCLEAR EteERGY RPV CS-DNCMRA4 IWI EXAM B0342 SIL200 71141 UT 19981002 R222 P

EMas PEMORadED SY GE seUCLEAR EseERGY RPV CS-DNCMRA-7 IWIEXAM B0342 SIL200 71141 UT 19981002 R222 P

EMas PEMORhdED SY GE NUCLEAR EleERGY RPV CS-DNCANIA4A IWI EXAM 903-02 SIL200 71141 UT 19981002 R222 P

Emes PERFORadED SY GE NUCLEAR ENERGY RPV CS-DNCMRA4B IWIEXAM B03-02 SIL209 71141 UT 19981002 R222 P

Emes PEMORbsED BY GE 80UCLEAR EpeERGY RPV CS-DNCMRS-4A IWIEXAM B0342 SIL289 71141 UT 19981002 R222 P

EMas PEMORadED BY GE 900 CLEAR EfeERGY RPV CS-DNCMRIMB IWI EXAM B0342 SIL298 71141 UT 19981002 R222 P

Emes PERFOmsED BY GE NUCLEAR ENERGY RPV CS-DNCMRINC IWIEXAM B0342 SE289 71141 UT 19981002 R222 P

EMas PEMOmadED BY GE NUCLEAR EfeERGY RPV CS-DNCMRB-40 fWIEXAM B0342 SIL209 71141 UT 19981002 R222 P

EMas PERFORedED SY GE NUCLEAR EteERGY RPV CS-DNCMRB-5 IWIEXAM B0342 SE289 71141 UT 19981002 R222 P

EMad PERFORedED BY GE teUCLEAR EteERGY RPV CS-DNCANtIM)

IWIEXAM B0342 SIL289 71141 UT 19981002 R222 P

Emes PERFORhdED BY GE NUCLEAR EteERGY RPV CS-DNCMtS-7 IWIEXAM B0342 SIL299 71141 UT 19981002 R222 P

Emes PEMORadED SY GE psUCLEAR EfeERGY RPV CS-DNCMRS4A IWIEXAM 90342 SE200 71141 UT 19981002 R222 P

EMAS PERFORRAED BY GE 9eUCLEAR EfeERGY RPV CS-DNCMRS4B IWIEXAM B0342 SE209 71141 UT 19981002 R222 P

Emes PERFORIsED BY GE NUCLEAR EteERGY RPV CS-DNCWIC-4A NVI EXAM B03-02 SIL289 71141 UT 19981002 R222 P

Emes PERFORbdED BY GE feUCLEAR EpeERGY RPV CS-DNCMRC-48 IWIEXAM B03-02 SE289 71141 UT 19981002 R222 P

EMAS PERFORhdED SY GE NUCLEAR EfeERGY RPV CS-DNCMRD-4A IWIEXAM B03-02 SIL289 71141 UT 19981002 R222 P

ExAas PERFORhsED BY GE peUCLEAR ENERGY RPV CS-DNCMRD 4B IWIEXAM B0342 SE289 71141 UT 19981002 R222 P

EXAss PERFORheED BY GE NUCt EAR ENERGY RPV CS-DNCMRD4C IWI EXAM B03-02 Sil.289 71141 UT 19981002 R222 P

EXAas PERFORadED BY GE NUCLEAR E HERGY 12/I7/98 Page 7ef 9

EXAM LEQUI!EMENI'S 301-32 OWNER: TENNESSEE VAI LEY AUTHORITY PLANT: BROWNS FERRY NUCLEAR FLANT 88242 NUC1. EAR FOWER GROtt P.O. BOX 2006 2

8I91 MARKETS 1REET DECATUR. AIABAMA 3%42 B6442 M2 CHATTANOOGA. TENNESSEE 37402 CERTIFICATION OF AlmlORIZATION: NOT REQUIRED UNIT:1HREE CYCLE:8 COMMERCIAL SERYlCE DATE: MARCll I,1977 NATIONAL DOARD NUMBER FOR UNIT: NOT REQUIRED y

3 System Corrponere ISO Droming Exam Caengary Bom Emam Cantwamon Exam Exam Enem Commonas NurWber Requeement Number Sd= w Senneerd Does Report Reeies RPV CSONCMRD4D IWI EXAM B03-02 SIL289 71141 UT 19961002 R222 P

EXAM PERFORMED 8Y GE NUCLEAR ENERGY RPV CS-DNCMRD-5 IWI EXAM B0342 Sil.289 71141 UT 19981002 R222 P

EXAM PERFORMED BY GE NUCLENt ENERGY RPV CS-DNCMRD-6 IWIEXAM 80342 SR289 71141 UT 19981002 R222 P

EXAM PERFORMED BY GE NUCLEAR ENERGY RPV C67 IWI EXAM B03-02 SR289 71141 UT 19981002 R222 P

EXAM PERFORMED BY GE NUCLEAR ENERGY RPV CS-DNCMRD4A NVI EXAM B0342 SIL289 71141 UT 19961002 R222 P

EXAM PERFORMCD BY GE NUCLEAR ENERGY RPV CS-DNCMRD-8B NV1 EXAM B0342 SIL289 71141-UT 19961002 R222 P

EXAM PERFORMED BY GE MUCLEAR ENERGY RPV N1 A-SE ISS-0328-C 01 B0242 C

NUO313 UT BF-107 19961002 R153 P

RPV N1 A-SE ISI-0328-C 01 B02-02 C

NUO313 UT BF-90 19961002 R153 P

RPV NIB-SE ISI-0328-C 02 B0242 C

NUO313 UT BF-107 19961002 R154 P

RPV NIB-SE ISI-0328-C 02 802-02 C

NUO313 UT BF-90 19981002 R154 P

RPV N4A(NOZ BORE)

IS84327-C 01 B01-02 7112 NUO619 UT BF-93 19961000 R210 P

EXAM PERFORMED BY GE NUCLEAR ENERGY RPV N4A-IR ISI-0327-C 01 B0142 7112 NUO619 UT BF-18 19961009 R210 P

EXAM PERFORMED BY GE NUCLEAR ENERGY RPV N4B(NOZ BORE)

ISl-0327-C 01 B01-02 7112 NUO619 UT BF-93 19981009 R211A P

EXAM PERFORMED BY GE NUCLEAR ENERGY RPV N484R IS84327-C 01 80142 7112 NUO619 UT BF-18 19961000 R211A P

EXAM PERFORMED 8Y GE NUCLEAR ENERGY RPV N4C(NOZ BORE)

ISI-0327-C 01 B01-02 7112 NUO619 UT BF-93 19961009 R212A P

EXAM PERFORMED BY GE NUCLEAR ENERGY RPV N4C-IR IS14327-C 01 B01-02 7112 NUO619 UT BF-18 19981009 R212A P

EXAM PERFORMED BY GE NUCLEAR ENERGY RPV N4D(NOZ BORE)

ISI-0327-C 01 801-02 7112 NUO619 UT BF-93 19961009 R213 P

EXAM PERFORMED BY GE NUCLEAR ENERGY RPV N4D-lR ISI-0327-C 01 B0142 7112 NUO619 UT BF-18 19961009 R213 P

EXAM PERFORMED BY GE NUCLEAR ENERGY RPV N4E(NOZ BORE)

ISl4327-C 01 B01-02 7112 NUO619 UT BF-93 19961009 R214 P

EXAM PERFORMED BY GE NUCLEAR ENERGY RPV N4E-IR IS84327-C 01 B01-02 7112 NUO619 UT BF-18 19981009 R214 P

EXAM PERFORMED BY GE NUCLEAR E NLRGY RPV N4F(NOZ BORE)

ISl4327-C 01 B0142 7112 NUO619 UT BF-93 19981009 R215 P

EXAM PERFORMED BY GE NUCLEAR ENLRGY RPV N4F-IR ISl4)327-C 01 B01-02 7112 NUO619 UT BF-18 19981009 R215 P

EXAM PERFORMED BY GE NUCLEAR ENLRGY I2/I7/98 Page 8 of 9

.___m EXAM CEQUIREMENIS 30842 OWNER: 1ENNESSEE VA11EY AUIIlORITY PLANT: httOWNS FERRY Nt< LEAR PLANT 30242 NOCLEAR POWER GROUP P.O. DOX 2000 M2 IISI MAREET STREET DECATUR. A1ABAMA 3%82 90442 M2 CHA1TANOOGA, TENNESSEE 37402 CERTIFICATION OF AUTilORIZATION-NOT REQUIRED UNIT:THIPTE CYCLE:0 COMMERCIAL SERVKE DATE: MARCH I,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED 3

Syeamm C

ISO Dramaig Exam Casmenry tem Enam Cameramon Emam Emam Enam Coneneres Nummer Reemromere sesmeer sdienses saaneens Date Repara Reeuen RWCU 3RWCU49 ISl4333-C 0t 80242 C

NUO313 UT BF41 19900927 R076 P

RWCU RWCU-3401-042 IS84332 4 01 P0742 B-J 89.11 PT 19900930 R062 P

SEE ALSO REPORT ROTT (PASSED)

RWCU RWCU-3401-042 IS84332-C 01 P07-02 B4 BG.11 UT BF-31 19961001 R007 P

RWCU RWCU-3-001-043 IS84332-C 01 P0742 B4 89.11 PT 19900927 R043 P

RWCU RWCU-3401443 ISl4332-C 01 P07-02 BJ 89.11 UT BF-31 19961003 R101 P

RWCU RWCU-3401-044 IS84332 4 01 P0742 BJ 89.11 PT 19981002 R090 P

SEE ALSO REPORT N000 RWCU RWCU-3401-044 IS84332-C 01 P0742 BJ 89.11 UT BF-31 19981003 R102 P

RWCU RWCU-3-001-066 ISI-0332-C 01 P0742 B4 89.11 PT 19961001 R060 P

RWCU RWCU4401-066 IS84332-C 01 P0742 B-J 89.11 UT BF-31 19961004 R100 P

i 12/17/98 rege f ef f

- - ~ ----- -

OWNER: TENNESSEE VALLEY AUIRORJTY PLANT. BROWNS FERRY NUCLEAR PL ANT OFFICE OF NUCLEAR POWER PO BOX 2000 l

1101 MARKET STREET DECARJR, ALABAMA 35602 l

l CHATTANOOGA, TENNESSEE 37402 UNIT THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED 4

COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UhlT: NOT REQUIRED.

AUGMENTED EXAMINATION

SUMMARY

This section includes information of the augmented examinations performed to comply with NRC or TVA self imposed requirements. Typical sources include generic letters, IE Bulletins, Technical Requirement, vendor reco===Ma' ions (GE Site Information Letter, SIL's), and tndustry experience. The following summanzes the augmented examinations performed during Cycle 8 and references the corresponding paragraph in 3 SI-4.6.G.

PARAGRAPH 7.11.1; FEEDWATER NOZZLES Surveillance Instruction 3-SI4.6.G requires that the feedwater nozzle safe end, bores, and inside blend radii be UT ernminM every second refueling outage. Additionally, to satisfy BFPER960265, feedwater nozzle N4E shall receive an ultrasonic examination

Reference:

NRC NUREG-0619 Exanunation Results: The UT ernminations revealed no relevant indications.

PARAGRAPH 7.11.2; CRD RETURN LINE REROUTE Surveillance Instruction 3-SI4.6.0 reqmres that the welded connections joining the rerouted CRD return line to the reactor water cleanup system be UT ernmind for three consecutiv: refueling outages. Also, welds RCRDS-343 and RCRD-344 be UT ersmind along with the pipe on the downstream side. These examinations were to be alimina M after cycle 7. However, at the izquest of Component Engineering the welds and prescribed areas were ernmind again in cycle 8.

Reference:

NRCNUREG-0619 Examination Results: The UT ernminatians revealed no relevant indications.

PARAGRAPH 7.11.3; AUGMENTED EXAMINATION OF AUSTENITIC STAINLESS STEEL AND DISSIMILAR METAL WELDS SUSCEPTIBLE TO IGSCC (GENERIC LETTER 88-01 AND NUREG-0313, REVISION 2)

Surveillance Instruction 3-SI4.6.G requires that the austenitic stainless steel and dissimilar metal ciic-m'eistial welds in piping four inches or larger in nominal pipe diameter which contain reactor coolant at te+.

n above 200 degrees F during power operation be volumetric exanuned.

Reference:

Generic Letter 88 01 and NUREG-0313, rev.2

OWNER. TENNESSEE VALLEY AUIRORITY PLANT. BROWNS FERRY NL' CLEAR PLAST OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATLR, ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT:

THREE CERTIFICATE OF AUTHOPJZATION: NOT REQUIRED.

COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNTT: NOT REQUIRED.

NUREG-0313 TOTAL NUMBER WELDS EXAMLNED CATEGORY OF WELDS DURING U3/C8 Ontmoe A

71 N/A B

N/A N/A C

80 80 D

1 2

E 9

1 F

N/A N/A G

2 2 (VT 2)

Exammation Results: One new indication indicative of IGSCC was detected. The flaw is located in RECIRC weld GR-3-63 which is the downstream weld joining valve 3-FCV 068-077 to 28 inch stainless steel rectreulation system suction piping for the loop B rectreulation pump. The UT results indicated the IGSCC is located at approximately 140-degree azimuth or 35-inches clockwise from top-dead-center. The flaw is 1.7-inches in length with a through-wall dimension of 0.2-inch. The results of the analytical evaluation demonstrate that weld GR-3 63 is acceptable for a mininmm of three additional fuel cycles.

The weld was reclassified as IGSCC Category E.

PARAGRAPH 7.11.4.1 CORE SPRAY PIPING AND SPARGERS Surveinsnem Instruction 3-SI-4.6.G requires an ultrasonic enmination of the associated piping included the P4a, P4b, P4c, P4d, PS, P6, P7, P8a, and P8b weldments of Core Spray dum.orner lines A, B, and D.

P4a, and P4b on line C.

Dowicomer Elbow er==nnatians:

The examinations were perfortned as a one sided ernmination from the piping side of the configuration using 60' and 70' shear wave technique. No reportable indications were identified during the enminations.

Welds AP4a, BP4a, CP4a, and DP4a were limited in examination coverage due to scanner interference with the RPV wall.

Downcomwer Sleeve Fnmination:

Welds P5, P6, and P7 are welds nsaacintad with the coupler sleeve configuration of each downcomer piping run. The enminations were performed from both sides of each weld within this configuration using 60' and 70' sheer wave technique. No reportable indications were identified during the ernminatiana Shroud Collar Ma%

e The downcomer piping from the lower elbow is connected to the sparger piping T Box which is Q

located inade the core shrood. This is accomplished by welds P44 (elbow weld to shroud pipe) and U

hidden weld P9 (shroud pipe to sparger T-Box). The shroud pipe is also connected to a collar

(

assembly (P8a) which attnehas the configuration to the shroud OD (P8b).

The ernminations were performed as a one sided examination from the piping side of the configuration using 60' and 70' shear wave technique. No reportable indic=tions were identified.

Some of the examinations were supplemented with the IVVI.

Reference:

SIL-289 Exammation Results: The ultrasonic examinations identified no reportable relevant indications.

OWNER: TENNESSEE V/I" ' O iTHORITY PLANT. BRO %HS FERAY NUCLEAR PLANT OFFICE OF NUCLL + i. '.TR PO BOX 2000 1101 MARKET STREEi DECATLP., ALABAMA 35602 CHATfANOOGA, TEN 1EnEE 37402 UNIT.

THREE CERTIFICATE OF AUTHORIZATYON: NOT REQUIRED.

COMMERCIAL SERVICE DATE: 4 RCH 1,1977 NATIONAL BOARD NUMBER FO.} UNIT: NOT REQUIRED 1

PARAGRAPH 7.11.4.2 CORF EPRO N'ARGER INDICATIONS l

Suiveillance Instruction 3-S1-4 6.G eqa tnat the four indications which were identiSed during the IVVI of cycle 5B be monitored. The re S 4 af cycle 8 examinations of the four indications on the core spray spargen are to be comparco to %,.nuiu from cycle 7. Any changes shall receive an engineenng review.

Reference:

LEBulletin 80-13 Examination Results: The indication located at Core Spray Header T-Box @ 120*, left side weld base material shows no discernible change. The indication located at Core Spray T-Box @ 240', left side weld shows no discernible change. The two indications loc ed at the Core Spray Downcomer Elbow at 325.5*

revealed the following: These two indications do not appear to be as "present" as they were when first detected. The general area of these indications is physically abused by various inspection / cleaning tooling transiting the area. For example the brushing equip: ent when going on the bottom side of the elbow to shroud weld may cause scratches or apparent gouges ca the elbo" d". ring inspection or removal. Also, this outage the Access Hole Covers were VT and UT ex:.mmed wn.ch createt :nore opportunities'for poles, cameras and scanners to scratch or scar the.iW. R was the opinion of the examiners that these two l

indications be closed out as non-relevant, PARAGRAPH 7.11.4.3 CORE SPRAY T-iM ",' ELDS M!.,-289 Surveillance Instruction 3-SI 4.6.G requires a visual examination of the Core Spray T-Box front cover plate weld and the Core Spray T Box to thermal sleeve weld joint per the recommendations of SIL 289

Reference:

G.E. Sile289 Examination Results: The cycle 8 enmmarion resulu revealev. na relevant indications.

PARAGRAPH 7.11.4.9 JET PUMP RISER BRACES SIL.551 Surveillance Instruction 3 SI-4.6.G requires a visual enmmation of Rise / Braces oflet Pump Numbers 11 through 20 per the recommendatians of SIL 551.

Reference:

GESils531 Enmmation Results: The enmmatino revealed no relevant indications PARAGRAPH 7.11.4.10 JET PUMP RISER BRACE CLAMP Surveillana Instruction 3 SI-4.6.G requires a visual examtnation of de jet Pump Riser Brace Arm welds l

forjet pump pairs 5,6,14,15, and 16.

1

Reference:

BWRVIP-41 i

Examination Results: The exammation revealed no relevant irnications.

1

l l

j OWNER: TENNESSEE VALLEY AUTHOluTY PLANT: BROWNS FERRY NUCLEAR PLANT OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR. ALABAMA 35602 CHATTANOOGA, TENNESSEE 37402 UNIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED.

l COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED PARAGRAPH 7.11.4.12 TOP GUIDE SIL-S54 l

l Surveillance Instruction 3-SI 4.6.G requaes a visual examination of the Top Guide Beams per the l

recon mendarians of SIL-554.

Reference:

GESIL-534 j

Exammarion Results: The examination revealed no relevant indications.

PARAGRAPH 7.11.4.14 STEAM DRYER DRAIN CHANNEL WELDS Surveillance Instruction 3-SI-4.6.G requaes a vissal exanunation of selected Steam Dryer Drain Channel l

Steam Dryer Drain Channel Number twas exami:1ed during cycle 8.

Reference:

GE Letter BFSE 94-002 dated !!%W Exammarion Results: The eraminatian :evealed no relevant indications.

PARAGRAPH 7.11.4.16 TOP GUIDE AND CORE PLATE BOLTING EXAMINATION SIL-588 Surveillance Instruction 3-SI 4.6.G reqmres a visual exanunation of the Top Guide Alignment Pins and Core Plate Bolting per SIL-588 and BRWVIP 25.

Reference:

GESIL-588 and BWRVIP 25 Examinatian Results: The====m'ian revealed no relevant indications.

PARAGRAPH 7.11.5 WELD INSPECTION FOR PIPE WHIP PROTECTION Surveillance Instruction 3-SI 4.6.G reqmres selected cucumferential pipe welds received a surface and i

volumetnc mminarian to prtmde additional protection agamst pipe whip in accordance with TSR 3.4.3.2. A total of nine welda rocerved a surface and volumetric cramination dunng cycle 8.

Reference:

%nnical Seveillance Requirements Examination Results: The====m'ian revealed no evidence of" pipe-whip" l

l r

f l

OWNER: TENNESSEE VALLEY AlmiORITY PLANT. BRO %HS FERRY NYCLEAR PLAST i

OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35602 CHATTANOOGA, ~1TNNESSEE 37402 1' NIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT NOT REQUIRED 1

ATTACHMENT 3 9

4 i

l

l l

l l

l i

i CU.'.?ECTED EXAMINATION DATA FOR BFN UNIT 3 RPV EXAMINATION FROM THE INSIDE SURFACE CONDUCTED DURING CYCLE 5 OPERATION (1993) - SEE ENCLOSURE 3 OF THIS LETTER i

OWNER: TENNESSEE VALLEY AUIRORITY PLANT: BROWNS FERRY NUCLEAR PLA.VT OFFICE OF NUCLEAR POWER PO BOX 2000 1101 MARKET STREET DECATUR, ALABAMA 35603 CHATTANOOGA, TENNESSEE 37402 l

UNIT:

THREE CERTIFICATE OF AUTHORIZATION: NOT REQUIRED COMMERCIAL SERVICE DATE: MARCH 1,1977 NATIONAL BOARD NUMBER FOR UNIT: NOT REQUIRED l

l ATTACHMENT 4 O

l l

l t

P TENNESSEE VALLEY AUTHORITY m,,,

imew BROWNS FERRY NUCLEAR POWER PLANT - UNIT 3

" " " ~

EXAMS SCHEDULED FOR CYCLE 08 SYSTEM WELDNO ISONO CYCLE ITEMNO CATEGORY EXREQ EXSCHD NDErftOC CALSID COMPtXA NOMulCK COMFDESA COMPDESB CRDS RCRD 3-33 1844 332 4 02 08 MUO313 C

B0242 UT N-UT44 BF-76 04.00 PC.SE PC. CAP t

CRDS RCRIM-33 IS84332-C 02 00 NUO313 C

B0242 UT N4JT44 BF40 04.00 PC.SE PC. CAP CRDS RCRD-3 44 1854 332 4 02 08 V0141 7112 80142 UT N-UT-18 BF41 04 00 PC. RED PC. PIPE i.

CRDS RCRE 345 IS84332-C 02 08 V01-01 7112 801-02 UT N4JT-18 BF-29 04.00 PC. PIPE PC. RED CRDS RCRD-3-40 IS14332-C 02 08 NUD313 C

B0242 UT N-UT44 BF-29 04.00 PC.VLV PE.EL i

C CRDS RCRD-340 IS84332 C 02 08 NUD313 C

B0242 UT N-UT44 BF-29 04.00 PE.EL PC.WV l

CRDS RCRD,3-52 IS84332-C 02 08 NUO313 C

B0242 UT N4JT44 BF-29 04.00 PC.VLV PC. PIPE j

f CRDS RCRDS-343 IS84332-C 02 08 V01-01 7112 80142 UT M4JT-18 BF-35 08.00 PBCC.TR PC. RED CSS DCS-3-04 IS84331-C 01 08 NUO313 C

B0242 UT M4JT44 BF-79 12.00 0.600 PP. PIPE PC. PIPE f

CSS DCS-345 IS84331 4 01 08 NUO313 C

B0242 UT N-UT44 BF-79 12.00 0.608 PC, PIPE PC VLV CSS DCS-3-05 IS84331-C 01 00 NUO313 C

80242 UT N4JT40 BF-79 12.00 0 000 PC. PIPE PC VLV CSS DCS-3-13 IS14331 4 01 08 NUO313 C

B0242 UT N-UT44 BF-79 12.00 0.000 PP PIPE PC. PIPE I

CSS DCS-3-14 IS4-0331-C 01 00 NUO313 C

B02-02 UT-N-UT44 BF-79 12.00 0.688 PC. PIPE PC.VLV i

CSS DCS-3-14 IS84331-C 01 08 NUO313 C

B02-02 UT N4JT48 BF-79 12.00 0.688 PC. PIPE PC.VLV i

l CSS DSCS-101 IS84331-C 01 00 NUO313 C

B0242 UT N4JT44 BF-79 12.00 0 880 PC. PIPE PE.EL

[

CSS DSCS-341 IS14331-C 01 08 NUO313 C

80242 UT M4fT48 BF-79 12.00 0 888 PC. PIPE PE.EL CSS DSCS-342 IS84331-C 01 08 NUO313 C

80242 UT M4JT44 BF-79 12.00 0 688 PE.EL PC PIPE CSS DSCS-342 IS84331-C 01 08 NUO313 C

B0242 UT N4JT40 BF-79 12.00 0 600 PE.EL PC. PIPE CSS DSCS-347 IS84331-C 01 08 NUO313 C

B0242 UT N-UT44 BF-79 12.00 0 688 PC, PIPE PE,EL CSS DSCS-347 8S84331-C 01 08 NUO313 C

80242 UT N4JT48 BF-79 12.00 0.688 PC. PIPE PE.EL CSS DSCS-108 IS84331-C 01 00 NUO313 C

B0242 UT N4JT44 BF-79 12.00 0 688 PE.EL PC. PIPE I

CSS DSCS-349 ISl4331-C 01 00 NUO313 C

B0242 UT N4JT44 BF-79 12.00 0 688 PC. PIPE PC. PIPE CSS FCV-75-54-BC ISl4331-C 01 08 B7.70 BLG-2 69E-02 VT-1 N-VT-1 BVAL i

SURTORDER:SESTEM-WELDNO Page I of Li i

s

l SYSTEM WELDNO ISONO CYCW ITEMNO CATEGORY EXREQ EXSCHD NDEPROC CALSTD COMPDIA NOMTIK'K COMPDESA COMPlutt f

CSS TCS-3-405 IS8-0331-C 01 08 NUO313 C

B0242 UT N-UT44 BF-75 12.00 0.888 PC.VLV PE. RED CSS TCS-3406 ISl4331-C 01 08 BO.11 84 80E42 PT N-PT-0 12.00 0 688 PE. RED PC,WV I

CSS TCS-H06 IS84331 C 01 08 B9.11 84 80E-02 UT N-UT44 BF-75 12.00 0 888 PE. RED PC.WV CSS TCS-3-406 IS84331-C 01 08 NUO313 C

80242 UT N-UT44 BF-75 12.00 0 688 PE. RED PC,WV CSS TCS-M10 ISl4331-C 01 08 NUO313 C

B0242 UT N-UT44 BF-75 12.00 0.688 PC.WV PE.EL I

CSS TCS-3-417 ISl4331 C 01 08 85.10 B-F 80E-02 PT N-PT-9 10.00 0.504 PC.SE SNOZCS r

CSS TCS-3417 IS84331-C 01 08 B5.10 Bf 80E42 UT N-UT44 BF45 10.00 0.504 PC.SE SNOZCS CSS TCS-3417 ISl4331 C 01 08 86.10 Bf 80E42 UT N-UT44 BF-106 10.00 0 504 PC.SE SNOZCS CSS TCS-3-417 IS84331-C 01 08 86.10 Bf 80E-02 UT IHIT48 BF45 10 00 0.504 PC.SE SNOZCS CSS TCS-3-417 ISI-0331-C 01 08 85.10 Bf 80E42 UT N-UT48 BF-106 10.00 0.504 PC.SE Sh0ZCS CSS TCS-3-421 IS84331-C 01 08 NUO313 C

80242 UT N-UT44 BF-75 12.00 0 688 PC.VLV PE. RED

[

CSS TCS-3422 IS14331-C 01 08 NUO313 C

80242 UT N-UT44 BF-75 12.00 0.848 PC. PIPE PC,WV CSS TCS-3428 IS84331-C 01 08 80.11 B4 80E42 PT N-PT-9 12.00 0 608 PC,VLV PE.EL CSS TCS-3-426 ISl4331-C 01 08 80.11 84 00E-02 UT N-UT44 BF-75 12.00 0 688 PC,WV PE.EL CSS TCS-3426 ISl4331-C 01 08 NUO313 C

80242 UT N-UT44 BF-75 12.00 0 688 PC WV PE.EL CSS TSCS-3-408 ISl4331-C 01 08 TS48G B4 80442 MT N-MT4 12.00 0.688 PC. PIPE PE.EL CSS TSCS-3-408 ISI-0331-C 01 08 TS46G B4 80442

-UT N-UT44 BF-75 12.00 0.688 PC. PIPE PE,EL t

CSS TSCS-3-418 ISl4331-C 01 08 80.11 84 80E-02 PT N-PT-9 10.00 0.504 PC. PIPE PC.SE f

CSS TSCS-3-418 ISl4331-C 01 08 80.11 84 80E42 UT N4fT-64 BF45 10.00 0.504 PC. PIPE PC.SE CSS TSCS-3-418 ISI-0331-C 01 08 B0.11 B4 00E42 UT N-UT44 BF-46 10.00 0.594 PC, PIPE PC.SE CSS TSCS-3-418 IS$4331-C 01 08 80.11 B4 80E42 UT N-UT48 BF-05 10.00 0.594 PC. PIPE PC.SE l

CSS TSCS-3-418 IS84331-C 01 08 BS 11 B4 80E-02 UT N4JT48 BF-46 10.00 0 594 PC. PIPE PC.SE l

l CSS TSCS-3-423 ISI-0331-C 01 08 TS46G B4 804-02 MT N-MT4 12 00 0 688 PC. PIPE PE.EL CSS TSCS-3-423 IS84331-C 01 08 TS46G B4 804-02 UT M4JT44 BF-75 12.00 0 688 PC. PIPE PE,EL l

FWS 3-470415-31HA ISl4336-C 01 08 B10.10 BK 80E-01 MT N-MT4 1.500 PllWA FWS 3J Til415-38 ISS-0336-C 01 08 F1.10C FA 89E 02 VT-3 N-VT-1 12.00 HCF2 SORTURDER: SYSTEM-WELDNO W 2 *S U i

[

SYSTEM WELDNO ISONO CYCLE IILMNO CATEGC3Y EXREQ EXSCIID NDEPROC CAISTD COMPDIA NOMTHCK COMPDESA COMPDESS 7WS M78415-38-IA IS14336-C 01 08 B10.10 B-K-1 89E-02 MT NMT4 1.500 Pl M A FWS 3-478415-424A IS8433&C 01 08 B10.10 B-K-1 89E-02 MT N-MT4 1.500 Pl.lWA FWS 3-478415474A ISl4336-C 01 08 B10.10 BK-1 89E-02 MT N M T-6 1.500 Pl.lWA FWS 3-478415-584A IS8433&C 01 08 B10.10 B-K-1 89E42 MT NMT4 1.500 Pl.lWA FWS 3-478415404A IS$4336C 01 08 B10.10 BK-1 89E-02 MT MMT4 1.500 Pl,M A FWS GFW-3-12 IS84327 C 01 08 TS46G B.J B0442 MT NMT4 12.00 0.066 PBCC.TR PC, PIPE FWS GFW-3-12 ISl4327-C 01 08 TS46G BJ B04-02 UT N-bT-1R BF-75 12.00 0.515 PDCC.TR PC. PIPE FWS GFW-3-26 ISI-03274 01 08 TS46G B-J B0442 MT NMT4 12.00 0'44 PE.EL PE.EL FWS GFW-3-26 IS84327-C 01 08 TS46G B-J B04-02 UT N-UT-18 BF-75 12.00 0.566 PE.EL PE.EL FWS KFW-3-39 IS84327-C 01 08 TS46G B4 B0442 MT N-MT4 12.00 0.568 PE.EL PE.EL FWS KFW-3-39 IS84327 4 01 08 TS46G B-J B04-02 UT N-UT-18 BF-75 12.00 0.566 PE EL PE,EL HPCIS 3-478455426 Cme-2413C O2 08 F1.20C F-A P07-02 VT-1 N-VT-1 10 00 HVS KPCIS HPCI-341H09 CM2407-C 02 08 C5.51 C-F P0742 MT N-MT4 HPCIS HPCI-3-019-009 CHM-2407-C 02 08 C5.51 C-F P07-02 UT N-UT 18 BF-42 KPCIS HPCI-3-019-010 CM2407-C 02 08 C5.51 C-F-2 P07-02 MT N-MT4 10.00 PC. PIPE PC.EV HPCIS HPCI-3-019410 CHM-2407-C 02 08 C5.51 C-f%.

P07-02 UT N-UT-18 BF-42 10.00 PC. PIPE PC VLV KPCIS HPCI-3-019 011 CHM-1407-C 02 08 C5.51 C-F P07-02 MT N-MT4 KPCIS HPCI-3419-011 CHM-2407-C 02 08 C5.51 C-F P07-02 UT N4JT-18 BF-42 KPCIS THPCI-3-070 IS4-0333C 01 08 TS46G B4 B04-02 MT NET 4 10 00 0 593 PE.EL PC. PIPE HPCIS THPCI-3-070 IS843334 01 08 TS46G B-J B04-02 UT N4JT 18 BF-05 10.00 0 593 PE.EL PC. PIPE MSS 3-47B4004814A IS14355-C 01 08 C3.20 C-C 89E-02 MT NMT4 Pl.fWA MSS M78400 083 ISl4338-C 01 08 F1.10C FA 89E-02 VT-3 N-VT-1 26.00 HCF MSS 3 47B400-0834A ISS-03384 01 08 B10.10 B-K-1 89E-02 MT N-MT4 0.500 Pl.lWA MSS 3-478400-1144A ISI-03384 02 08 B10.10 B-K-1 89E-02 MT NET 4 1.625 Pl.lWA MSS DMS-3-29 ISI-0354-C 01 08 C581 C-F-2 89E-02 MT N-MT4 18 00 0 938 PC.PlPE PBC,SWP MSS FCV-1427-BC IS14329-C 02 08 BT.70 B-G-2 89E-02 VT-1 N-VT-1 BVAL SORTORDER: SYSTEM-HELDNO Pate 3 of13

l SYSTEM WELDNO ISONO CYCLE ITEMNO CATEGORY EXREQ EXSCHD NDEPROC CAIJSTD COMPDIA NOMlHCK COMPDESA COMPDESB MSS FCV-1437 IS84329-C 02 08 B12.50 BM-2 80E-02 VT-3 N-VI-1 26.00 AVAllNT MSS GMS-3-15 BS8-0329C 02 08 TS46G BJ B04-02 MT NMT4 26.00 0.950 PE.EL PBCC.T MSS GMS-3-15 IS84329-C 02 08 TS46G B-J B04-02 UT N-UT-18 BF-104 26.00 0 950 PE.EL PBCC.T MSS GMS-3-32 IS6432SC 01 08 TS46G B.J B0442 MT NMT4 26.00 0.950 PE.EL PE.EL MSS GMS-3-32 IS8432SC 01 08 TS46G BJ B0442 UT N4JT-18 BF-104 26.00 0 950 PE.EL PE.EL MSS HPAS-3-H-02 IS84356 4 02 08 F1.20C F-A P07-02 VT-3 N-VT-1 06.00 HVS i

MSS HPAS-34643 IS84356C O2 08 F1.20C F-A 80E42 VT-3 N-VT-1 06.00 HVS MSS HPAS4+447 IS84366-C 02 08 F1.20C FA P0742 VT-3 N-VT-1 06.00 HVS MSS HPAS-3-H-10 IS8436SC 02 08 F1.20C F-A 80E42 VT-3 N-VT-1 06.00 HVS l

MSS KMS-3-114 IS64329 4 02 08 80.11 B4 80E42 MT NMT4 26.00 0.950 PC.FH MSS KMS-3-114 IS14329-C 02 08 BO.11 BJ 80E42 UT M4JT-18 BF-104 26.00 0.950 PC.FH MSS MS4-H49 ISI-0365C 01 08 F1.20C F-A 80E-02 VT-3 N-VT-1 24.00 HVS MSS MS-3-H-12 ISS-0365-C 01 08 F1.20C F4 80E-02 VT-3 N-VT-1 24.00 HVS MSS MS-341-13 IS84356-C 01 08 F1.20C F-A 80E42 VT-3 N-VT-1 24.00 HVS MSS MS-3-N-1MA IS84355-C 01 08 C3.20 CC 80E-02 MT NMT4 Pl.RMA MSS MS-341-15-IA ISI-0365-C 01 08 C3.20 C-C 80E42 MT NMT4 Pl.lWA

{

MSS MS-3-H-16-4A ISI-0355 C 01 08 C3 20 C-C 80E42 MT NMT4 Pt.lWA f

MSS MS-341-17 1584356 4 01 08 F1.20C F-A 80E42 VT-3 N-VT-1 30.00 HVS i

MSS

'?CV1-3404-PBC BS843134 01 08 BT.50 BG-2 80E-02 VT-1 N-VT-1 BVAL MSS PCV14-018 IS84313 4 01 08 B7.70 BG-2 80E-02 VT-3 N-VT-1 MSS PCV1-3418 IS843134 01 08 B12.50 84-2 80E42 VT-3 N-VT-1 MSS PCV1-3418-PBC IS84313-B 01 08 B7.50 B G-2 80E42 VT-1 N-VT-1 BVAL t

MSS PCV14418-PBC IS84313 4 01 08 B7.50 BG-2 P07-02 VT-3 N-VT-1 BVAL MSS PCV1-3418-VBC IS8-0313-8 01 08 B7.70 BG-2 89E42 VT-1 N-VT-1 BVAL l

MSS PCV1-3434-PBC 1S843134 01 08 B7.50 BG-2 80E42 VT-1 N-VT-1 BVAL MSS PCV1-3434-VBC ISI-0313-B 01 08 B7.70 B-G-2 80E42 VT-1 N-VT-1 BVAL l

l SORTORDER: SYSTEM-WELDNO

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I

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1 SYSTEM WELDNO ISONO CYCLE ITEMNO CA.GOORY EXREQ EXSCHD NDEPROC CALSTD COMFDBA NOMT1KK COMPDESA COMPDLSB MSS PCV13442-PBC ISS-0313-8 01 08 B7.50 BG-2 SEE42 VT-1 N-VT-1 BVAL MSS PCV1-3442-VBC IS84313 4 01 08 B7.70 EG-2 80E42 VT-1 N-VT-1 BVAL MSS PCV1-3-1794C IS84313-8 01 08 B7.70 B-G-2 P07-02 VT-3 N-VT-1 BVAL MSS PCV1-3-171WBC IS$43134 01 08 B7.50 BG2 P07-02 VT-1 N-VT-1 BVAL MSS PCV1-3-179-VBC IS64313 4 01 08 B7.50 84-2 P07-02 VT-1 N-VT-1 BVAL RECIR M78465-2048 IS84337 C 01 08 F1.10C F-A V0142 VT-1 N-VT-1 RECR M78465497 ISHl337-C 02 08 F1.40D F-A SSE42 VT-3 N-VT-1 Sees RECIR 3-478465-498 IS84337 C 02 08 F1.400 F-A 80E42 VT-3 N-VT-1 tees RECR 347846H99 ISHl3374 02 08 F1.40D F4 80E42 VT-3 N-VT-1 HMS j

RECE 3478465-500 IS$4337402 08 F1.10C FA SSE42 VT-3 N-VT-1 HCF I

RECR 3-478485-501 IS14337-C 02 08 F1.10C F4 80E42 VT-3 N-VT-1 HCF i

l RECR 3-478465-502 IS84337-C 02 08 F1.10C FA 80E42 VT3 N-VT-1 HCF RECR 3-478465-503.

IS84337-C 02 08 F1.10D F-A 80E42 VT-3 N-VT-1 HMS RECR GR-341 ISl4320-C 01 08 NU0313 C

B0242 UT N-UT44 BF-57 28.00 PC. PUMP PC.PtPE

[

RECR GR-341 IS84326 4 01 08 NUO313 C

B02-02 UT N-UT48 BF-57 28.00 PC. PUMP PC.Pn'E RECE GR-342 IS84328-C 01 08 NUO313 C

B0242 UT N-UT-64 BF-57 28.00 PC. PIPE PC.VLV RECR GR-342 IS84328 C 01 08 NUO313 C

B0242 UT NUT 48 BF-57 28.00 PC.PtPE PC,VLV RECR GR-344 IS84328 C 01 08 NUO313 C

B0242 UT IHJT44 BF42 04.00 0.337 PBC,A PC. CAP f

f RECR GR-3-07 IS8432&C 01 08 NUO313 C

B0242 UT N-UT44 BF-02 04 00 0.*,37 PBC.A PC. CAP RECR GR-3-28 IS8432&C 02 OS NUO313 C

B02-02 UT N-UT44 BF-57 28.00 PC. PIPE PC VLV I

RECR GR->2s IS84326-C 02 Os NuG313 C

80242 uT NUT 48 er4T 28 2 PC. PIPE PC.VLV RECIR GR-3-29 IS84328-C 02 08 NUO313 C

B0242 UT N-UT44 BF-57 28.00 PC,VLV PE.EL RECR GR-3-29 IS84328-C 02 08 NUO313 C

802-02 UT NET 48 BF-57 28 00 PC,ti.V PE.EL RECE GR-3-30 IS84328-C 02 08 NUO313 C

802-02 UT NUT 44 BF-02 0400 0 337 PPO.A PC. CAP RECE GR-3-33 ISI-0328-C 02 08 NUO313 C

B02-02 UT NET 44 BF-02 04 00 0 337 P8C.A PC. CAP RECIR GR-3-55 IS8-0328 4 01 08 NUO313 C

BM-02 UT N-VT44 BF-57 28 00 PC. PIPE PBCC.TR

[

L SORTORDER: SYSTEM-WELDNO

?^V5 *f El i

i

r SYSTEM WELDNO ISONO CYCLE IILMNO CATEGORY EXREQ EXSCHD NDEPROC CALSTU COMPDIA NOMTitCK COMPDESA Ct*f7DESB RECR GR-3-55 IS84328-C 01 08 NUO313 C

B02-02 UT N-UT-68 BF-57 28 00 PC PIPE PBCC.TR RECR GR-3-58 ISI-03284 01 08 NUO313 C

B02-02 UT N-UT44 BF-57 28.00 PE.Es.

PC.WV RECR GR-3-58 ISI-032&C 01 08 NUO313 C

80242 UT N-UT48 SF-57 28 00 PE.EL PC.VLV RECR GR-3-58 IS84328 4 01 08 NUO313 C

80242 UT N-UT44 BF-57 28.00 PE.EL PC. PUMP RECR GR-3-58 IS84328-C 01 08 NUO313 C

B0242 UT N-UT48 BF-57 28.00 PE.EL PC. PUMP RECE GR-3-50(OL)

IS84328-C 02 08 NUO313 E

80242 UT N-UI48 SF43 28.00 PC.OVLY

[

RECR GR-341 IS$43284 02 08 NUO313 C

B0242 UT NET 44 BF-57 28.00 PC. PIPE PC. PIPE RECR GR-341 IS84328 4 02 08 NUO313 C

B0242 UT N-UT48 BF-57 28.00 PC. PIPE PO.PaPE i

RECR GR-342 IS84328 4 02 08 B9.11 BJ 88E42 PT N-PT-9 28.00 PE.EL PC vtV RECR GR-342 IS8432&C 02 08 80.11 B4 88E-02 UT sv4T44 BF-57 28.00 PE.EL PC.WV RECR GR-342 IS84328 4 02 08 80.11 B,J 88E-02 UT

• • lT48 BF-57 20.00 PE.EL PC.WV a

RECR GR-342 IS84326 4 02 08 NUO313 C

80242 UT N-UT44 BF-57 28.00 PE.EL PC,WV t

RECR GR-342 ISl4328-C 02 08 NUO313 C

B0242 UT N-UT48 BF-57 18.00 PE.EL PC.WV RECE GR-343 IS64328-C 02 08 NUO313 C

B02-02 UT NET 44 BF-57

?8.00 it.VLV PC alPE RECR GR-343 IS8432&C 02 08 NUO313 C

B0242 UT IMIT48 BF-57 28.00 PC.WV PCJ'*E RECR GR-343A IS84328 4 02 08 NUO313 C

B0242 UT N-UT44 BF-50 04.00 0.337 PBCA PC. CAP RECR GR-3438 IS84328 4 02 08 NUO313 C

B02-02 UT N-UT44 BF-59 04.00 0 3.M PC. PIPE PBC.A RECR KR441 IS84328-C 01 08 NUO313 C

B0242 UT N-UT44 BF-59 PC. PIPE PBC.A i

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RECR KR-342 IS84328 4 01 08 NUO313 C

B0242 UT NUT 44 BF-57 28.00 PE.EL PC. PIPE RECR KR-3-02 IS84328 4 01 08 NUO313 C

B02-u2 UT IMIT48 BF-57 28.00 PE.EL PC, PIPE I

RECR Kit-3-04 ISI-0328-C 01 08 NUO313 C

B02-02 UT NET 44 BF-59 PC. PIPE PBCA RECE KR-3-23 ISS-0328-C 02 08 NUO313 C

90242 UT N-UT44 BF-59 PC. PIPE PBC.A RECR KR-3-24 ISS-03284 02 08 NUO313 C

B0242 UT NUT 44 BF-57 28.00 PE.EL PC. PIPE RECIR KR-3-24 IS84328 4 02 08 NUO313 C

B02-02 UT N-UT48 BF-57 2800 PE.EL PC. PIPE RECIR KR-3-26 1S8-0326 4 02 08 NUO313 C

B02-02 UT N-UT44 BF-59 PC. PIPE PBC.A

{

RECIR KR-3-45 IS84328 4 01 08 NUO313 C

B02 02 UT N-UT44 eF-57 28 00 eC.eee ee.Et 1

i SURTORDER: SYSTEM-WELDNO M' ' */ IA l

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SYSTEM WELDNO ISONO CYCLE ITEMNO CATEC3ClY EXREQ EXSCliD NDEPROC CALSlD COMPDIA NOMTHCK COMPDESA COMPDLSI!

RECE KR-345 1584328 4 01 06 NUO313 C

B0242 UT N-UT48 BF47 28.00 PC. PIPE PE.EL RECR KR-3-48 IS84328 4 01 08 NUO313 C

B0242 UT N-UT44 BF-57 28.00 PBCC.TR PC. PIPE RECE KR-348 ISl4328401 08 NUO313 C

80242 UT N4JT48 BF-57 28.00 PBCC,TR PC. PIPE RECR KR-347 1S84328 4 01 08 NUO313 C

B0242 UT N-UT44 BF-57 28 00 PC. PIPE PE,EL RECR KR-3-47 IS84328-C 01 08 NUO313 C

B0242 UT N4JT48 BF-57 28.00 PC PIPE PE.EL RECR KR-348 IS84328 4 01 08 NUO313 C

B0242 UT N4JT44 BF47 28.00 PC PIPE PE EL RECR KR-3-48 ISl432&C 01 08 NUO313 C

B02-02 UT N4JT48 BF-57 28.00 PC. PIPE PE.EL RECR KR-3-49 ISO-0328-C 01 08 NUO313 C

80242 UT N-UT44 BF-59 04.00 0.337 PC. PIPE PBCA RECR KR-3-50 IS84328 4 02 08 NUO313 C

B0242 UT N-UT44 BF-57 28.00 PC. PIPE PE EL RECE KR-3-50 IS8-0328-C 02 08 NUO313 C

B02-02 UT N4JT48 BF-57 28.00 PC PtPE PE.EL RECR KR-3-51 ISl43284 02 08 NUO313 C

B0242 UT N4JT44 BF-57 28.00 PC. PIPE PE EL RECE KR-3-51 IS84328-C 02 08 NUO313 C

80242 UT N-UT48 BF-57 28 00 PC.P1PE PE EL RECR KR-3-52 IS8-0328 4 02 08 NUO313 C

B0242 UT N-UT44 BF-57 28.00 PC. PIPE PE EL RECR KR-3-52 ISS-03284 02 08 NUO313 C

B0242 UT N4JT48 BF-57 28.00 PC.PtPE PE.EL RECE KR-343 IS84328-C 02 08 NUO313 C

B0242 UT M4JT44 BF-59 04.00 PC. PIPE PBCA RECR RWR-3417 004 IS84328-C 01 08 B9.20 Eh!

P07-02 PT N-PT4 RECR RWR-M17405 IS84328 4 01 08 89.20 thi P0742 PT N-PT4 RECE RWR-3417-007 1S84328 4 01 08 89.20 B-J P0742 PT MPT4 RECR RWR-3417-009 IS84328 C 01 08 89.20 B-J P07-02 PT N-PT4 RHRS 3478452-3179 IS84340 4 01 06 NA WA V0142 VT-1 AVI-1 RHRS DRHR-342 IS14393 4 10 08 C5.51 C-F-2 89E42 PT N-PT-9 24 00 1.531 PC, PIPE PC VLV RHRS DRHR-M2 1S8-0393 4 10 08 C5 51 C-F-2 89E42 UT N4JT44 BF-102 24.00 1.531 PC. PIPE PC,VLV RHRS DRHR-342 ISI-0393-C 10 08 C5.51 C-F-2 89E42 UT N4JT48 BF-102 24 00 1.531 PC. PIPE PC.VLV RHRS DRHR-3-02 ISl4393410 06 NUO313 C

B0242 UT N4JT44 BF-102 24.00 1.531 PC PIPE PC,VLV RHRS DRHR-3-02 151-0393 4 10 08 NUO313 C

B0242 UT N4JT48 BF-102 24 00 1.531 PC. PIPE PC,VLV RHRS DRHR-343 IS14330 4 01 08 NUO313 D

B02-02 UT N4JT44 BF-57 24 00 1.219 PC. PIPE PE.EL SORTORDER: SYSTEM-NELDNO W *$ U b

l SYSTEM WFLDNO ISONO CYCI.E ITEMNO CATEGORY EXREQ EXSCHD NDEPROC CALSTD COMPDIA NOh4THCK COMFDESA COMPDESB RHRS DRHR-3438 ISI-0330-C 01 08 NUO313 G

B0242 VT-2 N-VT-4 24 00 1.219 PC. PIPE PP. PIPE RHRS DRHR-3-04 IS84330-C 01 08 NUO313 C

B0242 UT N4JT44 BF-57 24.00 1.219 PP. PIPE PE.EL RHRS DRHR-3-05 IS84330-C 01 08 NUO313 C

B0242 UT N4JT44 BF-57 24.00 1.219 PE.EL PC VLV RHRS DRHR-348 IS84330 C 01 08 89.11 B-J 8eE42 UT N-UT44 BF-57 24.00 1.219 PC,VLV PC. PIPE RHRS DRHR-348 ISl4334C 01 08 89.11 B-J 80E42 UT N4fT48 BF-57 24.00 1.219 PC.WV PC. PIPE I

RHRS DRHR-348 ISI-0334C 01 08 NUO313 C

80242 UT ff t#144 BF-57 24.00 1.219 PC,VLV PC. PIPE RHRS DRHR-348 IS64330C 01 08 NUO313 C

B0242 UT N-UT48 BF-57 24.00 1.219 PC,VLV PC. PIPE RHRS DRHR-347 IS84330 C 01 08 NUO313 C

80242 UT N4fT44 BF-57 24.00 1.219 PE.EL PC.VLV RHRS DRHR-347 ISl433SC 01 08 NUO313 C

B02-02 UT N-UT48 BF 57 - 24 00 1.219 PE,EL PC,VLV RHRS DRM-3-11 IS64303-C 11 08 C5.11 C-F-1 80E42 PT N-PT-9 24.00 1.531 PC. PIPE PC.VLV RHRS DRHR-3-11 IS84303 C 11 08 C5.11 Cf-1 00E42 UT N4JT44 BF-102 24.00 1.531 PC. PIPE PC,VLV f

RHRS DRHR-3-11 IS84393-C 11 08 C5.11 Cf-1 80E42 UT N-UT48 BF-102 24.00 1.531 PC. PIPE PC.VLV RHRS DRHR-3-11 IS84303 C 11 08 NUO313 C

B0242 UT M4fT44 BF-102 24.00 1.531 PC. PIPE PC VLV RHRS DRHR-3-11 ISI-0303411 08 NUO313 C

80242 UT N4fT48 BF-102 24.00 1.531 PC. PIPE PC,VLV RHRS DRHR-3-12 IS84330-C 01 4e NUO313 0

Sa?M t/T N4JT44 BF-57 24.00 1.219 PC,WV PC. PIPE

[

RHRS DRHR-3-13 IS84334C 01 08 NUO313 C

B0242 ui N4fT44 BF-57 24.00 1.219 PP. PIPE PE.EL RHRS DRIM-3-138 ISl43304 01 08 NUO313 G

B0242 VT-2 N-VT-4 24.00 1.219 PC. PIPE PP. PIPE RHRS DRHR-3-14 ISI-0334C 01 08 80.11 B-J 80E42 PT N-PT-9 24.00 1.219 PE.EL PC.VLV I

L RHRS DRHR-3-14 IS84330C 01 08 B9.11 B4 00E-02 UT N4fT44 BF-57 24.00 1.219 PE.EL PC.VLV j

RHRS DRHR-3-14 ISl43304 01 08 NUO313 C

B0242 UT M4JT44 BF-57 24.00 1.219 PE.EL PC.VLV f

RHRS DesiR-3-15 ISI-0334C 01 08 NUO313 C

B0242 UT N-UT44 BF-57 24 00 1.219 PC,VLV PC. PIPE Ri %

DidiP.T-15 ISI-0330-C 01 08 NUO313 C

80242 U1 N41T48 BF-57 24.00 1.219 PC.VLV PC. PIPE f

RHRS DRHR-3-18 ISB-0333C 01 08 NUO313 C

B0242 UT N4JT44 BF-57 24 00 1.219 PE.EL PC VLV RHRS DRHR-3-16 IS84330-C 01 08 NUO313 C

B0242 UT N4JT48 BF-57 24 00 1.219 PE.EL PC.VLV I

RHRS DRHR-3-19 ISI-0330-C 01 08 NUO313 C

B0242 UT N4JT44 BF47 20.00 1.031 PE.EL PC. PIPE i

RHRS DRHR-3-21 IS84330-C 01 08 NUO313 C

B02-02 UT

'44JT44 BF-87 20 00 1 031 PE.EL PC.VLV j

i i

SURTORDER: SYSTEM-NELDNO

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SYSTEM WELDNO ISONO CYCLE IllMNO CATEGORY EXREQ EXSCHD NDEPROC CALSTD G MFDIA NOM 11K'K CfMPDESA GMFDLSit RHRS OfDst-3-21 ISl4330 C 01 08 NUO313 C

80242 UT N-UT48 BF47 20.00 1.031 PE.EL PC VLV RHRS DRHR-3-22 IS84330C 01 08 NUO313 C

80242 UT N-UT44 BF47 20.00 1.031 PC.RV PC. PIPE i

RHRS DRHR-3-22 IS84330 C 01 OS NUO313 C

80242 UT N-UT40 BF47 20.00 1.031 PC.RV PC. PIPE 1

RHRS DRHR-3-23 IS84330C 01 08 NUO313 C

B0242 UT N-UT44 BF47 20.00 1.031 PC. PIPE PC WV RHRS DRHR-3-23 1S84330C 01 08 NUO313 C

B0242 UT N-UT48 BF47 20.00 1.031 PC.PW E PC,WV RHRS DSRHR-341 IS$4330 C 01 08 NUO313 C

80242 UT N-UT44 BF-57 24 00 1.219 PC.EL PC.PtPE RHRS DSRHR-341 1S84330C 01 08 NUO313 C

802-02 UT N-UT48 BF-57 24.00 1.219 PC.EL PC. PIPE

[

RHRS DSRHR-342 IS84330C 01 08 NUO313 C

80242 UT N-UT44 BF47 24.00 1.219 PC. PIPE PE.EL f

RHRS DSRHR-342 1884330C 01 08 NUO313 C

B0242 UT IHIT40 BF-57 24.00 1.219 PC. PIPE PE.EL RHRS DSRHR-343 IS84330 4 01 08 NUO313 C

B0242 UT N-UT44 BF-57 24.00 1.210 PC. PIPE PC. PIPE i

RHRS DSRHR-343 IS$4330C 01 08 NUO313 C

B0242 UT N-UT40 BF-57 24.00 1.219 PC. PIPE PC. PIPE RHRS DSM-344 ISI-0330C 01 08 NUO313 C

B0242 UT N-UT44 BF-57 24.00 1.219 PC. PIPE PE.EL f

RHRS DSRHR-344A 1S44330C 01 08 NUO313 C

802-02 UT N-UT44 BF-57 24.00 1.219 PE.EL PE.EL RHRS DSRHR-3-05 IS84330 C D1 08 80.11 B4 SSE42 PT N-PT-9 24.00 1.219 PE.EL PC. PIPE i

l Rifts DSRHR-3-05 IS84330 4 01 08 80.11 B4 SSE42 UT N-UT44 BF-57 24.00 1.219 PE.EL PC.PIPt:

j RHRS DSRHR-345 IS8-0330 4 01 OS NUO313 C

80242 UT N-UT44 BF-57 24.On 1.219 PE.EL PC. PIPE RHRS DSRHR-345A IS84330C 01 06 NUO313 C

B0242 UT N-UT44 BF-57 24.00 1.219 PC PIPE PE.EL l

t RHRS DSRHR-348 IS84330C 01 08 11U0313 C

B0242 UT N-UT44 BF-57 24.00 1.219 PC. PIPE PE.EL RM DSRHR-3-08 IS84330C 01 08 NLIO313 C

B0242 UT N-UT48 BF-57 24.00 1.219 PC PIPE PE.EL RHRS DSfD5t-3-08 IS84330C 01 08 TS43G BJ B0442 PT N-PT-9 24.00 1.219 PC. PIPE PE.EL I

RHRS DSRHR-348 IS84330 4 01 08 TS40G B-J B0442 UT N-UT44 BF-57 24.00 1.219 PC. PIPE PE EL

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RHRS DSRHR-3-08 IS84330C 01 08 TS40G B-J B0442 UT N-UT40 BF-57 24.00 1.219 PC. PIPE PE.EL f

RHRS DSRHR-347 IS84330C 01 08 NUO313 C

B0242 UT N-UT44 BF-57 24.00 1.219 PE.EL PE.EL RHRS DSRHR-3-07 ISI-0330 C 01 08 NUO313 C

B0242 UT N-UT40 BF-57 24 00 1.219 PE EL PE EL f

RHRS DSRHR-308 IS14330-C 01 08 B9.31 B-J 89E-02 PT N-PT-9 20.00 1.031 PBC.A PC. PIPE RHRS DSRHR-3-08 IS84330C 01 08 B9 31 B-J 89E42 UT N-UT44 BF47 20 00 1.031 PBC.A PC, PIPE SURTORDER: SYSTEM-DVELDNO P'Ed */13

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SYS1EM WELDNO ISONO CYCLE ITEMNO CATEGORY EXREQ EXSCHD NDEPROC CALSTD COMFDIA NOM 111CK COMFDESA COMFDL.ss RHRS DSRt5t-3-08 IS84330 C 01 08 NUO313 C

80242 UT NUT 44 SF47 20.00 1.031 PBC.A PC PIPE t

RHRS DSRift-100 IS84330-C 01 08 NUO313 C

80242 UT N4fT44 BF47 20.00 1.031 PC, PIPE PE EL Rifts DSRHR-349 ISS-0330C 01 08 NUO313 C

80242 UT N4JT48 8F47 20.00 1.031 PC PW'E PE.EL RHRS DSRHR-3-10 ISI 0330sC 01 OS NUO313 C

80242 UT N4JT44 SF47 20.00 1.031 PC. PIPE PE EL Rifts DSRift-3-10 1664330C 01 08 NUO313 C

80242 UT N4fT48 SF47 20 00 1.031 PC PN'E PE.EL RHRS FCV74-544C IS$4336C 01 08 87.70 84-2 80E42 VT-1 N-VT-1 BVAL I

RHRS FCV7448 8804330 4 01 OS 87.73 84-2 V0142 VT-1 N-VT-1 24.00 1.219 AVAL54T RHRS TRHR-3-191 Mil 4330401 08 80.11 84 80E42 PT N-PT4 20 00 1.031 PC,VI.V PC.EL

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RHRS TRHR-3-101 1804 330 4 01 OS 80.11 BJ 80E42 UT N4fT44 8F-00 20.00 1.031 PC,VLV PC.EL f

RtstS TRHR-3-191 IS$4330 C 01 05 NUO313 C

80242 UT N4JT44 8F-90 20.00 1.031 PC,VLV PC.EL f

RPV 348-3.3.1 A 08 815.50 SP 80E42 VT-2 N-VT-4 RPV 3-St-3.3.1 A.

08 815.10 BP 80E-02 VT-2 N-VT-4 i

RPV 3-SI-3.3.1 A 08 815.00 8-P 90E42 VT-2 N-VT-4 RPV 3-St-3.3.1 A 08 815.70 BP 80E-02 VT-2 N-VT-4 RPV 3-SI-3.3.1.C 00 C7.70 C-H 00E42 VT-2 N-VT-4

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f RPV 3-SI-3.3.1.C 08 C7.30 C-H 80E 02 VT-2 N-VT-4 RPV 3-St-3.3.1.C 08 C7.70 C41 40E42 VT-2 N-VT-4 f

t RPV 3-SI-3.3.1.C OS C7.30 C-H 80E42 VT-2 N-VT-4 l

f RPV 3-St-3.3.11 08 C7.30 CH 80E42 VT-2 N-VT 4 RPV 3-SI-3.3.11 08 C7.70 C41 80E-02 VT-2 N-VT-4 i

RPV 3-St-3.3.2A 08 C7.30 C-H 80E42 VT-2 N-VT-4 f

i RPV 3-St-3.3.2A 08 C7.70 C-H 80E-02 VT-2 N-VT-4 l

t RPV 3 SI-3 3.2.8 08 C7.30 C-H 80E-02 VT-2 N-VT-4 i

RPV 3-St-3.3.2.8 08 C7.70 C-H 80E 02 VT-2 N-VT-4 RPV 3-S8-334 06 C7.30 C-H 80E-02 VT-2 N-VT-4 RPV 3-St-3 3.4 08 C7.50 C44 80E42 VT-2 N-VT4 i

SUKTORDER: SYSTEM-WELDNO

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SYSTEM WELDNO ISONO CYCLE ITEMNO CATEGORY EXREQ EXSCHD NDEPROC CALSTD COMPDIA NOMHICK COMPDESA COMFDEsit RPV 3-S84 3.4 08 C7.70 C-H 80E-02 VT-2 N-VT4 RPV 3-SI-3.3.5 08 C7.70 C-H 80E42 VT-2 N-VT-4 RPV 3-St-3.3.5 08 C7.30 C-H 80E-02 VT-2 N-VT-4 RPV 1S8-3.3.7 08 C7.70 C-H 80E42 VT-2 N-VT-4 RPV 3-St-3 3.7 08 C7.30 C41 80E42 VT-2 N-VT-4 RPV 3-SI-3.3 8 B 08 C7.70 C-H 80E42 VT-2 N-VT-4 RPV 3-St-3.3.8.B 08 C7.30 C41 80E-02 VT-2 N-VT-4 RPV INTERIOR IS84220C 02 08 B13.10 B48-1 80E42 VT VENDOR RPV N1A IS84328 4 01 08 83.90 B-D 80E42 UT VENDOR BF-18 28.00 SNOZRCO SSHELL RPV N1A-IR IS84328 4 01 08 B3.100 B-O 80E42 UT VEleOR BF-18 SNIRRCO RPV N1A-SE IS14328 4 01 08 85.10 Bf 80E-02 PT NPT4 28.00 SNOZRCO PC.SE i

RPV N1A-SE IS84328 4 01 08 85 10 BF 80E-02 UT M4JT44 BF-90 28.00 SNOZRCO PC.SE RPV N1A-SE IS84328 4 01 08 85.10 Bf 80E42 UT N4JT44 BF-107 28.00 SNOZRCO PC.SE RPV N1A-SE 8S44328 4 01 08 B5.10 B-F 80E-02 UT N4JT48 BF-107 28.00 SNOZRCO PC.SE i

RPV N1A-SE IS84326 4 01 08 B5.10 Bf 80E42 UT N4JT48 BF-90 28.00 SNOZRCO PC SE RPV N1A-SE ISI43284 01 08 NUO313 C

B0242 UT N-UT44 BF-107 28.00 SHOZRCO PC.SE RPV N1A-SE ISI-03284 01 08 NUO313 C

B0242 UT N-UT44 BF-90 28.00 SNOZRCO PC.SE e

RPV N1A-SE IS84328 4 01 08 NUO313 C

B02-02 UT N-UT48 BF-107 28.00 SNOZRCO PC.SE

[

RPV NIA-SE IS84328 4 01 08 NUO313 C

B0242 UT N-UT48 BF-90 28.00 SNOZRCO PC.SE i

RPV N18-SE IS84328 4 02 08 NUO313 C

B02-02 UT N4JT44 BF-107 28 00 SNOZRCO PC,SE i

RPV N18-SE IS84328 4 02 08 NUO313 C

B0242 UT N41T44 BF-90 28 00 SNOZRCO PC.SE RPV N18-SE ISl43284 02 08 NUO313 C

B0242 UT N4JT48 BF-90 28.00 SNOZRCO PC SE RPV N18-SE ISO-03284 02 08 NUO313 C

B0242 UT N-UT48 BF-107 28 00 SNOZRCO PC.SE RPV N2B ISl4328-C 02 08 B3 90 B-D 89E-02 UT VENDOR BF-18 12.00 SNOZRCI SSHELL RPV N28-IR IS84328 4 02 08 B3.100 B-D 80E42 UT VENDOR BF-18 SMIRRCI RPV N2D 1S84328 4 02 08 B3 90 B-D 89E-02 UT VENDOR BF-18 12.00 SNOZRCI SSHELL SORTORDER: SYSTEM-WELDNO ray II of13

~-

SYSTEM WELDNO ISONO CYCLE IlEMNO CATEGORY EXREQ EXSCHD NDEPROC CALSTD COMPDIA NOMTitCK COMPDESA COMPDESit RPV N2(MR ISI.0328-C 02 08 B3.100 B-D 89E-02 UT VENDOR BF-18 SMRRCI RPV N2F ISl432&C 02 08 B3.90 B-D 89E-02 UT VENDOR BF-18 12.00 SNOZRCI SSELL RPV N2F-IR ISM 326-C 02 08 B3.100 B-D 89E42 UT VENDOR BF-18 SNIRRCI RPV N38 IS8432SC C2 08 B3.90 B-D 89E42 UT VENDOR BF-18 26.00 SNOZMS SSHELL RPV N3ENR IS8432SC 02 08 B3.100 B-D 89E-02 UT VENDOR BF-18 SNEMS RPV N38-SE IS8432SC 02 08 B9.11 84 80E42 MT N-MT4 28.00 SNOZMS PC.SE RPV N38-SE ISM 329-C 02 08 89.11 B-J 80E-02 UT N U7-18 BF-104 28.00 SOZMS PC.SE RPV N4A(NOZ BORE)

IS84327-C 01 08 NUO619 7112 B0142 UT VENDOR BF-93 SNOZIWB SSE RPV N4A-IR IS84327-C 01 08 NUO619 7112 80142 UT VENDOR BF-18 SNIRFW RPV N48 IS84327-C 01 08 B3.90 B-D 89E42 UT VENDOR BF-18 12.00 SNOZFW SSHELL

[

RPV N4B(NOZ BORE)

IS84327-C 01 08 NUO619 7112 B01-02 UT VENDOR BF-93 SNOZFWB SSE RPV N4EN R ISI43274 01 08 83.100 BD 80E-02 UT VENDOR BF-18 SMRFW RPV N4ENR IS84327-C 01 08 NUO619 7112 B0142 UT VENDOR BF-18 SNIRFW RPV N4EMiE IS84327 4 01 08 89.11 B4 80E-02 MT N-MT4 14.00 SNOZFW PC.SE RPV N48-SE ISI-0327-C 01 08 99.11 B.J 80E42 UT N-UT-18 BF-58 14 00 SNOZFW PC.SE RPV N4C iS84327-C 01 08 B3.90 B-D 89E42 UT VENDOR BF-18 12.00 SNOZFW SSHELL RPV N4C(NOZ BORE)

ISl4327-C 01 08 NUO619 7112 801-02

.UT VENDOR BF-93 SNOZFWB SSE RPV N4C-IR IS84327-C 01 08 B3.100 B-D 89E42 UT VENDOR BF-18 SNIRFW RPV M4C-IR IS84327-C 01 08 NUO619 7112 90142 UT VENDOR BF-18 SNIRFW RPV N4C-SE ISI-0327-C 01 08 89.11 B4 80E42 MT N-MT4 14.00 SNOZFW PC.SE RPV N4C-SE IS44327-C 01 08 89.11 BJ 89E-02 UT N-UT-18 BF-58 14 00 SNOZFW P0SE RPV N40(NOZ BORE)

IS84327-C 01 08 NUO619 7112 901-02 UT VENDOR BF-93 SNOZFWB SSE RPV M4D-IR ISI-0327-C 01 08 NUO619 7112 801-02 UT VENDOR BF-18 SMRFW RPV N4E(NOZ BORE)

ISI4327-C 01 08 NUO619 7112 B01-02 UT VENDOR BF-93 SNOZFWB SSE l

RPV N4E-IR IS84327-C 01 08 NUO619 7112 801-02 UT VENDOR BF-18 SMRFW RPV N4F(NOZ BORE)

ISI-0327-C 01 08 NUO619 7112 B01-02 UT VENDOR BF-93 SNOZfWB SSE SURTORDER: SYSTEM-WELDNO

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• t SYSTEM WELDNO ISONO CYCLE ITEMNO CA1TEOY EXREQ EXSCO NDEPROC. CALSTD COh4PDIA NOMTHCK COMPC3SA COMFDESS t

frv fMF-4R IS$4327401 08 NUOS19 7112 80142 UT VEDOOR OF-18 SpefyW l

r RPV NSA 1S84331 4 01 08 83.90 SD 80E42 UT VEfeOR BF-18 10.00 SNOZCS SSDELs.

s RPV NSA-IR IS84331-C 01 08 83.100 80 00E42 UT VEfeOR OF-18 SNWICS

^

RPV NSA-3-1-8C IS84206 A 01 08 87.50 54-2 80E42 VT-1 N-VT-1 BFLG RPV NBA ISHM114 01 08 83.90 54 80E42 UT VEteOR OF-18 04.00 SNQZJP1 SSHELL RPV NAA-IR ISHM114 01 OS 83.100 B4 80E-02 UT VENDOR 8F-18 SNNUPI i

RWCUS 3RWCU40 ISHl333 C 01 08 NUO313 C

80242 UT N-UT44 BF-01 04.00 0 375 PC VLV PC. PIPE i

RWCUS RWCU4401442 ISHD32401 OS 80.11 B,J P0742 PT N-PT-9 RWCUS RWCU4401442 ISHl332-C 01 08 80.11 54 P0742 UT N-UT44 BF-31 RWCUS RWCU4401043 1884 332 4 01 08 80.11 84 P0742 PT NPT-9 I

RWCUS RWCU4401443 ISHD32-C 01 08 80.11 B4 P07-02 UT N-UT44 BF-31 RWCUS RWCU-3401444 ISHD324 01 08 80.11 84 P0742 PT NPT-9 RWCUS RWCU-3401444 ISHD32-C 01 00 80.11 EJ P0742 UT N41T44 BF-31 RWCUS RWCU-3401-006 ISHD32-C 01 08 89.11 84 P0742 PT N # T-9 i

I RWCUS RWCU-3401-006 IS84332 4 01 08 80.11 B4 P0742 UT N-UT44 BF-31 i

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SORTORDER: SYSTEM-WELDNO A

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