Text

Fermi 2 - Summary Report of the 2009 Inservice Inspection Activities
	ML092100486
Person / Time
Site:	Fermi
Issue date:	07/23/2009
From:	Plona J H; DTE Energy
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209, NRC-09-0038
	Download: ML092100486 (303)
	v • d • e

Joseph H. Plona Site Vice President 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.5910 Fax: 734.586.4172 DTE Energy-10 CFR 50.55a 9 July 23, 200Y NRC-09-0038 U. S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington D C 20555-0001

Reference:

Subject:

Fermi 2NRC Docket No. 50-341 NRC License No. NPF-43Inservice Inspection Summary Report Enclosed is the Summary Report of the 2009 Inservice Inspection (ISI) activities performed at Detroit Edison Company's Fermi 2 Nuclear Power Plant. This report represents a summary of the ISI activities for the Second Ten-Year Inspection Interval beginning February 17, 2000 through the Thirteenth Refueling Outage, which was completed on May 1, 2009.This report is being submitted in accordance with ASME Section XI, 1989 Edition, paragraph IWA-6230, for IWB, IWC, IWD, and IWF inspections, and the 1992Edition, including the 1992 Addenda, for IWE inspections.

Should you have any questions or require additional information, please contact Mr. Rodney W. Johnson, Manager -Nuclear Licensing, at (734) 586-5076.Sincerely, Enclosure cc: NRC Project Manager NRC Resident Office Reactor Projects Chief, Branch 4, Region III Regional Administrator, Region III M. Wilson -ANH Supervisor, Electric Operators, Michigan Public Service Commission R. J. Aben Jr. -Chief Inspector Michigan Department of Labor & Economic Growth Bureau of Construction Codes and Fire Safety -Boiler Division 0"1 " --ýý)" A o, 17 Sheet 1 of 1 FORM NIS-1 OWNERS' DATA REPORT FOR LNSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules 1. Owner Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 (Name and Address of Owner)2. Plant Fermi-2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport MI 48166 (Name and Address of Plant)3. Plant Unit 2 4. Owner Certificate of Authorization (if required)

N/A 5. Commercial Service Date 01-23-88 6. National Board Number for Unit N/A 7. Components Inspected See Program Table in Section 7.0 and 8.0 of attached Summary Report Component Manufacturer Manufacturer or State or National Appurtenance or Installer Installer Serial No. Province No. Board No.RPV Combustion Engineering CE-67211 M345962M 21085 Class 1, 2, & 3 Wisner & Becker Components (1) Townsend & Bottom Various M345962M N/A Associated Supports Chicago Bridge & Iron Various M345962M N/A Reactor Controls Inc. Various M345962M N/A Walbridge Aldinger Co. Various M345962M N/A Containment Vessel Chicago Bridge and Iron C-4512 N/A N/A Note: Supplemental sheets in formn of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. x 11 in., (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(1) Certificate of Accreditation No. OWN-159 for N-3 Data Report.

Sheet 1 of 1 FORM NIS-1 (back)8. Examination Dates 11/19/2007 to 05/01/2009

9. Inspection Interval from 02/17/00 to 05/01/2009

10. Abstract of Examinations.

Include a list of examinations and a statement concerning status of work required for current interval. (A listing of all required examinations and those completed to date for Interval 2, Period 3, Refuel Outage Thirteen (RF-13), is included in the ISI Summary Report of the 2009 Inservice Inspection, Sections 6 and 7.)11. Abstract of Conditions Noted (included as Section 5 with IWE in Section 8 of Summary Report).12. Abstract of Corrective Measures Recommended and Taken (included as Section 5 and 8 of Summary Report).We hereby certify that the statements made in this report are correct and the examinations andcorrective measures taken conform to the rules of the ASME Code,Section XI.Date 2009 Signed Detroit Edison Co. By D,/" 2 9 Sge Owner Lead ISI Engineer Certificate of Authorization No. (if applicable) N/A Expiration Date N/A CERTIFICATE OF LXSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, Conn 06102, have inspected the components described in this Owners Data Report during the period of 11/19/2007 to 05/01/2009 and state thatto the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date 6(tA L 2 , 2009 Signed (L. Commissions

/0 Inspector's Signature State, Province ISI

SUMMARY

REPORT OF THE 2009 INSERVICE INSPECTION Refueling Outage RF- 13 at Fermi 2 Nuclear Power Plant6400 N. Dixie Highway Newport, MI 48166Detroit Edison Company One Energy Plaza Detroit, MI 48226 Commercial Service Date: January 23, 1988 NB No. 21085 (RPV)Michigan Boiler Serial Number M345962M To: U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Prepared by: Marc A. Brooks Lead ISI Engineer, NDE Program Level III Reviewed by: 6-tLF&, a x "[cq-.-(Richard M. Ham leton Lead ISI Engineer, RVIM Program Level III Approved by: "7-17--r Tom Dong -rv> q5 -O t Manager, Performance Engineering Detroit Edison Co., One Energy Plaza, Detroit, M1 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)

TABLE OF CONTENTS I Se ction I Description 1 INTRODUCTION 2

SUMMARY

OF ASME CLASS 1 & 2 AND AUGMENTED EXAMINATIONS 3

SUMMARY

OF REACTOR INTERNAL EXAMINATIONS 4

SUMMARY

OF COMPONENT SUPPORT EXAMINATIONS 5 ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE ACTIONS TAKEN 5.1 REFUEL-13 5.2 REFUEL-12 5.3 REFUEL-11 5.4 REFUEL-10 5.5 REFUEL-09 5.6 REFUEL-08 5.7 REFUEL-07 6 PROGRAM STATUS, ASME SECTION XI CREDIT

-IWB, IWC, & IWF 7 UPDATED PROGRAM TABLES ENCLOSED PROGRAM TABLES TABLE A -(34 pages)TABLE B -(10 pages)8

SUMMARY

OF CONTAINMENT INSPECTIONS (IWE)

ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE ACTIONS TAKEN ENCLOSED PROGRAM TABLES (23 pages)9 SECTION XI REPAIR/REPLACEMENT NIS-2 FORMS INDEX (Forms Attached -Note NIS-2 forms are double sided)

Page(s)1-7 8 -53 54 -68 69 -72 73 -87 88-117 118-130 131- 146 147- 149 Detroit Edison Co., One Energy Plaza., Detroit, MI 48166 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)

SECTION 1 INTRODUCTION Detroit Edison Co., One Energy Plaza., Detroit, MI 48166 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48226 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)1

1.0 INTRODUCTION

1.1 This report represents a summary of the Inservice Inspection (ISI) activities performed at Detroit Edison Company's Fermi 2 Nuclear Power Plant for the Second Ten-year Inspection Interval beginning February 17, 2000 and concluding on 5/1/2009.Fermi 2 -Program B (ASME Section XI, IWA-2420):

Second Inspection Interval (1989 Edition)1. First Inspection Period a. Seventh Refueling Outage b. Eighth Refueling Outage 2. Second Inspection Period a. Ninth Refueling Outage b. Tenth Refueling Outage

3. Third Inspection Period a. Eleventh Refueling Outage b. Twelfth Refueling Outage c. Thirteenth Refueling Outage (02/17/00

-05/01/2009)*

(02/17/00

-03/27/03)(04/01/00

-05/23/00)(10/22/01

-11/30/01)(03/28/03

-10/17/05)(03/28/03

-05/10/03)(11/06/04

-12/03/04)(10/18/05

-05/01/09)(03/25/06

-05/05/06)(09/29/07

-11/18/07)(03/28/09

-05/01/09)Fermi 2 was in an extended outage that began on 12/25/93 following a Turbine/Generator failure and ended with the closing of the output breaker on 01/18/95.

Because of the extended shutdown, the first inspection interval for Fermi 2 was extended by one additional year to 2/16/2000 as provided for in IWA-2430.

The second inspection interval is being shortened by nearly 10 months to maintain the overall pattern of intervals well within the one year maximum adjustment permitted in IWA-2430.

1.2 Examinations were performed to satisfy the requirements (or portions thereof) of the following, as applicable:

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)2

American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code,Section XI, Division 1, "Rules for Inservice Inspection of Nuclear Power Plant Components," Inspection Program B as listed in the following Table A and Section 6 of this report." NUREG-0313, Revision 2, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping.

BWRVIP-75, Technical Basis for Revision of NRC Generic Letter 88-01 Inspection Schedules." Fermi 2 Technical Requirements Manual TR 5.1.1, Augmented Inservice Inspection Program for Snubbers.* Augmented Inspection of selected components in accordance with the requirements as listed in the following Table A and Section 6 of this report.

BWROG NUREG-0619 Alternate Feedwater Nozzle Inspection Requirements, GE-NE-523 0292.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)3 TABLE A REQUIREMENT DESCRIPTION VESSELS EXAM METHODSect. XI, 1989 Edition Pressure Vessel (B-A, B-D, B-H, C-A, C-B)Appendix VIII, 1995 Edition, 1996 Addenda for UT as applicableReactor Vessel Interior and welded attachmentsor core support structures (B-N-i, B-N-2)Integral attachments for vessels (B-H, C-C)Pressure retaining bolting

>2" diameter (B-G-1,C-D)Pressure retaining welds in CRD housing (B-O)Surface and/or AutomatedVolumetric or Manual Volumetric Visual Examination Surface and/or Volumetric Surface and/or Volumetric Surface and/or VolumetricSect. XI, 1992 Edition, 92 AddendaContainment Inspection (IWE)Visual PIPING Sect. XI, 1989 Edition Appendix VIII, 1995 Edition, 1996 Addenda for UT as applicablePressure retaining Piping Welds (B-F, B-J, C-F)Surface and/or Manual Volumetric or Automated VolumetricIntegral attachment for piping pumps and valves (B-K-l, C-C, Code Case N-509)Surface and/or Volumetric OTHER 1989 EditionPressure retaining partial penetrationwelds (B-E)Pressure retaining bolting <2" diameter (B-G-2)Pressure retaining bolting

>2" diameter (B-G-l)Pressure boundary component supports(F-A, Code Case N491-1)Pump and Valve Internal Surfaces(B-L-2, B-M-2)Visual ExaminationVisual Examination Visual Examination and /or Volumetric Visual Examination Visual Examination Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)4 REQUIREMENT 1989 Edition NUREG-0313, Rev. 2 and BWRVIP-75BWROG NUREG-0619 Alternative FeedwaterNozzle Inspections Fermi 2 TechnicalRequirements Manual TR 5.1.1 IE Notice 93-079 Generic Letter 94-03 IEB 80-13 SIL No. 459 SIL No. 409RICSIL No.

073 SIL No. 420 SIL No. 433 TABLE A (continued)

DESCRIPTION PRESSURE TEST Interval 2 Pressure Testing (B-P, C-H,and D-B, Code Case N-416-1, Code Case N-498-1)AUGMENTEDPressure retaining piping welds (B-F, B-J)IGSCC in BWR Austenitic Stainless Steel Piping Pressure retaining piping welds (Nonclassed)

Feedwater Nozzle Inner Blend Radii (GE-NE-523-A71-594)

Safety Related Snubbers Sampling of Safety Related SnubbersCore Shroud Core Shroud Welds Core Spray and Spargers Vendor Recommendations Byron Jackson Recirculation Pump Shaft Cracking Incore Dry Tube Cracks Incore Dry Tube Cracks Jet Pump Sensing Lines and Support BracketsShroud Head Bolts EXAM METHODVisual Examination Manual Volumetric and/or Automated VolumetricManual Volumetric Manual or Automated from outside surface Volumetric

-Visual ExaminationFunctional Testing Visual Examination Visual Examination Visual Examination Visual ExaminationRemote Visual Examination

Remote Visual ExaminationRemote Visual ExaminationRemote Visual Examination Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)5 REQUIREMENT SILNo. 462 SIL No. 465 SIL No. 474 SIL No. 551 SIL No. 554 STL No. 559 SIL No. 574 SIL No. 588, Rev. 1 SIL No. 629 SIL No. 644, Rev. 0, Supplement 1 and SIL No. 644, Rev. 1BWRVIP-03 Reactor Vessel and Internal Examination GuidelinesBWRVIP-18-A Core Spray Inspection and Evaluation (I&E)GuidelinesBWRVIP-25 Core Plate I&E Guidelines BWRVIP-26-A Top Guide I&E GuidelinesBWRVIP-27-A BWR Standby Liquid Control System / Core Plate Differential Pressure I&E GuidelinesTABLE A (continued)

DESCRIPTION AUGMENTED (continued)

Access Hole Cover Cracking Jet Pump Inlet Mixer Steam Dryer Channel Cracking Jet Pump Riser Bracket Top Guide Beams Top Guide Inspections Jet Pump Adjusting Screw Tack Welds Top Guide and Core Plate Cracking Inlet Mixer Wedge Damage in BWR Jet Pump Assemblies BWR Steam Dryer IntegrityReactor Vessel Internals Components Core Spray Internals Piping and Spargers Core Plate Components Top Guide Components Core Differential Pressure and SLC Line Dissimilar Metal Nozzle Welds EXAM METHODRemote Visual Examination Remote Visual ExaminationRemote Visual ExaminationRemote Visual ExaminationRemote Visual ExaminationRemote Visual ExaminationRemote Visual ExaminationRemote Visual ExaminationRemote Visual ExaminationRemote Visual InspectionRemote Visual Examination, Ultrasonic and Eddy Current Remote Visual Examination Remote Visual Examination Remote Visual Examination Direct Visual Bare Metal VT-2 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)6 TABLE A (continued)

REQUIREMENT DESCRIPTION EXAM METHOD AUGMENTED (continued)BWRVIP-38 Shroud Support I&E Guidelines BWRVIP-41, Rev. 1 Jet Pump Assembly I&E Guidelines BWRVIP-47-A BWRLower Plenum I&E Guidelines BWVRIP-48-A Vessel ID Attachment WeldI&E Guidelines BWRVIP-49-AInstrument Penetration I&E Guidelines BWRVIP- 104 Evaluation and Recommendation To Address ShroudSupport Cracking in BWRs BWRVIP-139 SteamDryer Inspection and Flaw Evaluation GuidelinesBWRVIP-76 BWR Core Shroud Inspection and Flaw Evaluation GuidelinesBWRVIP-180 (Draft)

Access Hole Cover Inspection and Flaw Evaluation Guidelines Shroud Support Components Jet Pump Components Incore Guide/Dry TubesVessel Internal Attachments Instrument Penetrations Shroud Support.Steam Dryer Core Shroud Access Hole Cover Remote Visual ExaminationRemote Visual Examination Automated Ultrasonic for Diffuser Adapter Welds Remote Visual ExaminationRemote Visual Examination Remote Visual ExaminationRemote Visual and VolumetricRemote Visual Examination Remote and Volumetric Methods asin BWRVIP-03Remote Visual Examination Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)7 SECTION 2

SUMMARY

OF ASME CLASS 1 & 2 AND AUGMENTED EXAMINATIONS Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)8 2.1 Interval 2, Period 3 RF 13 Examinations AR F M 3 (EXAMI S CAT/COMP ID DESCRIPTION ISO Exams Procedure CALSTD COMP L III ANII Renort LocIAz/EI B-D Reactor Vessel 14-316B 13-314-B 13-314-KB-F Class 1-Piping N5B 2-303B 2-303K 5-315 SW-E21-3052-4WOX Nozzle to Vessel Welds CS Nozzle to Vessel Weld RRI Nozzle to Vessel Weld RRI Nozzle to Vessel Weld RIISI Welds 10" DM Nozz-SE 12" DM Nozz-SE 12" DM Nozz-SE 2.75" DM Nozz-SE DM-SE to Extension 5361-5 UT 6&11 2667-62-1 4/7 4/13 4/21 RF013-31 5361-5 UT 6& 11 2667-60-1 4/9 4/13 4/21 RF013-32 5361-5 UT 6&11 2667-60-1 4/9 4/13 4/21 RF013-33 3052-5 5358-5 5356-5 5361-5 R1-91 5361-5 UT UT UT UT UT 7&21 7&21 7&21 12 7&21 FER-44,45 FER-54,56 FER-54,56 FER28 FER-18-45 4/8 4/10 4/13 4/8 4/6 4/13 4/14 4/14 4/13 4/13 4/21 4/21 4/21 4/22 4/21 RF013-04 RF013-05 RF013-06 RFo 13 -44 RF013-03 DW,240,641' DW, 60, 615'DW, 330, 615 DW,240,641' DW, 60, 615'DW,330,615 DW, 180,607'DW,240,641' Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)9 RF113EXAMS CAT/COMP ID B-J Class 1-Piping FW-RD-2-B 16 FW-RD-2-A19 B-G-2 Bolting DESCRIPTION RIISI Welds Pipe to SE (IGSCC/CRC)

Pipe to SE (IGSCC/CRC)

ISO Exams Procedure CAL STD PDI-Alt.5358-5 UT 5 SS PDI-Alt.5356-5 UT 5 SS COMP L III ANII Report RF013-43 RF013-42 Loc/Az/EI 4/6 4/13 4/22 4/6 4/13 4/22 DW, 60, 615'DW,330,615' 2" and Less B21-FO13A-VBB FBC-B21-5355-01A B21-FO13D-VBB FBC-B21-5353-01D B21-FO13J-VBB FBC-B21-5354-01J B21-FO13M-VBB FBC-B21-5352-01M G33-F121-VBB-3536-5 El l-F015AVBB El 1-F050AVBB El 1-F050BVBB E21-F006BVBB Valve Bolting Valve Bolting Valve Bolting Valve Bolting Valve Bolting Valve Bolting Valve Bolting Valve Bolting Valve Bolting Valve Bolting Valve Bolting Valve Bolting Valve Bolting Valve Bolting 5355-5 5355-5 5353-5 5353-5 5354-5 5354-5 5352-5 5352-5 3536-5 2298-5 2298-5 2327-5 3053-5 VT-I VT-I VT-l VT- 1 VT- 1 VT- 1 VT- 1 VT-l VT-I VT-I VT-I VT-I VT-I 15 15 15 15 15 15 15 15 15 15 15 15 15 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/10 4/4 4/4 4/10 4/6 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/15 4/7 4/7 4/15 4/9 4/19 4/19 4/18 4/18 4/18 4/18 4/18 4/18 4/19 4/22 4/22 4/22 4/22 RF013-63 RF013-63 RFO13 -64 RFO13 -64 RF013-65 RF013-65 RF013-66 RF013-66 RF013-49 RF013-24 RF013-25 RF013-48 RF013-34 RF013-41 DW,320,613' DW,320,613' DW,62,613 DW,62,613 DW,314,613' DW,314,613' DW,45,613Y DW,45,613' STM,F12,586' RB1,B 13,594 DW,270,600' DW,104,600' DW,150,627' STM, F12,587'E51-FO08VBB 2192-5 VT-I 15 N/A 4/6 4/21 4/22 B-K-1 Integral Attachment Welds SW-PS-2-A2-AAI SW-PS-2-A2-AA2 SW-PS-2-A2-AA3 SW-PS-2-A2-AA4 Piping Attachment Welds MS Pipe Lug Class 1 MS Pipe Lug Class 1 MS Pipe Lug Class 1 MS Pipe Lug Class I 5352-5 5352-5 5352-5 5352-5 MT MT MT MT 2 2 2 2 N/A N/A N/A N/A 4/6 4/6 4/6 4/6 4/9 4/9 4/9 4/9 4/15 4/15 4/15 4/15 RF013-35 RF013-36 RF013-37 RF013-38 DW,72,638' DW,72,638' DW,72,638' DW,72,638'Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)10 RFICEXATMS I CATICOMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L IIl ANII Report Loc/AzIEI F-A Component Supports 4" Penetration X-10 10" Penetration X- 11 24" Penetration X-13B 20" Penetration X- 12 12" Penetration X-16A 6" Penetration X-43 20" Penetration X-9B 26" Penetration X-7A Anchor Support Structure RCIC Penetration Anchor Structure HPCI Penetration Anchor Structure RHR Penetration Anchor

'Structure RHR Penetration Anchor Structure Core Spray Penetration Anchor Structure RWCU Penetration Anchor Structure FW Penetration Anchor Structure MS Penetration Anchor Structure 2192-5 2297-5 2298-5 2299-5 3053-5 3096-5 3536-5 5352-5 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 18 18 18 18 18 18 18 18 N/A N/A N/A N/A N/A N/A N/A N/A 4/3 4/3 4/3 4/3 4/3 4/3 4/3 4/3 4/7 4/7 4/7 4/7 4/7 4/7 4/7 4/7 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 RFO 13-19 RF013-20 RF013-22 RF013-21 RF013-23 RF013-26 RF013-18 RF013-17 STM,350,583 STM,0,587 RB13,B113,594 R131,B112,591' RB2,C 11,633'RB2,C 11,615'STM, 10,594' STM,6,589' C-C Integral Attachment FW-X-223A, W1 I FW-X-223A, W12 Lug Attachment Welds Stiffener Attachment Weld Stiffener Attachment Weld 3153-5 MT 3153-5 MT 2 2 N/A 4/17 4/17 4/17 N/A 4/17 4/17 4/17 RF013-70 RF013-71 TorRm,B 11,541'TorRm,B 11,541'Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date:

1-23-88 NB No. 21085 (RPV)11 RFIC3EXAMPS CATICOMP ID ISO Exams Procedure CALSTD COMP LocIAzIEI DESCRIPTION L III ANII Report C-F-1 Augmented FW-C41-2979-P FW-C41-3361-02W1 FW-X-223A, Wi 1 F-A Component Supports E2101COO1A X-224B P4400C001A P4400B001C R3001C005 R3001B017 R3001B002 R3001B025 P4500C002A ElI51COO1A NRC Commitment 2" pipe to coupling 3" valve to pipe Stiffener Attachment Weld 2979-5 3361-5 PT PT l 1 N/A N/A 4/7 4/7 4/9 4/9 4/16 4/16 RF013-39 RF013-40 RF013-70 RB3,D1 1,648'RB4,E10,660' TorRm,B 11,541'3153-5 MT 2 N/A 4/17 4/17 4/17 Anchor Support Core Spray Pump Base Anchor Torus Penetration Piping Anchor Structure EECW Div. 1 Pump Base Anchor EECW HX Base Anchor DGSW Pump EDG 11 Jkt CIr Anchor Structure EDGI 1 Oil Chr Anchor Structure EDG I I Air Clr Anchor Structure EESW Pump Base Anchor RHRSW Pump Base Anchor 3144-5 3148-5 3351-1 3351-1 2176-2 2176-2 2176-2 2176-2 2176-2 2179-2 Vr-3 Vr-3 Vr-3 Vr-3 Vr-3 VT-3 VT-3 VT-3 Vr-3 VT-3 18 18 18 18 18 18 18 18 18 18 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4/6 4/14 4/1 4/1 4/4 4/4 4/4 4/4 4/4 4/4 4/13 4/17 4/14 4/14 4/7 4/7 4/7 4/7 4/7 4/7 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 RF013-30 RF013-29 RF013-28 RF013-27 RF013-09 RF013-12 RF013-14 RF013-13 RF013-10 RF013-11RBSB,F15, 540' Torus RM F15,541'RB2,A9,613' RB2,A1 2,613'RHR Complex RHR Complex RHR Complex RHR Complex RHR Complex RHR NW Quad Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)12 CATICOMP ID F-A Component Supports MKI01 MKI02 MK145 MK149 24" Penetration X-223A 24" Penetration X-223B El 102CO02B E4101CO01B E4101C002 E4101C001A X-225 C4103COOIA 16 Support Girders 4 Earthquake Ties DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI Anchor SupportRHR Complex undergroundpiping penetration sealRHR Complex underground piping penetration seal RHR Complex piping internal wall penetrations RHR Complex piping internal wall penetrations RHR Penetration Anchor StructureRHR Penetration Anchor Structure RHR Pump Base Anchor HPCl Booster Pump Base Anchor HPCl Turbine Pump Base AnchorHPCI Main Pump Base Anchor Torus Penetration Piping Anchor Structure Standby Liquid Control Pump Base Anchor Torus Support Structure Torus Support Structure 2179-2 2178-2 2176-2 2176-2 3153-5 3153-5 3153-5 3163-5 3162-5 3167-5 3163-5 3361-5 B2-52 B2-60 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Vr-3 VT-3 VT-3 VT-3 VT-3 VT-3 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4/4 4/4 4/4 4/4 4/14 4/14 4/16 4/10 4/15 4/10 4/16 4/13 4/14 4/14 4/7 4/7 4/7 4/4 4/16 4/16 4/17 4/14 4/17 4/17 4/17 4/15 4/16 4/16 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 4/22 RF013-15 RF013-16 RF013-08 RF013-07 RF013-55 RF013-56 RF013-68 RF013-47 RF013-61 RF013-46 RF013-67 RF013-50 RF013-54 RF013-53 RHR Complex RHR Complex RHR Complex RHR Complex Tor,B1 1,542 Tor,C10,543 RHR SW Quad HPCI RM HPCl RM HPCI RM Torus RM. G10, 542'RB4 Mezz Torus RM Torus RM Detroit Edison Co., One Energy Plaza, Detroit, M1 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV)13 RF13 Procedure References Procedure Cross Reference Code Cross Reference Code Method 39.NDE.001 39.NDE.002 54-1S1-136 54-ISI-835 54-ISI-836 54-ISI-850 54-ISI-857 54-1SI-860 54-ISI-861 54-9054490 54-ISI-805 Liquid Penetrant Examination, Solvent Removable Magnetic Particle ExaminationVessel Welds

<2PDI CS PDI-SS RPV Nozzle/ IR Auto DM Acq.Manual PA DMManual PA CS/S RPV Shell Auto PDI-UT-6 RPV Man 1 2 3 4 5 6 Procedure 54-ISI-829 43.000.03 43.000.017 43.000.014

43.000.019

43.000.015 Manual DM PDI-UT-10 VT-3 Snubbers IWI VT-i1 Bolting Primary Cont Valve Internal Component Supports RIISI Coverage JPDA UT Auto DM Sizing ASME Radiography 12 Method 13 14 15 16 17 18 19 20 21 22 7 8 9 10 11 43.000.004 ISI Prog. Part E. Att. 1 GE-UT-545 54-ISI-85639.NDE.01 1 Detroit Edison Co., One Energy Plaza, Detroit, M! 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)14 2.2 Interval 2, Period 3 RF 12 Examinations RF12;EXAMS SCATCOMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/AzIEI B-A Reactor Vessel 1-306F 1-319A 1-319C 1-319G 2-308C 3-319 3-319 RPV Shell Welds Bottom Head Meridional Closure Head Meridional Closure Head Meridional Closure Head Meridional SLongseam Head-to-Flange Head-to-Flange Longseam Longseam Nozzle to Vessel Welds RRS -Nozzle to Vessel RRI -Nozzle to Vessel RRI -Nozzle to Vessel 2667-59-5360-5 UT 11 1 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5361-5 5361-5 5361-5 UT UT UT UT UT MT UT UT UT UT UT 11 11 11 10 11 2 15-308 B 15-308D B-D Reactor Vessel 5-314B 13-314H 13-314J10/10 10/25 10/27 10 10 6&11 6&11 6&11 2667-58-1 2667-58-1 2667-58-1 2667-62-1 2667-58-1 N/A 2667-62-1 2667-62-1 2667-60-1 2667-60-1 2667-60-1 2667-62-1 10/3 10/3 10/3 10/29 10/3 10/3 10/24 10/24 10/24 10/31 10/26 10/26 10/27 10/26 10/26 10/31 10/27 10/27 RF12-1 RF12-2 RF12-3 RF12-4 RF12-5 RF12-6 RF12-7 RF12-9 RF12-10 RF12-11 RF12-12 RF12-13 DW 190, 605'Refuel Floor Refuel Floor Refuel Floor DW, 300,634'Refuel Floor Refuel Floor DW,172, 620'DW,352, 620'DW,180,614' DW,270,615'

DW,300,615' 10/31 10/31 10/31 10/31 10/31 11/1 10/10 10/10 10/13 10/28 10/28 10/29 10/29 10/28 10/30 4-316E FW Nozzle to Vessel 5361-5 UT 6 & 11 10/9 10/29 10/30 RF12-14 DW,270,642' Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)15 RF12 EXAMS*CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/AzIEl 4-316F 8-316C 8-316D B-D Reactor Vessel 5-314B IRS 13-314H IRS 13-314J IRS 14-316A IRS 8-316C IRS 8-316D IRS B-F Class 1-Piping 2-303A 2-303H 2-303J 4-303A FW Nozzle to Vessel MS -Nozzle to Vessel MS -Nozzle to Vessel Nozzle Inner Bore Region Reactor Recirc Suction Nozzle Reactor Recirc Inlet Nozzle Reactor Recirc Inlet Nozzle Core Spray Nozzle Main Steam Nozzle Main Steam Nozzle RIISI Welds 12" RRI -Nozzle to Safe-end (IGSCC)12" RRI -Nozzle to Safe-end (IGSCC)12" RRI -Nozzle to Safe-end (IGSCC)28" RRS -Nozzle to Safe-end (IGSCC)6" JPI Nozzle to Safe-end (IGSCC)5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5358-5 5356-5 5356-5 5357-5 UT UT UT V-1-VT VT VT VT VT UT UT UT UT 6 & 116& 11 6&11 2667-62-1 2667-62-1 2667-62-1 14 N/A 14 N/A 14 N/A 14 N/A 14 N/A 14 N/A FER 54, 7 56 FER 54, 7 56 FER 54, 7 56 FER 55, 7 57 10/19 10/2 10/2 10/21 10/24 10/24 10/23 10/26 10/26 10/16 10/15 10/17 10/19 10/29 10/27 10/27 11/1 11/1 11/1 11/1 11/1 11/1 10/25 10/25 10/25 10/25 10/30 10/28 10/28 11/6 11/6 11/6 11/6 11/6 11/6 10/27 10/25 10/27 10/25 RF12-15 RF12-16 RF12-17 RF12-103 RF12-103 RF12-103 RF12-103 RF12-103 RF12-103 RF12-86 RF12-18 RF12-20 RF12-19 DW,330,642 DW,252,655'

DW,288,655' Vessel,180 Vessel, 270 Vessel, 300 Vessel, 120 Vessel, 252 Vessel,288 DW,30,615', Replaced 102-304A per CARD 07-25329 DW,270,615'

DW,300,615' DW,0,614'102-304A FER 47, Scope Deleted per 5361-5 UT N/A Alt. 1 N/A N/A N/A CARD 07-25329 DW,101,612' Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)16 cRFI21EXAMS CATICOMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report LocIAzIEI B-J Class I-Piping RIISI Welds12" FW Nozz. To Orig.3-316D Safe-end (TASCS)3-316E FW-E21-3052-4WF1 FW-PS-2-A6 FW-RD-2-AI -Wi FW-RD-2-A17 FW-RS-2-A1 N4D N4E SW-PS-2-A4-B SW-RD-2-B4-W2 FW-RD-2-A18 SW-RS-2-A1 -W1 B-G-1 Bushings 326-03 12" FW Nozz. To Orig.Safe-end (TASCS)CS -12"X10" reducer MS Loop A -26" pipe to valve RR Loop A -4" sweepolet to cap (IGSCC)RR Loop A -12" safe-end to pipe (IGSCC/CRC)RR Loop A -28" safe-end to pipe (IGSCC)12" FW -safe-end to safe-end mod.(TASCS)12" FW -safe-end to safe-end mod. (TASCS)MS Loop A -26" elbow to pipeRR Loop B -12" elbow to'pipe (IGSCC)RR Loop A -12" safe-end to pipe (IGSCC/CRC)RR Loop A -28" pipe to elbow (IGSCC)Bushings 1 through 68 when disassembled CS-46-3536-5 UT 4 FER CS-46-3536-5 UT 4 FER CS-18-3052-5 UT 4 FER CS-5-5352-5 UT 4 FER 5357-5 UT 5 N/A 5356-5 UT 5 PDI-Alt SS-3-5357-5 UT 5 FER CS-46-3536-5 UT 4 FER CS-46-3536-5 UT 4 FER CS-5-5352-5 UT 4 FER SS-17-5358-5 UT 5 FER 5356-5 UT 5 PDI-Alt SS-3-5357-5 UT 5 FER10/20 10/28 10/28 10/19 10/24 10/13 N/A 10/20 10/10 10/22 10/22 10/13 10/28 10/26 10/29 N/A 10/26 10/14 10/27 10/27 10/25 10/29 10/27 10/30 N/A 10/27 10/23 10/27 10/27 10/27 RF12-21 RF12-22 RF12-23 RF12-24 Scope Deleted per CARD 07-26900 RF12-26 RF12-27 RF12-28 RF12-29 RF12-30 DW,210,642' DW,270,642' DW,240,641' DW, 6,589'DW,295,578' DW,270,615' DW,0,614'DW,210,642' DW,270,642' DW,20,589' DW,30, 615'DW,300,615' DW,0,614'Refuel Floor10/13 10/26 10/27 RF12-31 RF12-32 Scope Added per10/9 10/26 10/27 CARD 07-26347 Scope Deleted per N/A N/A N/A CARD 07-26347 5362-5 VT-1 15 N/A 9/30 10/25 11/5 RF12-101 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)17 RFI2EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI B-G-2 Bolting RRC Pump B Seal Bolts B21-FOlOA-VBB FBC-B21-5354-01H B21-F013H-VBB FBC-B21-5354-01 R B21-F013P-VBB

FBC-B21-5355-01 P B21-F013R-VBB B21-F022B-VBB B21-F022D-VBB E 11-F008-VBB E 11-F060A-VBB E21 F-007A-VBB E21-F007B-VBB G33-F101-VBB G33-F102-VBB 2" and Less Main RR Pump Seal Bolting FW MS MS MS MS MS MS MS MS RHR RHR CS CS RWCU RWCU 5365-5 VT-I 3537-5 VT-1 5354-5 VT-1 5354-5 VT-1 5354-5 VT-I 5355-5 VT-1 5355-5 VT-1 5354-5 VT-1 5353-5 VT-1 5355-5 VT-1 2299-5 VT-1 2298-5 VT-1 3052-5 Vr-1 3053-5 VT--I 3096-5 VT-1 5351-5 V-I1 15 15 15 15 15 15 15 15 15 15 15 15 15 15 15 15 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 10/25 10/14 10/16 10/16 10/16 10/16 10/16 10/16 10/2 10/2 10/2 10/19 10/19 10/19 10/4 10/2 10/26 10/29 10/14 10/29 10/18 10/29 10/18 10/29 10/18 10/29 10/18 10/29 10/18 10/29 10/18 10/29 10/11 10/27 10/12 10/27 10/12 10/27 10/26 10/29 10/26 10/29 10/26 10/29 10/12 10/27 10/12 10/27 RF12-102 RF12-92 RF12-93 RF12-93 RF12-94 RF12-95 RF12-95 RF12-94 RF12-81 RF12-82 RF12-83 RF12-98 RF12-99 RF12-100 RF12-91 RF12-84 DW,135,575'

DW,350,594' DW,323,613' DW,323,613' DW,289,613' DW,315,613' DW,315,613' DW,289,613' DW, 19,588'DW,354,588' RB1 3B12,591'DW,270,600' DW,245,636' DW, 125,636'DW,232,592' DW,245,582' Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)18 RF12 EXAMS CATICOMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI B-H Integral Attachments 8-319A 8-319B 8-319D B-K-1 Pump Integral SW-B31-5365-PUMP-A-WAB-0 Peripheral CRD CRDH-X02-Y39-W1 CRDH-X02-Y39-W2 C-A Vessel Welds SW-E11-D2-HX-05 SW-E11-D2-HX-11 C-C Integral Attachment SW-E 11-3151-4WE SW-E 11-3151-4WF SW-E 11-3151-4WG SW-E1 1-3151-4WH SW-E 11-3151-4WJ SW-E1 1-3151-4WK C-F-1 Augmented FW-C41-2979-17S18 FW-C41-2979-81S82 FW-C41-3361-1WF22 C-F-2 Piping FW-C1 1-2113-249-B RPV Attachment Welds Top Head Lifting Lug Top Head Lifting Lug Top Head Lifting Lug Piping Attachment WeldsPump integral Attachment Housing Welds CRD Housing Tube to Flange CRD Housing Tube to Tube Shell Circ Welds Head to Shell Weld Shell to Flange Weld Lug Attachment Welds RHR Piping Lug RHR Piping Lug RHR Piping Lug RHR Piping Lug RHR Piping Lug RHR Piping Lug NRC CommitmentSLC 1/2" Elbow to Pipe SLC -2" Pipe to ElbowSLC -3" Valve to Pipe Circumferential Weld CRD -8" Pipe -Elbow 5360-5 MT 2 N/A 10/4 10/26 10/27 5360-5 MT 2 N/A 10/4 10/26 10/27 5360-5 MT 2 N/A 10/4 10/26 10/27 5365-5 PT 1 N/A 10/8 10/10 10/11 5363-5 PT 1 N/A 10/15 10/24 10/24 5363-5 PT 1 N/A 10/10 10/14 10/13 5370-5 UT 3 CS-80 10/9 10/14 10/11 5370-5 UT 3 CS-80 10/11 10/26 10/30 RF12-33 RF12-34 RF12-35 RF12-36 RF12-37 RF12-38 RF12-39 RF12-40 RF12-41 RF12-42 RF12-43 RF12-44 RF12-45 RF12-46 RF12-47 RF12-48 RF-12-49 RF12-50 RPV Head 0 deg.RPV Head 90 deg.RPV Head 270 deg.DW,315,578' DW, Undervessel Dw, RPV skirt RB2, B9, 629'RB2, B9, 629'3151-5 3151-5 3151-5 3151-5 3151-5 3151-5 2979-5 2979-5 3361-5 MT MT MT MT MT MT PT PT PT 2 2 2 2 2 2 NA NA NA NA NA NA NA NA NA 10/4 10/4 10/4 10/4 10/14 10/14 10/14 10/14 10/18 10/18 10/18 10/18 10/4 10/14 10/18 10/4 10/14 10/18 RB1, B9, 587' RHR HX South, RB1, B9, 587' RHR HX South, RB1, B9, 587' RHR HX South, RB1, B9, 587' RHR HX South, RB1, B9, 587' RHR HX South, RB1, B9, 587' RHR HX South, RB1, B9, 587' RHR HX South, RB2,C1 1,630'RB4,F10, SLC Mezz.RB4,E10,661 RB1 ,B9,598 10/16 10/25 10/5 10/14 10/5 10/18 10/27 10/17 10/18 5372-5 MT 2 10/16 10/20 10/20 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)19

,RFI2"EXAMS CATICOMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI FW-C1 1-2113-249-B UT FW-E11-3154-4WO RHR -20" Tee to Valve 3154-5 MT FW-E11-3154-4WO UT FW-E11-3161-4WF5 RHR -18" Elbow to Pipe 3161-5 VT-1 FW-E11-3164-4W5 RHR -12" Elbow to Pipe 3164-5 UTFW-El 1-3164-4W5 MT FW-E11-4611-1W2 RHR -6" Elbow to Pipe 4611-5 VT-1 FW-E11-4611-1WF2 RHR -6" Pipe to Elbow 4611-5 VT-1 FW-E11-4612-3WF4 RHR -6" Pipe to Elbow 4612-5 VT-1 FW-E11-4612-4WF1 RHR -6" Pipe to Elbow 4612-5 VT-1 4 2 4 16 4 2 16 16 16 16 CS-82-FER 10/23 NA 10/24 PDI-Alt 10/25 NA 10/3 10/9 N/A 10/9 N/A 10/4 N/A 10/4N/A 10/19N/A 10/19 10/27 10/26 10/29 10/25 10/15 10/15 10/25 10/25 10/26 10/26 10/27 10/27 10/30 10/27 10/18 10/16 10/27 10/27 10/29 10/29 FW-E21-3148-0W8 CS -16" Pipe to Valve FW-E21-3148-0W8 HPCl -20" Elbow to FW-E41-3162-9WFO Valve 3148-5 UT 4 PDI-Alt 10/22 10/27 10/27 MT 2 N/A 10/22 10/26 10/27 3162-5 UT 4 PDI-Alt 10/15 10/25 10/27 FW-E41-3162-9WFO MT 2 N/A 10/15 10/26 10/17 RF12-51 RF12-52 RF12-53 RF12-87 RF12-54 RF12-55 RF12-90 RF12-89 RF1 2-96 RF12-97 RF12-56 RF12-57 RF12-58 RF12-59 RF12-60 RF12-61 RF12-62 RF1 2-63 RF12-64 RF12-65 RF12-66 RF12-67 RF12-88 RF12-68 RF12-69 RF12-70 RF12-71 Tor Rm,C1 7,546'Tor Rm,B11,572' RB2,B131,628' RB2 ,B10,632' RHR HX South RB2 ,B9,634' RHR HX South RB2,17,602' RHR HX North RB2 ,17,586' RHR HX North RBSB, G10, 555' CS South Tor Rm,G11,565' FW-E41-3167-1W2 HPCI -14" Elbow to Pipe 3167-5 MT FW-E41-3167-1W2 UT FW-E41-3172-0W8 HPCI -10" Valve to Pipe 3172-5 MT FW-E41-3172-0W8 FW-G41-3669-0W9 FPC 8" WOL -Elbow RHR 20" Expander to UT 3669-5 MT 2 4 2 4 2 2 4 2 16 N/A CS-39-FER N/A CS-18-FER 10/9 10/9 10/9 10/9 10/6 10/15 10/15 10/15 10/17 10/17 10/17 10/15 10/17 10/15 10/16 SW-E11-3157-1WB Pipe 3157-5 MT SW-E11-3157-1WB UT SW-E11-3161-1WH RHR -6" Elbow to Pipe 3161-5 MT SW-E11-3161-4WK RHR -18" Pipe to Elbow 3161-5 VT-1 SW-E21-3149-6WC CS -16" Pipe to Tee 3149-5 UT SW-E21-3149-6WC MT SW-N30-3258-13WJ MS -26" Pipe to Red. El 3258-5 MT SW-N30-3258-13WJ UT CS-42-FER 10/23 PDI-Alt 10/25 NA 10/6 N/A 10/3 10/24 10/27 10/14 10/25 10/27 10/27 10/17 10/27 HPCI,G10,552' HPCI,H 10,550'Tor Rm,B12,575' RBSB,A15,541' Tor Rm,B11,574' Tor Rm,B11,574' RBSB, G10,541'RB1 Stm, F12,590 4 PDI-Alt 10/4 2 PDI-Alt 10/4 2 N/A 10/3 CS-5-4 FER 10/310/20 10/26 10/14 10/18 10/15 10/16 10/15 10/18 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)20 RFI2 EXAMS CATCOMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI C-F-2 Piping SW-N30-3258-13WJLU SW-N30-3258-13WJLU C-F-2 Piping FW-E11-3146-15FW01 FW-E11-3157-4WF01 SW-E 11-3146-7WC Longitudinal Weld Intersecting Long Seam Branch Connections RHR 24" Weld to Pipe 20" Weld to Pipe 24"Weld to Pipe CS-5-3258-5 UT 4 FER 10/3 10/15 10/17 MT 2

N/A 10/3 10/15 10/17 RF12-72 RF12-73 RF12-74 RF12-75 RF12-76 RB1 Stm, F12,590 3146-5 MT 3157-5 MT 3146-5 MT 2 N/A 10/22 10/26 10/27 Tor Rm,B12,575' Tor Rm,B15,567' Tor Rm,B12,575' 2 2 N/A N/A 10/24 10/26 10/27 10/22 10/26 10/27 Procedure No.39.NDE.001 39.NDE.002 54-ISI-136 54-ISI-835 54-ISI-836 54-ISI-850 54-1SI-857

54-1SI-860 54-1SI-861 54-9054490 54-1SI-805 54-1SI-829 43.000.03/04 43.000.017 Cross Reference Code 1 2 3 4 5 6 7 8 9 10 11 12 13 14 Method PT MTVessel Welds

<2..PDI CS PDI-SSRPV Nozzle/

IR Auto DM Manual PA DM Manual PA CS/SRPV Shell Auto PDI-UT-6 RPV Man Manual DM PDI-UT-10 VT-3 Snubbers & Supports IWI Procedure No.43.000.014 43.000.019 43.000.013 ISI Prog. Part E. Att. 1 54-ISI-159 54-ISI-859 GE-UT-545 Cross Reference Code 15 16 17 18 19 20 21 Method VT-I1 Bolting Primary Cont Snubber Service Life RIISI Coverage JP Beam UT Shroud Phased Array UT JPDA UT Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)21 2.3 Interval 2, Period 3 RF11 Examinations RF11.EXAMS 1 --CAT/COMP ID B-A Reactor Vessel DESCRIPTION Reactor Vessel Shell Welds ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI 1-308A 1-308B 1-308C 1-308D 13-308 5-319 cl -306H 2-319-D Longitudinal Shell Weld 5360-5 Longitudinal Shell Weld 5360-5 Longitudinal Shell Weld 5360-5 Longitudinal Shell Weld 5360-5 Shell to Flange from Shell 5360-5 UT UT UT UT UT 25/26 25/26 25/26 25/26 25/26 D-70389 4/8/06 4/14/06 4/14/06 D-70389 4/7/06 4/14/06 4/14/06 D-70389 4/5/06 4/14/06 4/14/06 D-70389 4/6/06 4/14/06 4/14/06 D-70389 4/2/06 4/14/06 4/14/06 Closure Head Circumferential Bottom Head Meridional Closure Head Meridional Closure Head Meridional 2667-58-5360-5 UT 6 1 2667-59-5360-5 UT 6 1 2667-58-5360-5 UT 6 1 2667-58-5360-5 UT 6 1 2-319E B-D Reactor Vessel 4-318A 4-318B B-D Reactor Vessel 4/10/06 4/12/06 4/13/06 4/11/06 4/13/06 4/13/06 4/3/06 4/12/06 4/13/06 4/3/06 4/12/06 4/13/06 4/8/06 4/12/06 4/13/06 4/8/06 4/13/06 4/13/06 06-0409 06-0409 06-0409 06-0409 06-0409 RF-1 1-77 RF-1 1-78 RF-1 1-73 RF-11-72 RF-1 1-75 RF-1 1-76 Refuel Floor Annulus,260,605' Refuel Floor Refuel Floor Refuel Floor Refuel Floor RPV Internal RPV Internal RPV Internal RPV Internal RPV Internal Nozzle to Vessel Welds RPV Head Nozzle to Shell 5361-5 RPV Head Nozzle to Shell 5361-5 Nozzle Inner Bore Region UT 6 UT 6 2667-58-1 2667-58-1 RPV Nozzle Inside Radius 4-318A IRS 5361-5 VT-1 15 N/A 4/7/06 4/12/06 4/13/06 15 N/A 4/7/06 4/12/06 4/13/06 4-318B IRS B-F Class 1-Piping SW-El 1-2327-6WC B-G-1 Bolting 326-01 ( 23-45)326-02 (23-45))326-03 ( 23-45)RPV (23-45)RPV Nozzle Inside Radius 5361-5 RIISI Welds RHR -24" Pipe to Pipe (DM/IGSCC) 2327-5 Greater Than 2" RPV Closure Studs > 2" 5362-5 RPV Head Nuts > 2" 5362-5 RPV Washers &Bushings 5362-5 RPV Threads in Flange 5362-5 RF-1 1-80 RF-1 1-80 DW DW VT-1 SS-8-FER CS-07-UT 3 FER 4/11/06 4/13/06 4/13/06 UT VT-1 VT-1 UT 5 16 16 9 RPV Stud Cal. 3/31/06 4/2/06 4/4/06 N/A 4/2/06 4/7/06 4/10/06 N/A 4/4/06 4/7/06 4/12/06 CSCL- 3/28/06 4/2/06 4/4/06 RF-11-01 RF-1 1-02 RF-1 1-03 RF-1 1-04 RF-1 1-07 DW, 95, 600'Refuel Floor Refuel Floor Refuel Floor Refuel Floor Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)22 RF11 EXAMS CATICOMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/El 52-FER RRC Studs (1 through 16)RRC Washers Set (1-16)B-G-2 Bolting B21-FO13N-VBB B21-F022A-VBB B21-F028C-VBB B21-F032B-VBB B21-F076A-VBB B21-F076B-VBB B31-F023B-VBB B31-FO31B-VBB E11-F015B-VBB E 11-F608-VBB E41-F002-VBB E51-F013-VBB FBC-B21-5352-01 N G33-F106-VBB Spare Flange (ODeg)Spare Flange (180Deg)Instrumentation Nozzle B-J Class 1 Piping FW-E 11-2327-0W6 FW-E 11-2327-6W0 FW-G33-3096-6WF5 FW-N21-2336-16W19 Pump B Studs Pump B Nuts/Bush/Washers 2" and Less SRV Body/Bonnet Bolting MS Valve Bonnet Bolting MS Bonnet Bolting FW Bonnet Bolting FW Bonnet Bolting FW Bonnet Bolting Recirc. Valve Bonnet Bolting Recirc. Valve Bonnet Bolting RHR Valve Bonnet Bolting RHR Valve Bonnet Bolting HPCI Valve Bonnet Bolting RCIC Valve Bonnet Bolting SRV "N" Flange Bolting RWCU Valve Bonnet Bolting RPV Bolted ConnectionRPV Bolted Connection RPV Bolted Connection RIISI Welds RHR -24" Valve to Pipe RHR -24" Pipe to Tee (IGSCC)RWCU -4" Pipe to PipeFW -12" Reducer to Pipe 5365-5 5365-5 5352-5 5352-5 5354-5 3536-5 3537-5 3536-5 5359-5 5359-5 2327-5 2299-5 2297-5 3536-5 5352-5 5351-5 5361-5 5361-5 5361-5 UT VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-I VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 B31-Stud N/A NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 4/5/06 4/5/06 4/4/06 4/4/06 4/4/06 4/4/06 4/4/06 4/4/06 4/4/06 4/4/06 4/12/06 4/12/06 4/7/06 4/7/06 4/7/06 4/7/06 4/7/06 4/10/06 4/7/06 4/7/06 4/12/06 4/12/06 4/10/06 4/10/06 4/10/06 4/10/06 4/10/06 4/10/06 4/12/06 4/10/064/8/06 4/12/06 4/12/06 4/4/06 4/4/06 4/4/06 4/4/06 4/8/06 4/8/06 4/10/06 4/7/06 4/7/06 4/7/06 4/12/06 4/13/06 4/13/06 4/13/06 4/10/06 4/10/06 4/10/06 4/13/06 4/23/06 4/25/06 4/13/06 RF-11-05 RF-1 1-05 RF-1 1-08 RF-1 1-09 RF-11-10 RF-11-11 RF-11-12 RF-11-13 RF-11-14 RF-11-15 RF-11-16 RF-11-18 RF-11-19 RF-1 1-20 RF-1 1-21 RF-1 1-82 RF-1 1-82 RF-1 1-83 RF-11-24 RF-1 1-25 RF-1 1-26 RF-1 1-27 DW, 135, 579 DW, 135, 579 DW, 47, 612'DW, 5, 590'RB1-ST,F12,589' RB1-ST,F12,593' RB1-ST,F12,593' RB1-ST,F12,593' DW, 145, 574'DW, 110, 578'RB1, B12, 594'DW, 153, 608'DW, 0, 586'RB1,G12, 586'DW, 47, 612'DW,140, 572 RPV Head RPV Head RPV Head DW, 97, 600'DW, 93, 600'DW, 232, 591'DW,115, 608'CS-07-2327-5 UT 3 FER SS-08-2327-5 UT 4&22 FER 4/11/06 4/13/06 4/13/06 4/11/06 3096-5 UT 3537-5 UT 3 3 4/4/06 CS-15-FER 4/6/06 4/13/06 4/7/06 4/12/06 4/13/06 4/8/06 4/13/06 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)23 RFI1 EXAMS'CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L Ill ANII Report Loc/AzIE/FW-RD-2-Ai 1 B-J Piping Contd.FW-RD-2-B1 -Wi SW-G33-3096-5WD SW-G33-3096-5WH SW-RD-2-A3-W7 SW-RD-2-A4-W2 SW-RS-2-B1-W1 SW-RS-2-A3-W4 SW-RS-2-A3-W5 SW-RS-2-B3-W4 SW-RS-2-B3-W5 B-N-2 Vessel Interior Shroud Support Welds B-O Peripheral CRD CRDH-X02-Y35-W1 CRDH-X02-Y35-W2 Recirc. -12" SWOL to Pipe (IGSCC, CRC)RIISI Welds Recirc. -4" SWOL to Cap (IGSCC)RWCU -4" Pipe to Tee RWCU -6" Tee to Pipe Recirc -12" Cross to Pipe (IGSCC)Recirc- 12" Elbow to Pipe (IGSCC)Recirc -28" Elbow to Pipe (IGSCC)Recirc -4" SWOL to Pipe Recirc -4" Pipe to Flange Recirc -4" SWOL to Pipe Recirc -4" Pipe to Flange Interior Attachment Weld H-9 Shroud Support to Vessel Weld (17% of length min req. -12')CRD Housing Welds CRD Housing Tube to Flange CRD Housing Tube to Tube SS-17-5356-5 UT 22 & 28 FER SS-25-5359-5 UT 4 & 22 FER CS-24-3096-5 UT 3 FER CS-22-3096-5 UT 3 FER SS-10-5356-5 UT 4 & 22 FER SS-17-5356-5 UT 4 & 22 FER SS-03-5359-5 UT 4 & 22 FER4/8/06 4/13/06 4/13/064/6/06 4/12/06 4/12/06 4/3/06 4/7/06 4/8/06 4/4/06 4/7/06 4/8/064/6/06 4/12/06 4/13/06 4/6/06 4/12/06 4/12/064/8/06 4/12/06 4/13/06 RF-1 1-28 RF-1 1-29 RF-1 1-30 RF-11-31 RF-1 1-32 RF-1 1-33 RF-1 1-34 RF-1 1-68 RF-11-69 RF-1 1-70 RF-11-71 RF-11-81 DW, 240, 603'DW, 130, 578'DW, 229,591'DW, 229,591'DW, 270, 603'DW, 210, 615'DW, 180, 613'DW, 335, 575'DW, 335, 575'DW, 145, 575'DW, 145, 575'RPV Internal 5357-5 5357-5 5359-5 5359-5 PT/UT PT/UT PT/UT PT/UT 1 &4 1 &4 1 &4 1&4 15/23 SS-25-FER SS-25-FER SS-25-FER SS-25-FER 4/3/06 4/1/06 3/29/06 3/29/06 4/12/06 4/2/06 3/29/06 3/29/06 4/13/06 4/7/06 3/29/06 3/29/06 UT/VT Rl-52 -3 NA 4/7/06 4/12/06 4/13/06 5363-5 PT 1 NA 4/8/06 4/12/06 4/12/06 5363-5 PT 1 NA 4/8/06 4/12/06 4/12/06 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)24 RF-11-35 RF-1 1-36 DW-UV, DW-UV, RFl1 EXAMS I CATICOMP ID C-A Pressure Vessel Welds SW-E11-D2-HX-05 C-B Nozzle Welds SW-E11-D2-HX-10 SW-E11-D2-HX-10 SW-E11-D2-HX IRS C-C Integral Attachment SW-E11-D2-HXS-l7 SW-E11-D2-HXS-18 SW-E11-D2-HXS-19 SW-E 11 -D2-HXS-20 SW-E 11 -D2-HXS-21 SW-E11 -D2-HXS-22SW-E11 -D2-HXS-23

SW-E11 -D2-HXS-24 C1 1-50-2113-G262A Cl 1-50-2113-G262B Cl 1-50-2113-G262C Cl 1-50-2113-G262D Cl 1-50-2113-G262E Cl 1-50-2113-G262F C1 1-50-2113-G262G C1 1-50-2113-G262H C-F-1 Augmented FW-C41-2979-50S51 FW-C41-3361-1WF25 FW-C41-5058-65S66 C-F-2 Piping FW-El 1-3146-OW1 FW-El 1-3146-OW1 DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI Shell Circ Welds CS-80-UT 27 FER RHR HX Circ. Head Weld Nozzle to Shell RHR HX Nozzle to Shell RHR HX Nozzle to Shell Lugs & Attachment Welds RHR Lugs (90 deg -270 deg)5370-54/10/06 4/12/06 4/13/06 5370-5 UT MT 27 2 CS-80-FER 4/10/06 4/10/06 CS-81-FER 4/11/064/11/06 4/13/06

4/11/06 4/13/06 4/13/06 4/13/06 5370-5 UT 24 5370-5 MT 2 NA 4/18/06 4/15/06 4/24/06 RHR Lugs RHR Lugs RHR Lugs RHR Lugs RHR Lugs RHR Lugs RHR Lugs SDV Lugs SDV Lugs SDV Lugs SDV Lugs SDV Lugs SDV Lugs SDV Lugs SDV Lugs NRC Commitment 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5375-5 5375-5 5375-5 5375-5 5375-5 5375-5 5375-5 5375-5 MT MT MT MT MT MT MT MT MT MT MT MT MT MT MT 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 NA NA NA NA NA NA NA NA NA NA NA NA NA NA NA 4/18/06 4/18/06 4/18/06 4/18/06 4/18/06 4/18/06 4/18/06 3/30/06 3/30/06.3/30/06 3/30/06 3/30/06 3/30/06 3/30/06 3/30/06 4/15/06 4/15/06 4/15/06 4/15/06 4/15/06 4/15/06 4/15/06 4/2/06 4/2/06 4/2/06 4/2/06 4/2/06 4/2/06 4/2/06 4/2/06 4/24/06 4/24/06 4/24/06 4/24/06 4/24/06 4/24/06 4/24/06 4/4/06 4/4/06 4/4/06 4/4/06 4/4/06 4/4/06 4/4/06 4/4/06 RF-11-37 RF-1 1-38 RF-11-38 RF-1 1-39 RF-1 1-40 RF-1 1-40 RF-1 1-40 RF-1 1-40 RF-1 1-40 RF-1 1-40 RF-1 1-40 RF-1 1-40 RF-1 1-41 RF-1 1-41 RF-1 1-41 RF-1 1-41 RF-1 1-41 RF-1 1-41 RF-1 1-41 RF-1 1-41 RF-11-42 RF-11-43 RF-11-44 RF-1 1-45 RF-11-45 RB2, B9, 629'RB2, B9, 619'RB2, B9, 619'RB2, B9, 623'RB2, B9, RB2, B9, RB2, B9, RB2, B9, RB2, B9, RB2, B9, RB2, B9, RB1, C1O, 589'RB1, C1O, 589'RB1, C1O, 589'RB1, C1O, 589'RB1, C1O, 589'RB1, C1O, 589'RB1, C1O, 589'RB1, C1O, 589'RB2, CIO, 632'RB3, ElO, 659'RB3, F10, 662'RB1, C16, 611'SBLC -2" Elbow to Pipe SBLC -3" Pipe to Tee SBLC -2" Valve to Pipe Circumferential Weld RHR -20" Nozzle to Pipe 2979-5 PT 1 NA 3/27/06 4/2/06 4/4/06 3361-5 PT 1 NA 3/27/06 4/2106 4/4/06 5374-5 PT 1 NA 3/27/06 4/2/06 4/4/06 3146-5 MT 2 NA CS-42-UT 3 FER4/1/06 4/12/06 4/12/064/1/06 4/12/06 4/12/06 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date:

1-23-88 NB No. 21085 (RPV)25 RF11 EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/El FW-E 11-3151 -1 OWO FW-El1-3151-10WO FW-E 11-3160-0W2 FW-E 11-4612-9W0 FW-E41-3163-8W0 FW-E41-3163-8W0 FW-E41-3167-9W0 FW-E41-3167-9W0 SW-Cl 1-2113-303-A SW-Cl 1-2113-303-A SW-E1 1-3158-4WD SW-El 1-3158-4WD SW-El 1-3158-8WG SW-El1-3158-8WG SW-El 1-3177-6WD SW-El 1-3177-6WD SW-E21-3147-15WF SW-E21-3147-15WF SW-E21-3149-6WL SW-E21-3149-6WL SW-T48-04-2095-5WD SW-T48-04-2095-WSW3 SW-T48-04-2097-20WD C-F-2 Piping SW-E21-3144-5WE RHR -24" Elbow to Valve 3151-5 MT UT VT-I 2 3 4/11/06 CS-09-FER 4/11/06 4/13/06 4/13/06 4/13/06 4/13/06 RHR -18" Valve to Elbow RHR -8" Exp to WOL HPCI -16" Red El to Pump HPCI -14" Pipe to Valve SDV -12" Elbow to Pipe RHR -20" Elbow to Pipe RHR -20" Pipe to Pipe RHR -20" Elbow to Pipe CS -14" Pipe to Elbow CS-16" Elbow to Pipe CGC -6" Elbow to Pipe CGC -Tee to Red. El CGC -8" Pipe to Tee Branch Connections CS-14" WOL to Pipe 3160-5 17 4/1/06 4/2/06 4/7/06 4612-5 VT-1r 3163-5 MT UT 3167-5 MT UT 5372-5 MT UT 3158-5 MT UT 3158-5 MT UT 3177-5 MT UT 3147-5 MT UT 3149-5 MT UT 2095-5 MT 2095-5 MT 3258-5 MT 4/1/06 3/30/06 Alt. 1 3/30/06 4/7/06 Alt. 1 4/7/06 3/31/06 CS-38 3/31/06 3/31/06 CS-42-FER 3/31/06 4/11/06 CS-42-FER 4/11/06 3/30/06 CS-42-FER 3/30/06 3/27/06 Alt. 1 3/27/06 3/31/06 Alt. 1 3/31/06 3/27/06 3/30/06 3/30/06 4/12/06 4/2/06 4/2/06 4/12/06 4/12/06 4/2/06 4/2/06 4/12/06 4/12/06 4/13/06 4/13/06 4/2/06 4/2/06 4/2/06 4/2/06 4/2/06 4/2/06 4/2/06 4/2/06 4/2/06 4/12/06 4/4/06 4/4/06 4/13/06 4/13/06 4/7/06 4/7/06 4/12/06 4/12/06 4/13/06 4/13/06 4/4/06 4/4/06 4/10/06 4/10/06 4/6/06 4/6/06 4/4/06 4/4/06 4/4/06 RF-1 1-46 RF-11-46 RF-11-47 RF-11-48 RF-11-49 RF-1 1-49 RF-11-50 RF-11-50 RF-11-51 RF-11-51 RF-1 1-52 RF-1 1-52 RF-1 1-53 RF-1 1-53 RF-1 1-54 RF-1 1-54 RF-1 1-55 RF-1 1-55 RF-1 1-56 RF-1 1-56 RF-1 1-57 RF-1 1-58 RF-1 1-59 RF-1 1-60 RB1, B12, 594'Tor, B13, 575'Tor, C13, 574'HPCI, H9, 546'RB1, G12, 587'RB1, B13, 597'RB2, C17, 631'RB2, C9, 631'RB-SB,B1 0,544'RB1, E11, 598'RB-SB,F10,550' RB2, 89, 629'RB2, B9, 619'RB2, B9, 619'3144-5 MT 2 3/29/06 3/29/06 3/29/06 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)26 CRF11 EXAMS CATICOMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/AzIEI ANSI B31.1 FW-N20-3105-0W21 SW-N20-03-B009-BWSE FW-N21-3109-29W0 SW-N21-01-BO01-AWSE GL 88-01 Category D FW -20" Safe End to Pipe 3105-1 FW -20" Nozzle to Safe 3105-1 End FW -24" Safe End to Pipe 3109-1 FW -24" Nozzle to Safe 3109-1 End Vol.UT 3 UT 3SSCL-88 4/11/06 4/13/06 4/13/06 SSCL-88 4/11/06 4/13/06 4/13/06 SSCL-87 4/10/06 4/12/06 4/13/06 SSCL-87 4/10/06 4/12/06 4/13/06 RF-1 1-62 RF-1 1-63 RF-1 1-64 RF-1 1-65 TB2, P11,625'TB2, P11,625'TB3, P10, 650'TB3, P10, 650'UT UT 3 3 Procedure No.39.NDE.001 39.NDE.002 PDI-UT-1 PDI-UT-2 PDI-UT-5 GE-UT-300 GE-UT-704 GE-UT-705 GE-UT-308 GE-UT-209 GE-UT-245 GE-UT-504 PDI-UT-10 43.000.03/04 43.000.017 Cross Reference Code Method Procedure No.Cross Reference Code Method 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 PT MT PDI CS PDI SS PDI Bolting PDI Manual RPV GERIS GERIS Threads in Flange Auto N-SE Auto CRC UT JPB Manual DM VT-3 Snubbers & Supports IWI 43.000.014 43.000.019 43.000.013 39.NDE.015 GE-UT-309 GE-UT-311 ISI Prog. Part E. Aft. 1 GE-UT-319 GE-UT-301 lSwT-PDI-1 lSwT-PDI-2 GE-UT-321 GE-UT-105 GE-UT-605 16 17 18 19 20 21 22 23 24 25 26 27 28 29 VT-1 Bolting Primary Cont Snubbers Longseams Inner Radius Sizing Manual Inner Radius RIISI Coverage H-9 Manual UT Vessel UT < 2" T AIRIS Auto AIRIS Sizing RHR Vessel IR UT Non-PDI / CRC Straight Beam UT Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)27 2.4 Interval 2, Period 2, RF 10 Examinations RF1C EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD) COMP L III ANII Report Loc/Az/EI B-A Reactor Vessel I 5-308A RPV Shell Welds Shell Longitudinal Weld 5360-5 UT 7 2667-62 11/21/04 11/26/04 11/27/04 15-308B 2-307B 2-308A 1-319E 1-319F 1-306B 1-306C 3-319 Ind. 124 Successive Exam 5360-5 Shell Longitudinal Weld 5360-5 Shell Longitudinal Weld 5360-5 Closure Head Meridional 5360-5 Closure Head Meridional 5360-5 Bottom Head Meridional 5360-5 Bottom Head Meridional 5360-5 Head-to-Flange Weld 5360-5 Head-to-Flange Weld 5360-5 Circumferential Bottom Head 5360-5 UT UT 7 7 2667-62 11/12/04 11/19/04 11/20/04 2667-60 11/20/04 11/27/04 11/27/04 UT 7 2667-60 11/20/04 11/27/04 11/27/04 UT 6 2667-58 11/8/04 11/24/04 11/24/04 UT UT UT UT MT UT 6 6 6 6 2 6 2667-58 2667-59 2667-59 2667-58 11/10/04 11/24/04 11/24/04 11/17/04 11/22/04 11/27/04 11/16/04 11/24/04 11/27/04 11/14/04 11/26/04 11/27/04 RF-10-09 RF-10-10 RF-10-12 RF-10-13 RF-10-04 RF-10-05 RF-10-02 RF-10-03 RF-10-16 RF-10-16 RF-10-17 RF-10-07 RF 11 RF-10-08 RF-10-14 3-319 6-306 DW,84,620' N/A 11/17/04 11/26/04 11/27/04 2667-59 11/17/04 11/24/04 11/27/04 B-D Reactor Vessel 13-314C Nozzle to Vessel Welds Recite Inlet Nozzle Jet Pump Inst. Nozzle C.S. Nozzle 5361-5 UT 8 2667-60 11/22/04 11/25/04 11/27/04DW, 172,620-DW,104,610' DW,60,646' Refuel FloorRefuel Floor DWUV,40,604 DWUV,77,604 Refuel Floor Refuel Floor DWUV,604'DW,90,615' DW,97,615' DW,120,641'Refuel Floor Invess,90 lnvess,97Refuel Floor DW, 120,641'19-314A 14-316 A 5361-5 UT 5361-5 UT 6 & 21 2667-60 11/20/04 11/24/04 11/27/04 8 2667-62 11/24/04 11/25/04 11/27/04 2-318 Head Vent Nozzle5361-5 UT 6 & 21 2667-58 11/15/04 11/24/04 11/27/04 B-D Reactor Vessel13-314C IRS 19-314A IRS 2-318 IRS B-F Class 1-Piping N-5A Nozzle Inner Bore Region Recirc Inlet Nozzle Jet Pump Inst. Nozzle Head Vent Nozzle5361-5 VT 15 1-mil wire * * * *Completed Invessel VT's Under Job 11090403285361-5 VT 15 1-mil wire * * * *Completed Invessel VT's Under Job 1109040328 5361-5 VT-i 15 VT-1 * * * *Completed Invessel VT's Comparator tInder Job I 109040328 RIISI Welds CS Noz to SE (IGSCC,CC) 3053-5 UT 10 & 22 CS44/IN45 11/12/04 11/21/04 11/23/04 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)28 RF-10-55 RF1O~EXAMS

... ~ :~. -..~ ,;. 7;. :1 K <.>CAT/COMP ID SW-E21-3053-4WOX 101-304-E B-J Class I-Piping FW-PS-2-C3 SW-PS-2-C3-A SW-PS-2-C3-C SW-PS-2-C3-D FW-G33-3096-8W9 FW-G33-3096-8W1 1 FW-G33-3096-9WF1 SW-N21-2336-13WC FW-N21-2336-13W14 FW-N21-2336-14WF1 SW-N21-2336-13WE DESCRIPTION CS Safe-End to Ext.(IGSCC)3053-5 RRI Noz to SE (IGSCC)RIISI Welds Main Steam- Loop C 26" Pipe to Elbow Main Steam- Loop C 26" Elbow to Pipe Main Steam- Loop C 8" Sweepolet to Pipe Main Steam- Loop C 8" Pipe to Flange RWCU 6" Pipe to Tee RWCU 6" Pipe to Tee RWCU 6" Elbow to Pipe Feedwater 20" Elbow to Tee Feedwater 12" Tee to Elbow Feedwater 12" Pipe to Elbow Feedwater 20" Tee to Pipe ISO Exams Procedure CAL STD COMP L III ANII Report Loc/AzIEl 3053-5 5358-5 5354-5 5354-5 5354-5 5354-5 5351-5 5351-5 5351-5 3537-5 3537-5 3537-5 3537-5 UT UT 10 & 22 10&22 UT UT UT UT UT UT UT UT UT UT UT CS44/1N45 SS-56/CSCL-54 CS-5 CS-5 CS-20 CS-20 CS-22 CS-22 CS-22 CS-11 CS-15 CS-15 CS-11 11/11/04 11/14/04 11/12/04 11/11/04 11/10/04 11/9/04 11/8/04 11/8/04 11/9/04 11/12/04 11/12/04 11/11/04 11/16/04 11/22/04 11/19 11/14/04 11/14/04 11/19/04 11/13/04 11/13/04 11/13/04 11/14/04 11/13/04 11/14/04 11/17/04 11/20/04 11/27/04 11/24/04 11/16/04 11/18/04 11/21/04 11/20/04 11/27/04 11/16/04 11/27/04 11/27/04 11/27/04 11/18/04 11/21/04 RF-10-61 RF-10-01 RF-10-50 RF-10-78 RF-10-79 RF-10-80 RF-10-44 RF-10-43 RF-10-45 RF-10-70 RF-10-48 RF-10-49 RF-10-71 DW,120,641' DW,150,615' DW,260,2 12'DW,260,608' DW,282,609' DW,282,610' DW,240,572' DW,250,572' DW,140,572' DW,25,608 DW,30,61 1I DW,30,614 DW,35,608 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)29

[R-10 EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI FW-RD-2-B 19 B-G-1 Bolting 326-01 (Closure Studs)

Base Scope B-G-2 Bolting RRC Pump A Seal Bolts B21 -F028A-VBB FBC-B21-5353-01F B21-FO13F-VBB FBC-B21-5353-01C B21-FO13C-VBB FBC-B21-5354-01E B21-FO13E-VBB B21-F022C-VBB Ell-F060B-VBB E41-F006-VBB G33-FIOO-VBB G33-F220-VBB B-G-2 Emergent CRD Flange Bolts CRD Bolting Reactor Recirc -12" Pipe toSafe-end (IGSCC, CRC) 5358-5 UT 11 &22 SS-17 11/11/04 11/23/04 11/24/04 RF-10-51 DW,150,615 Greater Than 2" 1/3 of locations (1-22)5362-5 UT 5 RPV Stud Cal 11/7/04 11/13/04 11/16 RF-10-15Refuel Floor 2" and Less Main RR Pump Seal Bolting MS Valve Bonnet BoltingSRV Flange BoltingSRV Body to Bonnet Bolting SRV Flange BoltingSRV Body to Bonnet Bolting SRV Flange BoltingSRV Body to Bonnet Bolting MS Valve Bonnet Bolting RHR Valve Bonnet BoltingHPCI Valve Bonnet Bolting RWCU Valve Bonnet Bolting RWCU Valve Bonnet Bolting 2" and Less When DisassembledNew Bolting RPV Attachment Welds Top Head Lifting Lug RPV Attachment Welds 5365-5 5352-5 5353-5 5353-5 5353-5 5353-5 5354-5 5353-5 5354-5 2327-5 3537-5 5351-5 3536-5 N/A N/A VT-i VT-I VT-1 VT-1 VT- I VT-1 VT- 1 VT-1 VT-I VT-i VT-i VT-I VT-I 16 16 16 16 16 16 16 16 16 16 16 16 16 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 11/10/04 11/10/04 11/9/04 11/9/04 11/9/04 11/9/04 11/11/04 11/11/04 11/12/04 11/13/04 11/10/04 11/14/04 11/15/04 11/13/04 11/13/04 11/13/04 11/13/04 11/13/04 11/13/04 11/13/04 11/13/04 11/17/04 11/17/04 11/13/04 11/17/04 11/17/04 11/27/04 11/27/04 11/27/04 11/27/04 11/27/04 11/27/04 11/24/04 11/27/04 11/24/04 11/24/04 11/24/04 11/27/04 11/27/04 RF-10-60 RF-10-23 RF-10-31 RF-10-21 RF-10-30 RF-10-19 RF-10-32 RF-10-20 RF-10-22 RF-10-28 RF-10-29 RF-10-53 RF-10-54 RF-10-25 RF-10-24 RF-10-18 DW,315,580' Stm,5,589' DW,78,612' DW,78,612' DW,46,612' DW,46,612' DW,290,612 DW,290,612 DW,343,590' DW,90,600' STM,G12,587' DW,320,572' STM,F12,586 DW,UV As requested Refuel Floor VT-I 16 VT-I 16N/A 11/18/04 11/25/04 11/27/04N/A 11/4/04 11/5/04 11/24/04 B-Hl Integral Attachments 8-319-C5360-5 MT 2 N/A 11/8/04 11/13/04 11/27/04 B-K IntegralAttachments Piping Attachment Welds SW-N21-2336-20WB SW-N21-2336-20WC Feedwater Loop B Feedwater Loop B 3537-5 MT 3537-5 MT 2 2 N/A 11/13/04 11/17/04 11/27/04 N/A 11/13/04 11/17/04 11/27/04 RF-10-72 RF-10-73 DW,150,613' DW, 150,613'Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)30 IRF1O EXAMS'CAT/COMP ID SW-N21-2336-20WD SW-N21-2336-20WE B-N-1 Vessel Interior Sample Holders DESCRIPTION Feedwater Loop B Feedwater Loop B ISO 3537-5 3537-5 Exams MT MT Procedure 2 2CAL STD N/A N/A COMP 11/13/04 11/13/04 L III 11/17/04 11/17/04 ANII 11/27/04 11/27/04 Report RF-10-74 RF-10-75 Loc/AzJEI DW,150,613' DW,150,613' RPV Attachment Welds Vessel Interior VT-3 B-N-2 Vessel Interior Interior Attachment WeldSurveillance Specimen Bracket 15 N/A *Completed Invessel VT's Under Job 1109040328 15 N/A *Completed Invessel VT's Under Job 1109040328 VT-1 B-O Peripheral CRD CRDH-/X02-Y31 -W1 CRDH-/X02-Y3 1-W2 Housing Welds CRD Housing Tube to Flange 5363-5 CRD Housing Tube to Tube 5363-5 PT PT 1 1 N/A 11/13/04 11/17/04 11/27/04 N/A 11/12/04 11/19/04 11/23/04 RF-10-26 RF-10-27 DW, UV Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, M! 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)31 RF1O EXAMSCI CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD) COMP L III ANII Report Loc/Az(Il C-C Integral Attachment PSFW-E41-3167-1WE PSFW-E41-3167-1WF PSFW-E41-3167-1WG PSFW-E41-3167-1WH C-F-1 Augmented FW-C41-2979-L FW-C41-2979-11 S 12 C-F-2 Piping SW-El 1-3146-6WE SW-El 1-3146-6WE FW-E11-3151-7W1 FW-E11-3151-7W11 SW-El 1-3161-4WB SW-G41-3669-3WB FW-E1 1-4612-4W5 FW-EI 1-4612-7W8 FW-El 1-4612-8WF3 FW-E21-3144-0W4

FW-E21-3144-0W4 FW-E21-3145-1 IWO SW-E21-3147-15WG SW-E21-3147-15WG SW-E41-3162-1WU SW-E41-3162-1WU FW-E41-3162-1 W2 Lug Attachment Welds HPCI 14" Pipe Lug HPCI 14" Pipe Lug HPCI 14" Pipe Lug HPCI 14" Pipe Lug NRC Commitment SIC 2" Pipe to Elbow SLC 2" Pipe to Elbow Circumferential Weld RHR 24" Pipe to Tee RHR 20" Tee to Pipe RHR 18" Elbow to Pipe RHR-FPC 8" Elbow to Pipe RHR 6" Pipe to Elbow RHR 6" Elbow to Pipe RHR 6" Elbow to Pipe CS 12" Pipe to Valve CS 10" Pipe to Weldolet CS 14" Elbow to Pipe HPCI 20" Pipe to Elbow HPCI 20" Elbow to Pipe 3167-5 3167-5 3167-5 3167-5 MT MT MT MT 2 2 2 2 N/A N/A N/A N/A 11/5/04 11/5/04 11/5/04 11/5/04 11/14/04 11/14/04 11/14/04 11/14/04 11/17/04 11/17/04 11/17/04 11/17/04 2979-5 PT 2979-5 PT 1 1 N/A 11/2/04 11/19/04 11/27/04 N/A 11/2/04 11/19/04 11/27/04 3146-5 MT 2 N/A3146-5 UT

-3 CS-423151-5 MT 2 N/A 3151-5 UT 3 CS-42 3161-5 VT-i 17 N/A3669-5 MT 2 N/A 4612-5 VT-i 17 N/A 4612-5 VT-i 17 N/A 4612-5 VT-1 17 N/A3144-5 MT 2 N/A3144-5 UT 3 PDI-Alt-CS-i 3145-5 MT 2 N/A3147-5 MT 2 N/A 3147-5 UT 3 PDI-Alt-CS-i 3162-5 MT 2 N/A 3162-5 UT 3 PDI-Alt-CS-13162-5 MT 2 N/A 11/14/04 11/14/04 11/11/04 11/12/04 11/2/04 11/3/04 11/1/04 11/1/04 11/1/04 11/14/04 11/14/04 11/3/04 11/4/04 11/5/04 11/21/04 11/21/04 11/19/04 11/19/04 11/13/04 11/14/04 11/13/04 11/13/04 11/13/04 11/21/04 11/21/04 11/19/04 11/13/04 11/13/04 11/22/04 11/22/04 11/27/04 11/27/04 11/17/04 11/17/04 11/27/04 11/27/04 11/18/04 11/23/04 11/23/04 11/21/04 11/20/04 11/20/04 RF-10-56 RF-10-57 RF-10-58 RF-10-59 RF-10-34 RF-10-33 RF-10-63 RF-10-63 RF-10-35 RF-10-35 RF-10-64 RF-10-67 RF-10-36 RF-10-37 RF-10-38 RF-10-39 RF-10-39 RF-10-40 RF-10-65 RF-10-65 RF-10-66 RF-10-66 RF-10-41 HPCI, G10,546'RB2,D1 1,635'RB2, C 11,630'Tor,B 12,575'Tor, B12,575'Tor,B 11,575'RB1,B1i1,585' RBI,B17,585' Tor,B 15,574'Tor,1B15,574' RBSB,F16,540' NE Quad,578'RB1,DI 1,601'HPCI, G10,548'HPCI,G1O,550' 11/15/04 11/23/04 11/27/04 11/15/04 11/23/04 11/27/04 11/15/04 11/19/04 11/21/04 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)32

'R1:0 .EXAMS j CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI FW-E41-3162-1W2 3162-5 UT 3 PDI-Alt- 11/15/04 11/19/04 11/21/04 RF-10-41 HPCI Rm SW-E41-3162-2WC SW-E41-3162-2WC FW-E41-3172-OW 1 FW-E41-3172-OWl SW-N30-3258-1WJ SW-N30-3258-1WJ FW-T48-04-2095-7W8 SW-T48-04-2097-18WC SW-N30-3258-1WJLU C-F-2 PipingSW-El 1-3146-5WM HPCI 20" Elbow to Pipe HPCI 10" Valve to Pipe MS 26" Pipe to 24" Reducer CGC 6" Elbow to Pipe CGC 8" Expander to PipeIntersecting Long Seam Weld 3162-5 MT 3162-5 UT 3172-5 3172-5 3258-5 3258-5 2095-5 2097-5 3258-5 MT UT MT UT MT MT MT/UT 2 3 2 3 2 3 2 2 2, 3 CS-1 N/A PDI-Alt-CS-1 N/A CS-18 N/A CS-5 N/A N/A CS-5 11/23/04 11/23/04 11/17/04 11/17/04 11/17/04 11/17/04 11/3/04 11/5/04 11/17/04 11/23/04 11/23/04 11/20/04 11/20/04 11/21/04 11/21/04 11/14/04 11/14/04 11/21/04 11/24/04 11/24/04 11/21/04 11/21/04 11/27/04 11/27/04 11/17/04 11/17/04 11/27/04 RF-10-96 RF-10-96 RF- 10-42 RF-10-42 RF-10-76 RF- 10-76 RF-10-52 RF- 10-8 1 RF- 10-76 RF-10-62 HPCI Rm Stm,E12,586' Stm,FI 1,589'RB2,A12, 625'RB1,C13,587' Stm,Fl 1,589'Tor, B13 ,575'Branch Connections RHR 24" Pipe to 12" Weldolet 3146-5 MT 2 N/A 11/18/04 11/21/04 11/22/04 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)33

[kVIO'EXAMS

., .. .: -CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/El ANSI B31.1 FW-N20-3107-OW1 SW-N20-03-B013-BWSE FW-N20-3105-24W0 SW-N20-03-BO13-AWSE GL 88-01 Category D FWH 5N Upper Safe-end to El 3107-1 FWH 5N UpperNozz to Safe- 3107-1 end FWH 5N Lower Safe-end to El 3105-1 FWH 5N Lower Nozz to Safe- 3105-1 end Vol.UT UT UT UT 4 4 4 4 SSCL-88 11/19/04 11/22/04 11/23/04 SSCL-88 11/19/04 11/22/04 11/22/04 SSCL-88 11/19/04 11/22/04 11/22/04 SSCL-88 11/19/04 11/22/04 11/22/04 RF-10-47 RF-10-69 RF-10-46 RF-10-68 TB2,R12,624'

TB2,R12,624' TB2,R12,615' TB2,R12,615' Procedure 39.NDE.001 39.NDE.002 PDI-UT- 1 PDI-UT-2 PDI-UT-5 GE-UT-300 GE-UT-704 GE-UT-705 GE-UT-308 GE-UT-209 GE-UT-245 GE-UT-504 PDI-UT- 10 43.000.03/04 43.000.017 43.000.014 43.000.019 43.000.013 39.NDE.015 GE-UT-309 GE-UT-311 ISI Prog. Part E. Att. 1 Reference Code 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 Method PT MT PDI CS PDI SSPDI BoltingPDI Manual RPV GERIS GERIS Flange Threads Auto N-SE Auto CRC UT JPB Manual DM VT-3 Snubbers & Supports 1VVI VT-I Bolting Primary Cont Snubbers Longseams Inner Radius SizingManual Inner Radius RIISI CoverageLiquid Penetrant Magnetic Particle PDI Ferritic Pipe UT PDI Austenitic Pipe UT PDI Bolting UTMan. Vess.

Assy Welds GERIS Vess. Welds GERIS Nozz. Welds Flange Ligaments UT Automated DM Weld UT Automated CRC Weld UT JPB PDI DM UT Snubber/Hanger Vis.IVVI Bolting VisualContainment Visual Snubber Service Life Generic UT GERIS Nozz/IR Sizing Man. Noz/IR UT Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)34 2.5 Interval 2, Period 2, RF09 Examinations RF09 EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/El B-A Reactor Vessel 1-306J 1-319D 15-308B 2-307C 2-308B 4-319 2-307A B-D Reactor Vessel 13-314E 13-314F 15-315 4-316C B-D Reactor Vessel 13-314D IRS 13-314E IRS Shell & Head Welds Bottom Head Meridional Closure Head Meridional Shell Longitudinal Weld Shell Longitudinal Weld Shell Longitudinal Weld Closure Head Circ Weld Shell Longitudinal Weld Nozzle to Vessel Welds Recirc Inlet Nozzle Recirc Inlet Nozzle CRD Return NozzleFeedwater Nozzle Nozzle Inner Bore Region Recirc Inlet Nozzle Recirc Inlet Nozzle 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 UT UT UT UT UT UT UT 6 2667-59 6 2667-58 7 2667-62 7 2667-60 7 2667-60 6 2667-58 7 2667-60 4/6 3/31 4/4 4/4 4/5 4/9 4/8 4/8 4/2 4/10 4/7 4/9 4/10 4/12 4/16 4/11 4/15 4/14 4/14 4/16 4/14 4/14 4/14 4/14 4/14 RF-09-01 RF-09-02 RF-09-05 RF-09-08 RF-09-09 RF-09-13 RF-09-106 RF-09-03 RF-09-04 RF-09-06 RF-09-12Bio, 300,604'Refuel Floor DW,172,620' DW,218,610' DW,180,646' Refuel Floor DW,340,610' DW,150,615' DW,210,615' Auto UT DW,145,638' DW,150,642' 5361-5 UT 8 2667-60 4/6 4/11 5361-5 UT 8 2667-60 4/7 4/10 5361-5 UT 6 & 20 2667-60 4/8 4/9 5361-5 UT 8 2667-60 4/7 4/11 5361-5 5361-5 VT VT 15 15 1-mil wire 1 -mil wire*4/16 *4/27

5/13 *Completed under IVVISurveillance Event 1109*4/18 *4/27 *5/13 *Completed under IVVISurveillance Event 1109 Invess, 120, Invess, 150 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date:

1-23-88 NB No. 21085 (RPV) 35 CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANJI Report Loc/Az/El 13-314F IRS 13-314G IRS 13-314K IRS B-F Class 1-Piping N-9 2-303G B-J Class 1-Piping FW-RD-2-A 16 SW-RS-2-A2-WI FW-E1 1-2299-2WF3 SW-E21-3053-3WN SW-E21-3053-3WP FW-E51-2192-1 W2 FW-E51-2192-2W3 SW-N21-2336-IWD SW-N21-2336-IWU SW-N21-2336-1WL SW-N21-2336-3WC FW-N21-2336-3W4 Recirc Inlet Nozzle Recire Inlet Nozzle Recirc Inlet Nozzle RIISI Welds CRD Return Cap (IGSCC)RRI Noz to SE (IGSCC)5361-5 5361-5 5361-5 5361-5 5356-5 VT VT VT 15 15 15 1-mil wire 1-mil wire 1-mil wire CS-48, INC-49 SS-56/CSCL-54*4/18*4/16*4/16 4/8 4/2*4/27*4/27*4/27*5/13*5/13 5/13**Completed under IVVI Surveillance Event 1109*Completed under IVVI Surveillance Event 1109*Completed under IVVI Surveillance Event 1109 RF-09-47 RF-09-07 Invess,2 10 Invess,240 Invess,330 DW,145,638' DW,240,615' UT UT 13 10 4/14 4/16 4/5 4/11 RIISI Welds B31 12" SE-P (IGSCC,CRC) 5356-5 B31 28" Pipe-El (IGSCC)RHR 20" Tee-Pipe Core Spray 12" El-Pipe Core Spray 12" Pipe-El RCIC 6" El-Pipe RCIC 6" Pipe-E.RCIC 20" Sweep-Pipe RCIC 20" Pipe-Tee FW (TASCS) 20" Tee-Pipe RCIC 20" El-Tee RCIC 12" Tee-El 5357-5 2299-5 3053-5 3053-5 2192-5 2192-5 3536-5 3536-5 3536-5 3536-5 3536-5 Vol.UT UT UT UT UT UT UT UT UT UT UT UT 10 4 3 3 3 3 3 3 3 3 3 3 SS-17 SS-3 CS-12 CS-15 CS-15 CS-22 CS-22 CS-12 CS-12 CS-12 CS-12 CS-15 4/3 4/4 4/5 4/8 4/8 4/8 4/11 4/2 4/2 4/3 4/5 4/5 4/5 4/4 4/5 4/10 4/10 4/10 4/12 4/3 4/3 4/3 4/6 4/6 4/14 4/13 4/13 4/15 4/15 4/16 4/15 4/16 4/6 4/12 4/13 4/14 RF-09-44 RF-09-69 RF-09-29 RF-09-57 RF-09-58 RF-09-40 RF-09-60 RF-09-63 RF-09-65 RF-09-64 RF-09-66 RF-09-43 DW,240,615 DW,0,578'DW,175,597 DW,120,637' DW,120,636' DW,42,598' DW,355,598' Stm,10,586' Stm,10,590' Stm,10,594' DW,330,608' DW,330,608' Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)36 9EXAM CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI B-G-1 Bolting 326-02 (Closure Nuts)

Threads in Flange 326-03 (Closure Washers)Base Scope B-G-2 Bolting FBC-E4 1-2297-01 B3 I-F023A-VBB B3 I-F031A-VBB El l-F067-VBB El l-F009-VBB E21 -F005A-VBB E21 -F005B-VBB E51 -F007-VBB G33-F004-VBB B21-F032A-VBB Greater Than 2" 1/3 of locations (1-22)1/3 of locations (1-22)1/3 of locations (1-22)2" and Less 5362-5 5362-5 5362-5 MT UT VT-i 2 9 16 N/A RPV &CSCL-52 N/A 4/5 3/31 4/5 4/5 4/2 4/5 4/13 4/4 4/14 RF-09-10 RF-09-70 RF-09-11Refuel Floor RPV Cavity Refuel Floor 2297-5 5357-5 5357-5 2299-5 2299-5 3052-5 3053-5 2192-5 3096-5 3537-5 VT- 1 VT- 1 VT-l VT- 1 VT-l VT-l VT- 1 VT-l VT-i VT-1 16 16 16 16 16 16 16 16 16 16 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4/5 4/3 4/3 4/5 4/5 3/29 3/29 4/9 4/10 4/11 4/10 4/4 4/4 4/10 4/10 3/29 3/29 4/10 4/11 4/12 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 RF-09-25 RF-09-17 RF-09-18 RF-09-21 RF-09-20 RF-09-22 RF-09-23 RF-09-24 RF-09-46 RF-09-16 DW,51,595' DW,342,574' DW,290,578 DW,163,595'DW, 163,600' RB2,C13,633 RB2,C0 1,632 DW,360,583' RB2,C13,624 Stm,350,594' Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)37 CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Renort Loc/Az/EI B21 -F010B-VBB B21-FO11B-VBBInitial Sample Expansion B-G-2 Bolting E1 l-F015B-VBB E21 -F006A-VBB E21 -F006B-VBB E21 -F007A-VBB E21 -F007B-VBB 3536-5 3536-5 VT-1 16 VT-1 16 N/A 4/14 N/A 4/9 4/16 4/10 4/17 4/17 RF-09-14 RF-09-15 DW,I0,603' DW.10.594 2" and Less E41-F002-VBB E41 -F003-VBB E41 -F006-VBB E5 I-F008-VBB E51-F013-VBB G33-F001-VBB G33-F101-VBB G33-F121-VBB G33-F220-VBB 2327-5 3052-5 3053-5 3052-5 3053-5 2297-5 2297-5 3537-5 2192-5 3536-5 3096-5 3096-5 3536-5 VT-1 VT-i VT-1 VT-I VT-1 VT-1 VT-i VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 16 16 16 16 16 16 16 16 16 16 16 16 16 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4/9 4/9 4/9 4/9 4/9 4/8 4/8 4/8 4/8 4/8 4/9 4/9 4/8 4/10 4/10 4/10 4/10 4/10 4/10 4/10 4/10 4/10 4/10 4/10 4/10 4/10 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 RF-09-89 RF-09-95 RF-09-96 RF-09-97 RF-09-98 RF-09-79 RF-09-78 RF-09-77 RF-09-75 RF-09-76 RF-09-99 RF-09-101 RF-09-74 RF-09-733536-5 VT-i 16 N/A 4/8 4/10 4/17 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)38 RFAT9CEXAMS I CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III Ali' Report Loc/Ax/EI Second Sample Expansion B-G-2 Bolting B21-FOIOA-VBB B21-FOIOB-VBB B21-FO I1A-VBB B21-F032A-VBB B21-F032B-VBB B21 -F076A-VBB B21 -F076B-VBB El 1-F008-VBB E1 I-F015A-VBB El I-F050A-VBB E11-F050B-VBB El 1-F060A-VBBE 11-F060B-VBB E I1-F608-VBB G33-FIOO-VBB G33-F102-VBB G33-F106-VBB G33-F120-VBB Bolting 2" and Less 3537-5 VT-1 3536-5 VT-13537-5 VT-1 3537-5 VT-1 3536-5 VT-1 3537-5 VT-1 3536-5 VT-1 2299-5 VT-1 2298-5 VT-1 2298-5 VT-1 2327-5 VT-1 2298-5 VT-1 2327-5 VT-1 2299-5 VT-1 5351-5 VT-1 5351-5 VT-15351-5 VT-1

3536-5 VT-1 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4/11 4/14 4/11 4/11 4/11 4/11 4/11 4/14 4/11 4/11 4/11 4/11 4/11 4/11 4/11 4/11 4/11 4/12 4/15 4/12 4/12 4/12 4/12 4/12 4/15 4/12 4/12 4/12 4/12 4/12 4/12 4/12 4/12 4/12 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 4/17 RF-09-80 RF-09-8 1 RF-09-82 RF-09-83 RF-09-84 RF-09-85 RF-09-86 RF-09-87 RF-09-88 RF-09-90 RF-09-91 RF-09-92 RF-09-93 RF-09-94 RF-09-100 RF-09-102 RF-09-103 RF-09-104 16 N/A 4/11 4/12 4/17 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)39 RF09 EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI B-G-2 BoltingCRD Flange Bolts CRD Bolting C-C Vessel SW-El l-D2-HXS-13 SW-Ell-D2-HXS-14 SW-El l-D2-HXS-15 SW-E I I-D2-HXS-16 C-F-I Augmented FW-C41-2979-63S64 FW-C41-2979-64S65 FW-C41-5058-54S55 C-F-2 SW-Cl1-2113-172-A SW-Cl1-2113-172-A SW-El 1-3035-7WB FW-El 1-3151-3WF2 FW-El 1-3151-3WF2 SW-E 11-3154-4WC SW-E 11-3154-4WC FW-E1 1-3154-13WO FW-El 1-3154-13WO FW-E 11-3158-1W2 FW-El 1-3158-1W2 FW-El 1-3158-9WF2 FW-E 11-3158-9WF2 SW-E 11-3177-9WE SW-El 1-3177-9WE FW-E21-3148-7W0 FW-E21-3148-7WO FW-E41-3162-1 lWFl FW-E41-3162-11WF4 Bolting 2" and Less 4219 (1) 3431 (2)New CRD Bolting 1-184 Integral Attachment RHR HX B RHR HX B RHR HX B RHR HX B NRC Commitment SLC weld 2" El -Pipe SLC weld 2" Pipe-El SLC weld 2"Pipe-Reducer Circumferential Weld CRD SDV' Pipe-Tee RHR 6" El-Pipe RHR 24" Tee-El RHR 24" El-Tee RHR 24" Pipe-Pump RHR 24" Pipe-El RHR 20" Pipe-El RHR 20"El-Pipe Core Spray 12" Red-Pump HPCI 16" Pipe-Tee HPCI 16" Tee-Reducer 5363-5 VT-1 16 N/A N/A VT-1 16 N/A 4/9 4/12 4/173/27 3/28 4/16 Loc/AzIEl 5370-5 5370-5 5370-5 5370-5 2979-5 2979-5 5374-5 5375-5 5375-5 3035-5 3151-5 3151-5 3154-5 3154-5 3154-5 3154-5 3158-5 3158-5 3158-5 3158-5 3177-5 3177-5 3148-5 3148-5 3162-5 3162-5 MT MT MT MT PT PT PT MT UT MT MT UT MT UT MT UT MT UT MT UT MT UT MT UT VT-1 VT-i 2 2 2 2 N/A N/A N/A N/A N/A N/A N/A 4/12 4/12 4/12 4/12 4/14 4/14 4/14 4/14 4/15 4/15 4/16 4/16 1 1 1 3/24 3/26 4/4 3/24 3/26 4/4 3/24 3/26 4/4 2 3 2 2 3 2 3 2 3 2 3 2 3 2 3 2 3 17 17 N/A CS-20 N/A N/A CS-43 N/A PDI-AIt-CS 1 N/A PDI-Alt-CS I N/A CS-43 N/A CS-42 N/A CS-42 N/A PDI-Alt-CS 1 N/A N/A 3/29 3/29 3/29 4/12 4/12 3/30 3/30 3/31 4/1 3/30 3/31 3/30 3/31 4/3 4/3 3/31 4/1 3/25 3/25 4/1 4/1 3/30 4/14 4/14 3/30 4/2 4/2 4/2 3/30 3/31 4/1 4/1 4/4 4/4 4/2 4/2 3/28 3/28 4/6 4/6 4/4 4/16 4/16 4/6 4/6 4/13 4/13 4/6 4/6 4/14 4/14 4/6 4/6 4/14 4/14 4/4 4/4 RF-09-105 RF-09-72 RF-09-53 RF-09-54 RF-09-55 RF-09-56 RF-09-26 RF-09-27 RF-09-28 RF-09-48 RF-09-48 RF-09-49 RF-09-30 RF-09-30 RF-09-50 RF-09-50 RF-09-31 RF-09-31 RF-09-32 RF-09-32 RF-09-33 RF-09-33 RF-09-52 RF-09-52 RF-09-34 RF-09-34 RF-09-35 RF-09-36 RB3, 652,E 1I RB3, 652,E1 1 RB3,F10,661 RB1,C10,597' Tor, 180,578 HxRm,C10,605' Tor,C17,543' RBSB,A15,541' HxRm,C 17,593'HxRm,B17,635' Tor,B 10,570'RBSB,G17,541' Tor,GL 1,564'Tor,G1 1,564'RB2,B9,625' Drywell, Undervessel Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)40 RCFed9/EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI FW-E41-3162-11 WF5 FW-E41-3167-OW1 FW-E41-3167-OW1 FW-E41-3169-2W0 FW-E41-3169-2W0 SW-E41-5373-GW3 SW-E41-5373-GW3 SW-N30-3258-7WK SW-N30-3258-7WK SW-N30-3258-7WKLU SW-N30-3258-7WKLU C-F-2 SW-Ell-3160-1WD ANSI B31.1 FW-N20-3105-0W23 HPCI 10" Reducer-Reducer HPCI 10" Pump-Pipe HPCI 10" Pipe-Valve HPCI 12"El-PipeMain Steam 26" Pipe-RedEl Main Steam 26" Long Seam Branch Connections RHR 18" Weldolet GL 88-01 Category D 20" El-SE Htr 4N, Upper Nozz 3162-5 3167-5 3167-5 3169-5 3169-5 5373-5 5373-5 3258-5 3258-5 3258-5 3258-5 VT-1 MT UT MT UT MT UT MT UT MT UT 17 2 3

2 3 2 3 2 3 2 3 N/A N/A CS-50 N/A CS-36 N/A PDI-Alt-CS 1 N/A CS-5 N/A CS-5 3/25 3/26 3/26 3/26 3/27 3/27 3/27 4/6 4/6 4/6 4/6 3/28 3/28 3/28 3/29 3/29 3/30 3/30 4/10 4/10 4/10 4/10 4/4 4/11 4/11 4/14 4/14 4/12 4/12 4/13 4/13 4/15 4/15 RF-09-37 RF-09-38 RF-09-38 RF-09-39 RF-09-39 RF-09-59 RF-09-59 RF-09-67 RF-09-67 RF-09-68 RF-09-68 RF-09-51I RF-09-41 RF-09-62 RF-09-42 RF-09-61 Tor,G11,564'HPCI Skid, 546'CRD,G1 1,569' HPCI Skid, 546'Stm,F12,589' Stm,F12,589' 3160-5 MT 2 N/A 3/29 3/30 4/4 Tor,B 15,578'SW-N20-03-B01 I-BWSE 20" Nozz-SE 4N, Upper Nozz 3105-1 PT/UT 1 / 13 SSCL-88 4/16 4/18 N/A PT/UT 1 / 13 SSCL-88 4/16 4/18 N/A PT/UT 1 / 13 SSCL-88 4/15 4/18 N/A PT/UT 1 / 13 SSCL-88 4/15 4/18 N/A TB2,P12,624' TB2,P12,624' TB2,P12,615' TB2,P 12,615'FW-N20-3105-22WO SW-N20-03-BO011-AWSE 20" El-SE Htr 4N, Lower 3105-1 Nozz 20" Nozz-SE 4N, Lower Nozz 3105-1 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)41 RIFO9EXAMS-Procedure Reference Code 39.NDE.001 1 39.NDE.002 2 PDI-UT-1 3 PDI-UT-2 4 PDI-UT-5 5 GE-UT-300 6 GE-UT-704 7 GE-UT-705 8 GE-UT-308 9 GE-UT-209 10 GE-UT-236 11 GE-UT-504 12 PDI-UT- 10 13 43.000.03/04 14 43.000.017 15 43.000.014 16 43.000.019 17 43.000.013 18 GE-UT-309 19 GE-UT-311 20 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)42 2.6 Interval 2, Period 1, RF08 Examinations RF08 EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANiI Report Loc/Az/El B-A Reactor Vessel 1-308A 1-308B 15-308C 2-307A B-A Reactor Vessel 4-319 6-306 2-319A 2-3 19B 2-319C 1-319B 1-319H 1-306A 1-306D 1-306E 1-306G 1-306K Shell Welds Longitudinal Seam Weld 5360-5 Longitudinal Seam Weld 5360-5 Longitudinal Seam Weld 5360-5 Longitudinal Seam Weld 5360-5 Circ Head Welds 2-319C to 2-319E 40% 5360-5 180 deg. to 360 deg. 5360-5 Top Head 5360-5 Top Head 5360-5 Top Head 5360-5 Top Head 5360-5 Top Head 5360-5 Bottom Head 5360-5 Bottom Head 5360-5 Bottom Head 5360-5 Bottom Head 5360-5 Bottom Head 5360-5 UT 8 2667-62-1 UT 8 2667-62-1 15-Nov 17-Nov 19-Nov R8-96 15-Nov 17-Nov 19-Nov R8-97 UT UT UT UT UT UT UT UT UT UT UT UT UT UT 8 2667-62-1 8 2667-60-1 6 2667-58-1 6 2667-59-1 6 2667-58-1 6 2667-58-1 6 2667-58-1 6 2667-58-1 6 2667-58-1 6 2667-59-1 6 2667-59-1 6 2667-59-1 6 2667-59-1 6 2667-59-1 14-Nov 12-Nov 1 -Nov 5-Nov 31-Oct 31-Oct 2-Nov 30-Oct 30-Oct 6-Nov 6-Nov 6-Nov 6-Nov 6-Nov 17-Nov 17-Jan 5-Nov 7-Nov 6-Nov 6-Nov 6-Nov 5-Nov 5-Nov 7-Nov 7-Nov 7-Nov 7-Nov 7-Nov 19-Nov R8-98 19-Nov R8-9917-Nov R8-47 15-Nov R8-57 17-Nov R8-4417-Nov R8-45 17-Nov R8-46 17-Nov R8-4217-Nov R8-43

17-Nov R8-60 18-Nov R8-6118-Nov R8-6218-Nov R8-6318-Nov R8-64 DW,52,552 DW,142,552 DW,262,244 DW,339,122 Refuel Floor Refuel Floor Refuel Floor Refuel Floor Refuel FloorRefuel Floor

Refuel Floor Bin, OdegBin, 120deg Bio, 144 deg Bin, 225deg Bin, 335deg Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)43 RF0 EX-A-MS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/AzIEI B-A Reactor Vessel 13-308 13-308 B-A Reactor Vessel 3-319 3-319 B-D Reactor Vessel 8-316A 8-316-B 4-316A 4-316B 4-316D 14-316B 13-314A 13-314B 13-314D 13-314G Shell to Flange WeldsPartial from shell sidePartial from flange Head to Flange 1/3 of weld length 1/3 of weld length Nozzle to Vessel Welds Main Steam Nozzle Main Steam Nozzle Feedwater NozzleFeedwater Nozzle Feedwater Nozzle Core Spray Nozzle Recirc Inlet Nozzle Recirc Inlet Nozzle Recirc Inlet Nozzle Recirc Inlet Nozzle Recirc Inlet Nozzle Recirc Suction Nozzle JPI Nozzle Nozzle Inside Radius Inner Radius Region Inner Radius Region Inner Radius Region Inner Radius Region Inner Radius Region5360-5 UT 7 2667-62-1 13-Nov 16-Nov 16-Nov R8-95 5360-5 UT 7 2667-58-1 I-Nov 6-Nov 17-Nov R8-415360-5 MT 2 N/A 30-Oct 6-Nov 17-Nov R8-41 5360-5 UT 9 CSCI-52-FER 28-Oct 30-Oct 17-Nov R8-12 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 UT UT UT UT UT UT UT UT UT UT UT UT UT 7 7 7 7 7 7 7 7 7 7 7 7 7 2667-62-1 2667-62-1 2667-62-1 2667-62-1 2667-62-1 2667-62-1 2667-60-1 2667-60-1 2667-60-1 2667-60-1 2667-60-1 2667-60-1 2667-60-1 8-Nov 8-Nov 8-Nov 7-Nov 8-Nov 7-Nov 5-Nov 5-Nov 6-Nov 4-Nov 5-Nov 12-Nov 9-Nov 9-Nov 9-Nov 9-Nov 8-Nov 10-Nov 8-Nov 7-Nov 7-Nov 7-Nov 7-Nov 7-Nov 14-Nov 10-Nov 19-Nov 19-Nov 19-Nov 18-Nov 18-Nov 18-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 15-Nov 17-Nov R8-76 R8-77 R8-75 R8-65 R8-78 R8-66 R8-53 R8-59 R8-58 R8-51 R8-54 R8-93 R8-82 DW, 723"Vessel Cav.

Refuel Floor Refuel Floor DW,71,655 DW,109,655 DW,30,642 DW,90,642 DW,210,642

DW,240,641 DW,30,615 DW,60,615 DW,120,615 DW,240,615 DW, 330,615 DW, 0,614 DW,280,612 13-314K 5-314A 19-314B B-D Reactor Vessel 8-316A 8-316-B 4-316A 4-316B 5361-5 UT/VT 13 or 15 N/A 5361-5 UT/VT 13 or 15 N/A 1VVI 18-Nov 30-Nov 01-034 IVVI 18-Nov 30-Nov 01-034 5361-5 UT 11 N/A 8-Nov 13-Nov 17-Nov5361-5 UT 11 N/A 8-Nov 13-Nov 17-Nov5361-5 UT 11 N/A 7-Nov 13-Nov 17-Nov Same as Nozzle to vessel above DW,71,655 DW,109,655 DW,30,642 DW,90,642 DW,210,642 R8-86 R8-87 R8-88 4-316DDetroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)44 RF08EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L Ill ANII Report Loc/Az/El 14-316B Inner Radius Region 5361-5 15-315 Inner Radius Region 5361-5 13-314A Inner Radius Region 5361-5 13-314B Inner Radius Region 5361-5 13-314D Inner Radius Region 5361-5 13-314G Inner Radius Region 5361-5 13-314K Inner Radius Region 5361-5 5-314A Inner Radius Region 5361-5 19-314B Inner Radius Region 5361-5 B-D Reactor Vessel Nozzle Inner Bore Region 4-316A IBR FW Nzz Inner Bore 5361-5 Region 4-316B IBR FW Nzz Inner Bore 5361-5 Region 4-316D IBR FW Nzz Inner Bore 5361-5 Region B-F & B-J Class 1 Piping RIISI Welds N5B 12" CS SE to Nzz (DM) 3052-5UT /VT 13 or 15 UT/VT 13or15 UT/VT 13or 15 UT/VT 13or 15 UT/VT 13 or 15 UT/VT 13or 15 UT/VT 13or 15 UT/VT 13or 15 UT/VT 13or 15 N/A N/A N/A N/A N/A N/A N/A N/A N/A 70287 70287 70287 I-Nov 13-Nov 30-Nov 1-Nov 13-Nov 30-Nov 1-Nov 18-Nov 30-Nov 1-Nov 18-Nov 30-Nov N/A N/A N/AN/A N/A N/AN/A N/A N/A 1 -Nov 18-Nov 30-Nov I -Nov 18-Nov 30-Nov 8-Nov 13-Nov 17-Nov8-Nov 13-Nov 17-Nov 7-Nov 13-Nov 17-Nov UT UT UT 11 11 11 01-034 01-034 01-034 01-034 N/A N/A N/A 01-034 01-034 R8-86 R8-87 R8-88 R8-79 R8-71 R8-49 R8-39 R8-38 R8-40 R8-74 R8-72 R8-73 R8-91 DW,240,641 DW,150,638 DW,30,615 DW,60,615 DW,120,615 DW,240,615 DW, 330,615 DW, 0,614 DW,280,612 DW,30,642 DW,90,642 DW,210,642 DW,240,641 DW,240,641 DW,270,613 DW,270,600 DW,270,600 DW,140,573 DW,72,655 DW,72,655 DW,72,653 DW,314,609 UT 12 CS-44/IN-45 6-Nov 16-Nov 19-Nov UT 12 CS-18/IN-45 7-Nov 16-Nov 19-Nov SW-E21-3052-4WOX FW-RD-2-A9 FW-E1 1-2298-6W0 SW-El 1-2298-6WC 10"CS Pipe to SE (DM) 3052-5 28" Tee to Cross 5357-5 24" Pipe to Tee 2298-5 24" Pipe to Pipe (DM) 2298-5 FW-G33-3096-1OWF3 4' Sweepolet to Tee 5351-5 7-316A Main Steam Nzz to SE 5352-5 SW-PS-2-A1-A 26" Pipe to Elbow 5352-5 SW-PS-2-A1-B 26" Elbow to Pipe 5352-5 SW-PS-2-C3-J 8" Sweepolet to Pipe 5354-5 UT UT UT UT UT UT UT UT 4 4 4 3 3 3 3 SS-30 SS-8 CS-7/SS-8 2-Nov 2-Nov 16-Nov 3-Nov 5-Nov2-Nov 2-Nov 17-Nov SS-23 CS-5 CS-5 CS-5 CS-20 2-Nov 8-Nov 17-Nov 8-Nov 8-Nov 19-Nov 8-Nov 8-Nov 17-Nov8-Nov 8-Nov 17-Nov12-Nov 13-Nov 17-Nov Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)45 RFC8ESEXAMSP A L II ocA CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI SW-PS-2-C3-K SW-RD-2-B8-WI SW-RD-2-B8-W2 FW-El 1-2327-OWl FW-E41-2297-2W3 8" Pipe to Flange 12" Pipe to Elbow 12" Elbow to Pipe 24" Valve to Pipe 10" Pipe to Elbow FW-E41-2297-0W4 B-F & B-J Class 1 Piping 3-316A N4A FW-N21-2336-15W0 SW-N21-2336-15WP B-G-1 Bolting RPV Closure Nuts 10" Fluted head to pipe RIISI Welds FW 14" SE to Noz SE Ext. to SE 12" Pipe to SE 12" Pipe to Elbow Greater Than 2" 1/3 of locations 1/3 of locations in place 48-51 48-51 removed 1/3 of locations 1/3 of locations Pump A 1-16 Pump A 1-16 5354-5 5358-5 5358-1 2327-5 2297-5 2297-5 3537-5 3537-5 3537-5 3537-5 UT UT UT UT UT 3 4 4 3 3 CS-20 SS-17 SS-17 CS-9 CS-22 12-Nov 1-Nov 30-Oct 3-Nov 2-Nov 13-Nov 2-Nov 2-Nov 4-Nov 3-Nov 17-Nov 16-Nov 16-Nov 17-Nov 16-Nov UT 3 CS-182-Nov 2-Nov 1 -Nov R8-92 R8-35 R8-15 R8-48 R8-37 R8-36 R8-69 R8-70 R8-68 R8-67 R8-83 UT UT UT UT 3 3 3 3 CS-46 CS-46 CS-15 CS-15 7-Nov 7-Nov 7-Nov 7-Nov 8-Nov 8-Nov 8-Nov 8-Nov 19-Nov 19-Nov 17-Nov 18-Nov DW,314,609 DW,90,613 DW,90,615 RB1,B 12,594 DW,0,586 Stm,F12,586 DW,30,642 DW,30,642 DW,30,642 DW,30,641 Refuel Floor RPV Cavity Refuel Floor RPV Cavity Refuel Floor DW,315,579 DW,315,579

DW,315,579 Refuel Floor Refuel Floor DW,360,594 DW,360,5945362-5. MT 2 N/A 10-Nov 12-Nov 17-Nov RPV Closure Studs RPV Closure Studs Threads in Flange RPV Closure Washers/Bushings Recirc Pump Studs Recirc Pump Studs UT MT UT VT-I 5365-5 VT-i UT VT-I 5361-5 VT-i VT-i 2 10 16 16 5 16 16 16 RPV Stud 28-Oct 4-Nov.N/A 10-Nov CSCL-52 29-Oct N/A 10-Nov N/A 10-Nov B31 Stud 10-Nov N/A 10-Nov N/A 10-Nov N/A 10-Nov 5-Nov 11-Nov 17-Nov12-Nov 17-Nov 30-Oct 16-Nov 12-Nov 17-Nov 17-Nov 27-Nov 12-Nov 19-Nov 17-Nov 27-Nov 17-Nov 27-Nov 17-Nov 27-Nov R8-10 R8-50 R8-50 R8-11 R8-84 R8-85 01-035AP 01-035AN 01-035AO 01-035A 01-035B Recirc Pump nuts, bushings, Pump A 1-16 and washersRPV Spare Flange 0 deg.RPV Spare Flange 180 deg.B-G-2 Bolting 2" and Less FBC-E51-2192-01 FE Flange FBC-B21-5352-OIL SRV Flange 2192-5 VT-1 16 5352-5 VT-1 16 N/A 1-Nov 17-Nov 27-Nov N/A 1-Nov 17-Nov 27-Nov Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)46 tRF08 EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII B-G-2 Bolting B21-FO13L-VBB FBC-B21-5353-01K B21-FO13K-VBB FBC-B21-5353-01G B21-FO13G-VBB B21-F028B-VBB FBC-B21-5354-01B B21-FO13B-VBB B21-F028D-VBB E21 -F006A-VBB E41-F003-VBB G33-FOOl-VBB G33-F120-VBB B21-FO11A-VBB B-H RPV Integral Attachment Welds3-306/4-309 Skirt Weld 3-306/4-309 Skirt Weld 10-324A Stabilizer 2" and Less SRV BonnetSRV Flange SRV BonnetSRV Flange SRV Bonnet B Line Outboard MSIV SRV Flange SRV Bonnet D Line Outboard MSIV CS Inbd Check HPCI Otbd ISO Valve RWCU Inbd IsoRWCU to FW CkFW A Manual Iso 10 percent of length 10 percent of length Stabilizer Lug Weld 5352-5 5353-5 5353-5 5353-5 5353-5 5353-5 5354-5 5354-5 5353-5 3052-5 2297-5 3096-5 3536-5 3537-5 5360-5 5360-5 5360-5 VT-i VT-i VT-1 VT-i VT-i VT-I VT-I VT-i VT-1 VT-I VT-i VT-I VT-i VT-I MT UT MT 16 16 16 16 16 16 16 16 16 16 16 16 16 16 2 7 2 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 1 -Nov 1 -Nov 1-Nov 1 -Nov 1-Nov I -Nov I -Nov 1 -Nov 31-Oct 9-Nov 31-Oct 1 -Nov 1 -Nov I-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 17-Nov 6-Nov 6-Nov 14-Nov 27-Nov 27 Nov 27-Nov 27-Nov 27-Nov 27-Nov 27-Nov 27-Nov 27-Nov 27-Nov 27-Nov 27-Nov 27-Nov 27-Nov 19-Nov 19-Nov 16-Nov Report 01-035D 01-035E 01-035F 01-035G 01-035H 01-0351 01-035J 01-035K 01-035L 01-035M 01-035N 01-0350 01-035P 01-035D Loc/Az1EI DW,39,613 DW,39,613 DW,70,613 DW,70,613 DW,38,613 DW,38,613 DW,298,613 DW,298,613 Stm,F12,599 DW,210,627 Stm,F12,587 DW,229,603 Stm,F12,587 DW,350,603 Bio Annulus Bio Annulus DW,0,647 N/A 4-Nov 4-Nov N/A 13-Nov R8-52 R8-52 R8-94Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)47 RF08 EXAMS -" CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/El B-O CRD Housing Welds CRDH-X02-Y27-W 1 CRDH-X02-Y27-W2 C-A Vessel SW-Ell-D2-HX-11 C-B Vessel SW-El1-D2-HX-01 SW-Eli-D2-HX-01 C-B Vessel SW-Ell-D2-HX-01 IRS C-C Vessel SW-El l-D2-HXS-05 SW-El l-D2-HXS-06 SW-Ell-D2-HXS-07 SW-Ell-D2-HXS-09 SW-Ell-D2-HXS-10SW-El l-D2-HXS-11 SW-El l-D2-HXS-12 SW-Ell-D2-HXS-21 SW-Ell-D2-HXS-22 SW-El l-D2-HXS-23 SW-Ell-D2-HXS-24 C-F-1 Piping FW-C41-2979-72S73 FW-C41-2979-2S3

FW-C41-2979-1S2 Peripheral Housing Weld Peripheral Housing Weld PT I N/A 9-Nov 10-Nov 18-Nov N/A 9-Nov 10-Nov 18-Nov Shell Welds Shell to Flange Nozzle to Shell Welds Inlet Nozzle to Head Inlet Nozzle to Head Inside Radius Inlet Nozzle to Head Integral Attachment Upper Shell Stiffener WeldLower Shell Stiffener Weld Support Ring Stiffener PlateStiffener Plate Stiffener PlateStiffener Plate Stiffener Plate Stiffener PlateStiffener PlateStiffener Plate Circumferential Welds 2" Elbow to Pipe 2" Elbow to Reducer 2" Reducer to Pipe5370-5 UT 14 CS-80 30-Oct 2-Nov 16-Nov 5370-5 UT 14 CS-80 30-Oct 1-Nov 16-Nov5370-5 MT 2 N/A 29-Oct 1-Nov 16-Nov UT 13 CS-81 30-Oct 1-Nov 15-Nov MT MT MT MT MT MT MT MT MT MT MT 2 2 2 2 2 2 2 2 2 2 2 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 31-Oct 31-Oct 31-Oct 3 1-Oct 31-Oct 31-Oct 31-Oct 31-Oct 31-Oct 31-Oct 3 1-Oct 1-Nov 1-Nov 1-Nov 1 -Nov 1 -Nov 1-Nov 1-Nov I -Nov 1-Nov 1-Nov 1 -Nov 26-Oct 1-Nov 1-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 11 -Nov 1 -Nov R8-80 R8-81 R8-34 R8-13 R8-13 R8-30 R8-20 R8-19 R8-21 R8-22 R8-23 R8-24 R8-25 R8-26 R8-27 R8-28 R8-29 R8-02 R8-33 R8-32 DWUV DWUV RB 1,B9, RB1,B9, RBI,B9, RB13,B9, RB1,B9, RB1,B9, RB13,B9, RBI,B9, RBI,B9, RB13,B9, RB13,B9, RB13,B9, RB13,B9, RBI,B9, RBI ,B9, 2979-5 2979-5 2979-5 PT PT PT 1 1 1 N/A 22-Oct N/A 31-Oct N/A 31-Oct RB4,668 RB2,C 12,633 RB2,C 12,633 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)48 "09: XAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI C-F-2 PipingFW-EI 1-3146-5W0 FW-El 1-3146-5WO SW-El 1-3153-13WD SW-E 11-3153-13WDFW-E1 1-3159-OWl FW-E1 1-3159-OWl SW-E21-3145-9WD SW-E21-3147-5WJ SW-E21-3147-5WJ SW-E21-3147-19WB SW-E21-3147-19WB SW-E21-3148-5WD FW-E41-3162-1 IW0 & LD SW-E41-3162-11WC FW-N30-3259-4W0 FW-N30-3259-4W0 FW-T48-04-2095-19W0SW-E 1l-3151-8WD SW-N30-3258-13WB ANSI B31.1 FW-N21-3109-18WO SW-N21-01-B002-AWSE FW-N20-3105-0W13 SW-N20-03-BO1O-BWSE Circumferential Welds 18" Elbow to Valve 24" Pipe to Elbow.375" Std.12" Wol to Pipe.406 Schd.

40 10" Elbow to Pipe 14" Pipe to Elbow.438 Schd. 40 12" Elbow to Pipe 20" Pipe to WOL 24" Elbow to Pipe 24" Elbow to Reducer 24" Pipe to Valve 3146-5 3146-5 3153-5 3153-5 3159-5 3159-5 3145-5 3147-5 3147-5 3147-5 3147-5 3148-5 3162-5 3162-5 3259-5 3259-5 MT UT MT UT MT UT VT-1 MT UT MT UT MT VT-1 VT-I MT UT MT MT MT 2 3 2 3 2 3 17 2 3 2 3 2 17 17 2 3 2 2 2 N/A CS-40 N/A PDI1-Alt N/A PDI1-Alt N/A N/A PDI1-Alt N/A CS-15 N/A N/A N/A N/A CS-9 N/A N/A N/A 25-Oct 25-Oct 24-Oct 25-Oct 26-Oct 26-Oct 3 1-Oct 23-Oct 24-Oct 23-Oct 27-Oct 26-Oct 29-Oct 29-Oct 31-Oct 31-Oct 19-Oct 26-Oct 29-Oct 29-Oct 29-Oct 29-Oct 29-Oct 31 -Oct 3 1-Oct 31-Oct 29-Oct 29-Oct 29-Oct 29-Oct 27-Oct 31-Oct 31-Oct 1 -Nov 1 -Nov 22-Oct 27-Oct 30-Oct 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 16-Nov 11-Nov 16-Nov 16-Nov 16-Nov 16-Nov 11-Nov 16-Nov 16-Nov R8-03 R8-03 R8-07 R8-07 R8-09 R8-09 R8-16 R8-04 R8-04 R8-05 R8-05 R8-06 R8-18 R8-17 R8-31 R8-31 R8-01 R8-08 R8-14 R8-56 R8-55 R8-89 R8-90 Tor,B 13,579 SW Quad,543Y Tor, B13,575 Tor,320,577SE Quad,549Y RB2,"C 11,628 NE Quad,541 Tor,GI 1,560 Tor,G 11,560 TB,L12,632 RB1,B 13,594 Tor,B 12,575 Stm,F12,598 TB3,P5,645 TB3,P5,645

TB2,P4,623 TB2,P4,623 8" Pipe to Tee 2095-5 24" Pipe to Weldolet 3151-5 26" Pipe to Sweepolet 3258-5 GL 88-01 Category D Feedwater Heater Safe-End 3109-1 Weld Feedwater Heater Safe-End 3109-1 Weld Feedwater Heater Safe-End 3105-1 Weld Feedwater Heater Safe-End 3105-1 Weld UT 3/4 CS-86/SSCL-87 UT 3/4 CS-86/SSCL-87 UT 3/4 CS-I 1/SSCL-88 UT 3/4 CS-11/SSCL-885-Nov 7-Nov 17-Nov5-Nov 7-Nov 17-Nov 10-Nov 14-Nov 15-Nov 10-Nov 14-Nov 15-Nov Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)49 RF08 EXAMS Procedure 39.NDE.001 39.NDE.002 PDI-UT-1 PDI-UT-2 PDI-UT-5 PDI-UT-6 ISI-UT-210 IIUX-PDI-254 GFRM2-ISI-54Reference Code 1 2 3 4 5 6 7 8 9 Procedure ISI-UT-55 GFRM2-ISI-246 U7NIXDETC ISI-UT-211 ISI-UT-215 43.000.017

43.000.014

43.000.019Reference Code 10 11 12 13 14 15 16 17Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)50 2.7 Interval 2, Period 1, RF07 Examinations RFO7 EXAMS CAT/COMP ID DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANII Report Loc/Az/EI B-D Reactor Vessel 4-31C IRS 4-316E IRS 4-316F IRS 4-316C IBR 4-316E IBR 4-316F IBR B-F RPV Piping N5B N5B 2-303H 2-303H 4-303A 4-303A 102-304A Nozzle Inner Radius and Bore Region (NUREG-0619)

Inner Radius (NUREG-0619)

Inner Radius 5361-5 UT 6 70287 4/17/00 4/18/00 5361-5 UT 6 70287 4/13/00 4/18/00 5361-5 UT 6 70287 4/17/00 4/18/00 FW Nozz Inner Bore Region 5361-5 FW Nozz Inner Bore Region 5361-5 FW Nozz Inner Bore Region 5361-5 RPV Nozzle to Safe End Dissimilar Metal Nozz-SE 3052-5Core Spray 3052-5 Dissimilar Metal Nozz-SE 5356-5 Recirc Inlet 5356-5 Dissimilar Metal Nozz-SE 5357-5 Recirc Suction 5357-5 Dissimilar Metal Nozz-SE 5361-5 UT 6 70287 4/16/00 4/18/00 UT UT UT PT UT PT UT PT UT PT UT PT MT MT MT MT 6 6 5 1 5 1 5 1 4 1 4 1 2 2 2 2 70287 4/13/00 4/18/00 70287 4/16/00 4/18/00 FER-44,45 4/12/00 4/18/00 N/A 4/11/00 4/18/00 FER-54,56 4/10/00 4/18/00 N/A 4/5/00 4/18/00 FER-55,57 4/12/00 4/18/00 N/A 4/7/00 4/18/00 FER47, Alt. 1 4/13/00 4/18/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/18/00 4/18/00 4/18/00 4/18/00 4/18/00 4/19/00 4/11/00 R7-01 R7-02 R7-03 R7-01 R7-02 R7-03 R7-04 R7-04 R7-05 R7-05 R7-06 R7-06 R7-07 R7-07 R7-08 R7-08 R7-09 R7-10 R7-11 R7-12 R7-13 DW, 150, 642'DW, 270, 642'DW, 330, 642'DW, 150, 642'DW, 270, 642'DW, 330, 642'DW, 240, 641'DW, 270, 615'DW, 0, 614'DW, 110,612'DW, 180, 608'DW, 72, 638'RB, SB, GIO 102-304A Jet Pump Instrumentation 5361-5 5-315 Dissimilar Metal Nozz-SE 5361-5 5-315 Core DP and Liquid Control R1-91 B-K-I Integral Attachment Piping, Pumps, Valves SW-PS-2-A2-AA1 Pipe Lug Class 1 5352-5 SW-PS-2-A2-AA2 Pipe Lug Class 1 5352-5 SW-PS-2-A2-AA3 Pipe Lug Class 1 5352-5 SW-PS-2-A2-AA4 Pipe Lug Class 1 5352-5 C-C Integral Attachments Piping, Pumps, Valves PSFW-E21-3147-301 Class 2 Stanchion to pipe 3147-5 N/A FER28 N/A N/A N/A N/A N/A4/13/00 4/18/00 4/14/00 4/14/004/14/00 4/14/00 4/13/00 4/13/00 4/13/00 4/13/00 4/13/00 4/13/00 4/13/00 4/13/00 MT 2 N/A 3/30/00 3/31/00 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)51 RFO7 EXAMS-DESCRIPTION ISO Exams Procedure CAL STD COMP L III ANI1 Report Loc/Az/EI Class 2 Piping Welds CAT/COMP ID C-F-1 and C-F-2 Pressure Retaining Welds FW-C41-2979-P FW-C41-3361-02Wl FW-E 11-3146-6W10 FW-El 1-3146-6W10 FW-El 1-3146-6WH FW-El1-3146-6WH FW-E1l-3158-1OWF4 FW-Ell-3158-1OWF4 SW-N-30-3258-19WJ SW-N-30-3258-19WJ SW-N-30-3258-19WJLU SW-N-30-3258-19WJLU SW-El 1-3035-5WE FW-EI 1-3157-0W6 FW-E 11-3157-0W6 FW-E21-3144-OWl FW-E21-3147-16W17 FW-E21-3147-16W17 SW-E21-3149-4WD SW-E21-3149-4WD FW-E41-3163-7W0 FW-E41-3163-7W0 FW-T48-04-2095-11W12 FW-T48-04-2097-8W9 SW-T48-04-2097-21WB FW-T48-04-2097-20W21 SW-T48-04-2097-25WF SW-El 1-3146-5WC ANSI B31.1 FW-N20-3107-OW17 SW-N20-03-B014-BWSE FW-N20-3105-16W0 SW-N20-03-B014-AWSE 2" pipe to coupling 3" valve to pipe 20" tee to elbow20" tee to elbow 24" tee to pipe 24" tee to pipe 20" pipe to nozzle 20" pipe to nozzle 26" pipe to reducer 26" pipe to reducer intersecting long seam weld intersecting long seam weld 6" tee to reducer 16" pump to expander 16" pump to expander 12" pump to expander 12" elbow to pipe 12" elbow to pipe 20" pipe to tee 20" pipe to tee 16" pipe to valve 16" pipe to valve 6" pipe to elbow 6" elbow to pipe 8" elbow to pipe 8" pipe to tee 10" elbow to elbow 24" pipe to weldolet GL 88-01 Category D 20" safe end to pipe (din)20" nozzle to safe end (din)20" elbow to safe end (dm)20" safe end to nozzle (din)2979-5 3361-5 3146-5 3146-5 3146-5 3146-5 3158-5 3158-5 3258-5 3258-5 3258-5 3258-5 3035-5 3157-5 3157-5 3144-5 3147-5 3147-5 3149-5 3149-5 3163-5 3163-5 2095-5 2097-5 2097-5 2097-5 2097-5 3146-5 3107-1 3107-1 3105-1 3105-1 PT PT MT UT MT UT MT UT MT UT MT UT MT MT UT MT MT UT MT UT MT UT MT MT VT-1 MT VT-1 MT UT UT UT UT 2 3 2 3 2 3 2 3 2 3 2 2 3 2 2 3 2 3 2 3 2 2 7 2 7 2 3,4 3,4 3,4 3,4 N/A N/A N/A FER-41 N/A FER-43 N/A FER-42 N/A FER-5 N/A FER-5 N/A N/A FER-40 N/A N/A PD1 -1 Alt.N/A PD1 -1 Alt.N/A FER-85 N/A N/A N/A N/A N/A N/A FER-11, 88 FER-11, 88 FER-1 1, 88 FER-l 1, 88 3/30/00 3/31/00 4/6/00 4/8/00 4/3/00 4/4/00 4/14/00 4/14/00 4/7/00 8-Apr 4/7/00 4/8/00 4/8/00 3/31/00 3/31/00 3/30/00 4/3/00 4/6/00 4/1/00 4/1/00 4/8/00 4/10/00 3/30/00 3/30/00 4/5/00 4/8/00 4/5/00 4/3/00 4/10/00 4/10/00 4/6/00 4/6/00 4/3/00 4/3/00 4/8/00 4/8/00 4/18/00 4/18/00 4/18/00 4/18/00 4/14/00 4/14/00 4/14/00 4/14/00 4/17/00 4/18/00 4/18/00 4/3/00 4/18/00 4/18/00 4/18/00 4/18/00 4/14/00 4/14/00 4/3/00 4/3/00 4/6/00 4/16/00 4/6/00 4/3600 4/18/00 4/18/00 4/18/00 4/18/00 4/11/00 4/11/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/19/00 4/19/00 4/19/00 4/19/00 4/19/00 4/20/00 4/20/00 4/11/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/20/00 4/11/00 4/10/00 4/10/00 4/18/00 4/10/00 4/11/00 4/21/00 4/21/00 4/19/00 4/20/00 R7-15 R7-16 R7-17 R7-17 R7-18 R7-18 R7-19 R7-19 R7-20 R7-20 R7-20 R7-20 R7-21 R7-22 R7-22 R7-23 R7-24 R7-24 R7-25 R7-25 R7-26 R7-26 R7-27 R7-28 R7-29 R7-30 R7-31 R7-32 R7-33 R7-34 R7-35 R7-36 RB3, 646'RB4, SLC Mezz, El0 Torus Rm, C13, 574'Torus Rm, B13, 575 RB2, B9, 629'RB1, Stm Tunnel, G13 RB2, B12, 621'RBSB, B17, 541'RBSB, A15,541'RB2, C 1, 628'RBSB, G10, 541 RBSB, GI 1, 541'RB2, A15, 622'RB2, BI11,627'RB2, B15,578'RB2, B15, 578'Torus Rm, X218, 558'Torus Rm.

B13, 575'TB2, R12, 625'TB2, R3, 615'Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)52 Procedure Reference Code Procedure Reference Code 1 39.NDEO0I1 39.NDE.002 PDI-UT-1I PDL-UT-2 1 2 3 4 UNIXDETC Fermi-800-1/2 43.000.019 43.000.004 5

6 7 8 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)53 SECTION 3

SUMMARY

OF REACTOR INTERNAL EXAMINATIONS Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)54 3.0

SUMMARY

OF REACTOR INTERNAL EXAMINATIONS Code Category B-N-1 and B-N-2 Inspections Interval 2, Period 3, RF13 Components Core Spray Piping Welds Spargers/Sparger Brackets Jet Pump Riser Brace (Jet Pump Nos. 9/10)Risers (Jet Pump No. 7/8,13/14, 15/16 Assemblies(Jet Pump No.6, 11, & 12)Diffusers/Adapter welds Restrainer Bracket (Wedges)(Jet Pump Nos. 1-5, 17-20) "Sensing Lines (Jet Pump Nos. 6, 7, 13, 14,, 16, 17)Techniaue Reauirement Results / Remarks EVT-1 EVT-1/NT-1 EVT-1 EVT-1 EVT-1 UT/VT-3 EVT- 1/VT- 1/3 VT-3/VT-1 B WRVIP-1 8-A BWRVIP-1 8-A ASME/BWRVIP-41 BWRVIP-41 BWRVIP-41 BWRVIP-41 BWRVIP-41 SIL 420NRI (Note 1)NRI (Note 1)NRI RI (Note 2)NRI (Note 4)NRI (Note 4)NRI (Note 5)NRI Top Guide / Core Plate 5 locations Top Guide EVT-1 Shroud Shroud Support GussetsShroud Access Hole Covers (AHC)(1)EVT-1/VT-3 EVT-1/VT-3 VT-1/VT-3 BWRVIP-183 BWRVIP-38 BWRVIP- 180 BWRVIP-139 NRI Steam Dryer Assembly 20%NRI (Note 3)RI (Note 8)RI (Note 6)RI (Note 7)NRISteam Separator Assembly 30%Shroud Head Bolts 50%VT-3 VT-3 N/A SIL 433 Notes: (1) Examined accessible areas of all selected piping welds and components to the extent possible per BWRVIP-18A requirements. Sampling inspections were also performed on sparger and bracket welds.(2) Reinspected indication adjacent to RS-1 weld (1.75") on Jet Pump Nos. 7 and 8 identified during RF06 (10/98), and no change in length observed. Therefore, no repair is required.(3) Examined accessible areas of gussets 5 and 6 to EVT- 1 requirements.

(4) All assembly welds visually inspected except for welds AD-1, AD-2 and DF-3, which are inaccessible for EVT-1 inspection. UT examination was unable to be performed on Jet Pumps due to tooling malfunction.

No indications of service induced cracking were detected.

(5) No additional wedge wear was identified on the main wedge for Jet Pump No. 2 following repairs performed during RF 11. 9 wedges were inspected and no additional damage or wear was identified.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)55 (6) No changes noted in previous indications. Inspection requirements were changed to VT-1 per BWRVIP-139. Small indications identified steam dryer support ring above skirt weld and adjacent to seismic support block. Indications evaluated as acceptable per CARD 07-25611.(7) 3 Gusset Plates that had previous indication of cracking in plate material adjacent to welds in RF12 were reinspected during RF 13 and no changes in the indications were identified. The condition remains acceptable without repair.(8) Five linear crack-like indications were identified in the vertical ring above the Adaptor Ring to Ring weldon the 0 degree AHC during RF12. The indications are located in the 316 SS ring material adjacent to the lower fillet weld and also along the ring weld butter fusion line. An evaluation was performed per CARD 07-26611 which concluded that this condition should be acceptable for at least 2 cycles of operationwithout repair. The indications were reinspected during RF 13 and there was no indication of any crackgrowth on any indication. The evaluation remains bounding and in accordance with ASME Section XIadditional inspections will be performed in future outages to ensure the indications remain stable. A planned modification to install a clamping device over the cover per EDP-35798 was unsuccessful and was terminated after the placement of one unthreaded blind hole. Future installation of the clamping device is under consideration for future outages.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)56 Code Category B-N-1 and B-N-2 Inspections Interval 2, Period 3, RF12 Components Technique Requirement Results / Remarks Brackets Jet Pump (8)Guide Rod (1)Steam Dryer (4)Feedwater (12)Surveillance (1)EVT-1/NT-1 EVT-1/VT-3 EVT-1/VT-3 EVT- 1/VT-3 EVT-1/NT-1 BWRVIP-41 BWRVIP-48 BWRVIP-48 BWRVIP-48 BWRVIP-48 BVWRVIP-18 BWRVIP- 18 NRI NRI NRI NRI NRI Core Spray Piping Welds Spargers / Sparger Brackets EVT-1 EVT-1 Jet Pump Riser Brace (Jet Pump Nos.7/8 & 9/10)Risers (Jet Pump Nos. 7/8 & 11/12Assemblies(Jet Pump No.6, 11, & 12)Diffusers/Adapter welds Restrainer Bracket Assemblies (Jet Pump Nos.

1, 2, 6 -15)Sensing Lines (Jet Pump Nos. 6, 7, 11, 12, 16, 17)Jet Pump Beam Bolt Assembly (20)EVT-1 EVT-1 EVT-1 UTNT-3 EVT-1/NT-1/3 VT-3/VT-1 UTNozzle Inner Radius Surfaces (6)Top Guide / Core Plate 2 locations Top Guide 5 locations Guide Tubes VT-1 ASME/BWRVIP-41 BWRVIP-41 BWRVIP-41 BWRVIP-41 SIL 574 / SIL 629SIL 420 BWRVIP-41 Relief Request RR-A31 and RR-A32SIL 554 / BWRVIP-26 BWRVIP-47 BWRVIP-76 BWRVIP-38BWRVIP-180 (Draft)NRI (Note 1)NRI (Note 1)NRI RI (Note 2)NRI (Note 4)NRI (Note 4)NRI (Note 5)NRI NRI NRI (Note 6)Shroud Shroud Welds (113, H4, H5, & 117)Shroud Support Gussets Shroud Access Hole Covers (AHC)(2)

VT-1 EVT-1/NT-3 UT EVT-1/VT-3 EVT-I/VT-3 VT-1/VT-3 NRI NRI Steam Dryer Assembly 50%NRINRI (Note 3)RI (Note 9)RI (Note 7)RI (Note 8)NRI BWRVIP-139Steam Separator Assembly 30%Shroud Head Bolts 50%VT-3 VT-3 N/A SIL 433 Notes: Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)57 (1) Examined accessible areas of all selected piping welds and components to the extent possible per BWRVIP-18A requirements. Sampling inspections were also performed on sparger and bracket welds.

(2) Reinspected indication adjacent to RS-1 weld (1.75") on Jet Pump Nos. 7 and 8 identified during RF06 (10/98), and no change in length observed. Therefore, no repair is required.(6) Examined accessible areas of gussets 4 and 13 to EVT-1 requirements.

(7) All assembly welds visually inspected except for welds AD-1, AD-2 and DF-3, which are inaccessible for EVT-1 inspection.

UT examination was unable to be performed on Jet Pumps due to tooling malfunction.

No indications of service induced cracking were detected.(8) No additional wedge wear was identified on the main wedge for Jet Pump No. 2 following repairs performed during RF 11. 12 wedges were inspected and no additional damage or wear was identified.

Auxiliary spring wedges were installed on Jet Pumps No. 1 and 2 and the slip joint clamp that was installed on Jet Pump No. 2 during RF 11 was reinspected and no damage was identified.

(9) Inspected accessible areas of 6 RPV nozzles inside radius areas within limits of design and geometry.(7) No changes noted in previous indications. Inspection requirements were changed to VT-1 per BWRVIP-139. Small indications identified steam dryer support ring above skirt weld. Indications evaluated as acceptable per CARD 09-22563.(8) 3 Gusset Plates had indication of cracking in plate material adjacent to welds. The condition was evaluated and determined to be acceptable without repair per CARD 07-26175.(9) Five linear crack-like indications were identified in the vertical ring above the Adaptor Ring to Ring weld on the 0 degree AHC. The indications are located in the 316 SS ring material adjacent to the lower fillet weld and also along the ring weld butter fusion line. An evaluation was performed per CARD 07-26611 which concluded that this condition should be acceptable for at least 2 cycles of operation without repair.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)58 Code Category B-N-1 and B-N-2 Inspections Interval 2. Period 3. RF 1I Components Technique Requirement Results / Remarks Brackets Core Spray Piping / Welds Spargers Jet Pump Riser Brace (Jet Pump No. 1/2)Risers (Jet Pump Nos. 1/2, 7/8, 9/10)Assemblies (Jet Pump No.5)Diffusers/Adapter welds (Jet Pump Nos. 11, 12, 13, 14, 15, 18)Restrainer Bracket Assemblies (Jet Pump Nos. 1-20)Sensing Lines (Jet Pump Nos. 6,7,16,17)

EVT-1 EVT- 1/VT-1 EVT- 1/VT-1 EVT-1 EVT-1 UT/VT-3 EVT-1/NT-1/3 VT-3 BWRVIP-18 BWRVTP- 18Nozzle Inner Radius Surfaces Top Guide / Core Plate 2 locations Top Guide VT-i ASME/BWRVIP-41 BWRVIP-41 BWRVIP-41 BWRVIP-41 SIL 574 / SIL 629 SIL 420 Relief Request RR-A31 and RR-A32 SIL 554 / BWRVIP-26 BWRVIP-3 8/104 BWRVIP-38 SIL 474/SIL 644, Rev. 1 BWRVIP-139 N/A SIL 433NRI (Note 1)NRI (Note 1)NRI RI (Note 2)NRI (Note 4)NRI (Note 4)RI (Note 5)NRI NRI (Note 6)VT-i NRI ShroudShroud Support Gussets Steam Dryer Assembly 50%EVT-1/UT EVT-1 VT-i/VT-3 VT-3 VT-3 NM (Note 3)NRI (Note 3)RI (Note 7)NRI NRI Steam Separator Assembly 30%Shroud Head Bolts 50%Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)59 Notes: (1) Examined accessible areas of all selected piping welds and components to the extent possible perBWRVIP-18A requirements. Sampling inspections were also performed on sparger welds.

(2) Reinspected indication adjacent to RS-1 weld (1.75") on Jet Pump Nos. 7 and 8 identified during RF06 (10/98), and no change in length observed. Therefore, no repair is required.(3) Examined H-8 and H-9 welds (EVT-1) at 0' and 180' as well as between various Jet Pumps. Percentcoverage on H8 was 24% and H9 was 30%. Examined accessible areas of gussets 5, 6, 7, 8, 9, 10, 18, and 20 to EVT- 1 requirements.

Performed a UT examination of the H9 weld from the vessel OD surface obtaining 19.6% coverage.(4) All assembly welds visually inspected except for welds AD-I, AD-2 and DF-3, which are inaccessible for EVT- 1 inspection.

UT examination was performed on 6 Jet Pumps (17 welds) using specially designed tooling. No indications of service induced cracking were detected.(5) Wedge wear was identified on the main wedge for Jet Pump No. 2. As a result, all 20 wedges were inspected and additional inspections were performed on the Jet Pump No. 1/2 riser attachment welds.Auxiliary spring wedges were installed on Jet Pumps No.

1 and 2 and a slip joint clamp was installed on Jet Pump No. 2 (reference EDP 34174 and CARD 06-22334).

(6) Inspected accessible areas of the RPV head spare nozzles (2) inside radius areas within limits of design and geometry.(7) No changes noted in previous indications. Inspection requirements were changed to "best effort VT-l "per SIL 644, Rev. 1 and BWRVIP-139.

Indications noted at the base of several vertical welds during RF10 were re-inspected and no changes were noted.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)60 Code Category B-N-1 and B-N-2 Inspections Interval 2, Period 2, RF10 Components Technique Requirement Results / Remarks Brackets Feedwater Spargers (3)Core Spray Piping (3)Guide Rod Bracket (1)Steam Dryer Support (4)Steam Dryer Hold Down (4)Surveillance Holder (1)VT-3 /EVT-1 VT-3/EVT-1 VT-3/EVT-1

VT-3/EVT-1 VT-3/VT-1 VT-1/EVT-1 ASME/BWRVIP-48 ASME/BWRVIP-48 ASME/BWRVIP-48 ASME/BWRVIP-48 ASME/BWRVIP-48 ASME/BWRVIP-48 NRI NRI NRI NRI NRI NRI NRI NM Feedwater Spargers (3)Nozzles (3)VT-3 VT-3 NUIREG-0619 NUJREG-0619 Core Spray Piping / Welds Spargers Jet Pump Riser Brace (Jet Pump No.5/6)Risers (Jet Pump Nos. 5/6 and 7/8)Assemblies (Jet Pump No.5)Diffusers/Adapter welds (Jet Pump Nos. 5,6,8,11,16,17,19)

Restrainer Bracket Assemblies (Jet Pump Nos. 5 and 15)Sensing Lines (Jet Pump Nos. 5,6,7,16,17)

EVT-1 EVT- 1/VT-1 EVT-1/NT-1 EVT-1 EVT-1 EVT-i/VT-3 EVT-i/VT-1/3 VT-3 BWRVIP- 18 BWRVIP- 18 ASME/BWRVIP-41 BWRVIP-41 BWRVIP-41 BWRVIP-41 SIL 574 / SIL 629 SIL 420 Relief Request RR-A31 and RR-A32 SIL 554 / BWRVIP-26 NRI (Note 1)NRI (Note 1)NRI RI (Note 2)NRI (Note 4)NRI (Note 4)RI (Note 6)NRI NRI (Note 5)Nozzle Inner Radius SurfacesTop Guide

/ Core Plate 2 locations Top Guide VT-1 VT-1 NRI Shroud Shroud Support Gussets Steam Dryer Assembly 50%EVT-1 VT-1 BWRVIP-07

/ 38 BWRVIP-07

/ 38NRI (Note 3)NRI (Note 3)RI (Note 7)VT-1/VT-3 SIL 474/SIL 644, Rev. 1Steam Separator Assembly 30%Shroud Head Bolts 50%VT-3 VT-3 N/A SIL 433 NRI NRI Notes: Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)61 (1) Examined accessible areas of all selected piping welds and components to the extent possible per BWRVIP-1 8 requirements. Sampling inspections were also performed on sparger welds.(2) Reinspected indication adjacent to RS-1 weld (1.75") on Jet Pump Nos. 7 and 8 identified during RF06 (10/98), and no change in length observed. Therefore, no repair is required.(3) Examined H-8 and H-9 welds adjacent to Jet Pump No.5. Examined accessible areas of gussets 7 and 8 to VT-i requirements.

(4) All assembly welds visually inspected except for welds DF-3, AD-1 and AD-2, which are inaccessible for EVT- 1 inspection.

An access study was performed in preparation for a UT examination in the future.(5) Inspected accessible areas of the following nozzle inside radius areas within limits of design and geometry:

Jet Pump Instrumentation (1), Reactor Recirculation inlet (1), RPV head instrumentation.

(6) Reinspected auxiliary spring wedge installed in RF09 as a permanent repair.

No changes were noted.Identified small gap on restrainer screw for Jet Pump No.5 that does not impact operability.

(7) No changes noted in previous indications. Inspection requirements were changed to "best effort VT-l"per SIL 644, Rev. 1. Indication noted at the base of several vertical welds not previously inspected.

Evaluated as acceptable for at least one cycle of operation without repair.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)62 Code Category B-N-1 and B-N-2 Inspections Interval 2, Period 2, RF09 Components Technique Requirement Results / Remarks Brackets Feedwater Spargers (3)Core Spray Piping (4)VT-3 EVT-1 EVT-1 Feedwater Spargers (3)Nozzles (3)Core Spray Piping / Welds Spargers VT-3 VT-3 BWRVIP-48 BWRVIP-48 NUREG-0619 NUREG-0619 BWRVIP- 18 BWRVIP- 18 NRIRI (PB-015 Wear)NRI NRI Jet Pump Riser Brace (Jet Pump Nos. 3 and 4)Risers (Jet Pump Nos. 3, 4, 7)Assemblies (Jet Pump Nos. 3 and 4)Restrainer Bracket Assemblies (Jet Pump Nos. 1 through 20)Sensing Lines (Jet Pump Nos.3 and 4)Nozzle Inner Radius Surfaces EVT-1 EVT- 1 iNT-1 EVT-1/VT-1 EVT-1 EVT-1 EVT- i/VT- 1/3 VT-3 ASME/BWRVIP-41 BWRVIP-41 BWRVIP-41 SIL 574 / SIL 629NRI (Note 1)NRI (Note 1)NRIRI (Note 2)NRI (Note 4)RI (Note 6)SIL 420 NRI VT-1 Relief Request RR-A31 and RR-A32 SIL 554 / BWRVIP-26 NRI (Note 5)Top Guide / Core Plate 6 locations Top Guide VT-1 NRI ShroudShroud Support Gussets Steam Dryer Assembly 30%Steam Separator Assembly 30%Shroud Head Bolts 50%EVT-1 EVT-1 VT-3 VT-3 VT-3 BWRVIP-07

/38 BWRVIP-07

/38 NRI (Note 3)NRI (Note 3)SIL 474 No change in indications noted N/A SIL 433 NRI NRI Detroit Edison Co., One Energy Plaza, Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)63 Notes: (1) Examined accessible areas of all selected piping welds and components to the extent possible perBWRVIP-18 requirements.

Sampling inspections were also performed on sparger welds.

(2) Reinspected indication adjacent to RS-1 weld (1.75") on Jet Pump Nos. 7 and 8 identified duringRF06 (10/98), and no change in length observed.

(3) Examined H-8 and H-9 between Jet Pump Nos. 3 and 4. Examined accessible areas of gussets 2 and 15.(4) All assembly welds visually inspected except for welds DF-3, AD-1 and AD-2, which are inaccessible forVT inspection.

UT technique not available.

(5) Inspected accessible areas of the following nozzle inside radius areas within limits of design and geometry: Reactor Recirculation outlet (1), Reactor Recirculation inlet (5).(6) Second cracked tack weld discovered on restrainer screw for Jet Pump No. 15. Crimped screw andinstalled auxiliary spring wedge as a permanent repair.Detroit Edison Co., One Energy Plaza, Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)64 Code Category B-N-I and B-N-2 Inspections Interval 2, Period 1, RF08 Components Technioue Reauirement

'Results / Remarks Brackets Steam Dryer Support (4)Feedwater Spargers (6)Guide Rod Bracket 00 & 1800 Core Spray Piping (4)EVT-1 EVT-1 EVT- 1/VT-3 EVT-1 Feedwater Spargers (3)Nozzles (3)Core Spray Piping / Welds Spargers VT-3 VT-3 BWRVIP-48 BWRVIP-48 BWRVIP-48 BWRVIP-48 NUREG-0619 NUREG-0619 BWRVIP-18 BWRVIP-18 BWRVIP-41 BWRVIP-41 BWRVIP-41 NRI NRI NRI NRI NRI NRI Jet Pump Risers (Jet Pump Nos. 7 and 8)Risers (Jet Pump Nos. 1 and 2)Assemblies (Jet Pump Nos. 1 and 2)Restrainer BracketAssemblies (Jet Pump Nos. 1 through 20)Sensing Lines EVT-1 EVT- 1/VT-1 EVT-1 EVT-1 EVT-1 EVT- 1/VT- 1/3 VT-3NRI (Note 1)NRI (Note 1)RI (Note 2)NRINRI (Note 4)SIL 574 / SIL 629 SIL 420 NRI NRI NRI NRI Dry Tubes 4-SRM 8-IRM VT-i VT-1 SIL 409 /RICSIL-073 Top Guide / Core Plate 8 locations Top Guide Core Plate Bolts (4 locations)

Shroud Shroud Support Gussets Steam Dryer Assembly 30%Steam Separator Assembly 30%Shroud Head Bolts 50%VT-1 VT-1 EVT-1 EVT-1 VT-3 VT-3 VT-3 SIL 554 / BWRVIP-26 SIL 588 / BWRVIP-25 BWRVIP-07

/38 BWRVIP-07

/38 NRI NRI (Note 6)NRI (Note 3)NRI (Note 3)SIL 474No change in indications noted N/A SIL 433 NRI NRI Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)65 Components Technique Requirement Results / Remarks Components Technique Requirement Results / Remarks Nozzle Inside Radius Sections RPV Seal Surface Head Flange Vessel Flange O-Rings Vessel Cladding VT-i (1 mil wire)VT-i VT-i VT-i (Direct)RR-A31 and RR-A32 NRI (Note 5)N/A VT-3 NRI NRI NRI NRI NRI NRI Control Rod Guide Tubes (10)Surveillance Specimen Bracket /Lugs EVT- 1/VT-3 EVT-1iVT-3 BWRVIP-47 BWRVIP-48 Notes: (1) Examined accessible areas of all welds and components to the extent possible.

BWRVIP baseline inspections were completed during RF06 and RF07.

Sampling inspections were performed on the spargers.(2) Reinspected indication adjacent to RS-1 weld (1.75") identified during RF06 (10/98), and no change in length observed.(3) Examined approximately 22% of H-8 and H-9 at 00 and 1800 and between Jet Pump Nos. 2 and 3.Examined accessible areas of gussets 1, 2, 3, 11, 12, and 22.(4) All assembly welds visually inspected except for welds DF-3, AD-1 and AD-2, which are inaccessible for VT inspection.

UT Technique not available.

(5) Inspected accessible areas of the following nozzle inside radius areas within limits of design and geometry:

Main Steam (2), Core Spray (1), CRD Hydraulic Return (1) and Reactor Recirculation (3).(6) Inspected top of bolts at four azimuth locations only.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)66 Code Category B-N-1 and B-N-2 Inspections Interval 2, Period 1, RF07 ComDonents Technioue Reauirement Results / Remarks Brackets Steam Dryer Support (4)Feedwater Spargers (6)Guide Rod Bracket at 1800 Core Spray Piping (4)EVT-1 EVT-1 EVT-1/VT-3 EVT-1 Feedwater Spargers Nozzles Core Spray Piping / Welds Spargers Jet Pump Risers (Jet Pump Nos. 7 and 8)Risers (Jet Pump Nos. 11 through 20)Assemblies (Jet Pump Nos.II through 20)Set Screw Tack Welds Sensing Lines VT-3 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 EVT-1 VT-3 BWRVIP-48 BWRVIP-48 BWRVIP-48 BWRVIP-48 NUREG-0619 NUREG-0619 BWRVIP- 18 BWRVIP- 18 BWRVIP-41 BWRVIP-41 BWRVIP-41 SIL 574 SIL 420 SIL 409 /RICSIL-073 SIL 554 SIL 588 R1 BWRVIP-07 BWRVIP-07 BWRVIP-07 NRI (Note 1)NRIRI (Note 2)NRI NRI (Note 4)NRI NRI NRI NRI NRI NRI NRI NRI Dry Tubes.4-SRM 8-IRM VT-1 VT-i VT-1 VT-1 NRI NRI NRI NRI Top Guide / Core Plate 8 locations Top Guide Core Plate Bolts (4 locations)

Shroud H2 Indication Shroud Support Gussets EVT-1 EVT-1 EVT-1 No change in indication NRI (Note 3)NRM (Note 3)No change Indications have shallow depth as expectedSteam Dryer Assembly 30%Previous Indications Steam Separator Assembly 30%Shroud Head Bolts 50%VT-3 VT-3iUT VT-3 VT-3 SIL 474 N/A SIL 433 NRI NRI Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)67 ComponentsControl Rod Blade 02-39 Technique EVT-1 Requirement CARD 98-17816 Results / Remarks Relook of previous indication

-no significant changes.RPV Seal Surface N/AHead Flange VT-1 NRI Vessel Flange VT-1 NRI O-Rings VT-1 (Direct) NRIVessel Cladding VT-3 NRIControl Rod Guide Rods EVT-iVT-3 BWRVIP-47 NRI Notes: (1) Examined accessible areas of all welds except P-I, which was inaccessible.

(2) Reinspected indication adjacent to RS-1 weld (1.75") identified during RF06 (10/98), and no change in length observed.(3) Examined H-8 and H-9 at 00 and 1800 only. Examined accessible areas of gussets between Jet Pump Nos. 11 through 20.(4) All assembly welds visually inspected expect for welds DF-3, AD-1 and AD-2, which are inaccessible for VT inspection. UT Technique not available.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)68 SECTION 4

SUMMARY

OF COMPONENT SUPPORT EXAMINATIONS Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)69 4.0

SUMMARY

OF COMPONENT SUPPORT EXAMINATIONS VT-3 examinations were performed on various system and component supports. Functional Testing for ASME Section XI, Article IWF-5000 snubbers was performed in accordance with EF-2 Technical Requirements Manualfor functional testing of snubbers (Ref. Paragraph 5.1).4.1 ASME SECTION XI -IWF (Class 1, 2 and 3) Credit for Component Supports for Interval 2, Outages RF-07 through RF- 13 was distributed as noted in the table below.CODE RF-13 RF-12 RF-1 1 RF-10 RF-09 RF-08 RF-07 CLASS 1 9 7 12 7 5 5 5 2 29 19 18 16 21 15 21 3 12 17 13 12 15 10 15 4.2 Technical Requirements Examinations 4.2.1 Refuel 13 Examinations

1. VT-3 examinations were performed on all safety related and non-safety related snubbers selected for functional testing per Technical Requirements Manual TR 5.1.1. Total examined was 176.2. A total of 86 safety related snubbers were functionally tested per the Technical Requirements Manual. 68 snubbers were initially selected and functionally tested.One snubber that failed in RF 12 was tested in RF 13. Due to testing failures, 16 additional snubbers were functionally tested as required by the Technical Requirements Manual. 3 hydraulic snubbers found with low fluid during visualexamination were also tested to determine if the snubbers were acceptable.

3. Service life change out was performed on 45 snubbers.4.2.2 Refuel 12 Examinations

4. VT-3 examinations were performed on all safety related and non-safety related snubbers per Technical Requirements Manual TR 5.1.1. Total examined was 699 snubbers.5. A total of 79 safety related snubbers were functionally tested per the Technical Requirements Manual. 66 snubbers were initially selected and functionally tested. 4 snubbers that failed in RF 11 were tested in RF 12. Due to testing failures, 8 additional snubbers were functionally tested as required by the Technical, Requirements Manual. 1 hydraulic snubber found with low fluid during visual examination was also tested to determine if the snubber was acceptable.

6. Service life change out was performed on 59 snubbers.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)70 4.2.3 Refuel- 11 Examinations

1. VT-3 examinations were performed on all safety related and non-safety related snubbers selected for functional testing per Technical Requirements Manual TR 5.1.1. Total examined was 348.2. A total of 113 safety related snubbers were functionally tested per the Technical Requirements Manual. 66 snubbers were initially selected at random and functionally tested. 6 snubbers that failed in RF 10 were tested in RF 11. Due to testing failures, 41 additional snubbers were functionally tested as required by the Technical Requirements Manual.3. Service life change out was performed on 75 snubbers.4.2.4 Refuel-10 Examinations

1. VT-3 examinations were performed on all safety related and non-safety related snubbers selected for functional testing per Technical Requirements Manual TR 5.1.1. Total examined was 545.2. A total of 122 safety related snubbers were functionally tested per the Technical Requirements Manual. 66 snubbers were initially selected at random and functionally tested. 8 snubbers that failed in RF09 were tested in RF10. Due to testing failures, 48 additional snubbers were functionally tested as required by theTechnical Requirements Manual.3. Seal Life Change out was performed on 47 snubbers.4.2.5 Refuel-09 Examinations

1. VT-3 examinations were performed on all safety related and non-safety related snubbers selected for functional testing per Technical Requirements Manual TR 5.1.1. Total examined was 198.2. A total of 149 safety related snubbers were functionally tested per the Technical Requirements Manual. 66 snubbers were initially selected at random and functionally tested. Due to testing failures, 83 additional snubbers were functionally tested as required by the Technical Requirements Manual.

3. Seal Life Change out was performed on 24 snubbers.4.2.6 Refuel-08 Examinations

1. VT-3 examinations were performed on all safety related and non-safety related snubbers per Technical Requirements Manual TR 5.1.1. Total examined was 699.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)71

2. A total of 66 safety related snubbers per the Technical Requirements Manual were initially selected at random and functionally tested. No snubbers failed functional testing.3. Seal Life Change out was performed on 31 Snubbers.4.2.7 Refuel-07 Examinations

1. VT-3 examinations were performed on all safety related and non-safety related snubbers selected for functional testing per Technical Requirements Manual TR 5.1.1. Total examined was 223.2. A total of 66 safety related snubbers per the Technical Requirements Manual.Snubbers were initially selected at random and functionally tested. Oneadditional snubber that failed functional testing during RF06 was alsofunctionally tested as required by the Technical Requirements Manual.

3. Seal Life Change out was performed on 27 snubbers.4. An additional 124 pre-service examinations were completed, resulting from the installation of additional supports due to a plant modification.

4.2.8 Pre-service Examinations A preservice visual examination was performed for Technical Requirements Manual Snubbers and ASME Section XI supports, which were modified, replaced, added, or repaired during each refueling outage.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166.Commercial Service Date: 1-23-88 NB No. 21085 (RPV)72 SECTION 5 ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE ACTIONS TAKEN Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)73 5.0 ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE ACTIONS TAKEN 5.1 Refuel- 13The results of the inservice inspections performed indicate that vessels, piping, and c6mponents included in the Fermi ISI-NDE Program are in good structural condition and can support safe and reliable operation during the next operating cycle.5.1.1 Reactor Pressure Vessel (RPV) Internals During RF 13, inspections were conducted on numerous reactor vessel components using the recommended inspection methods and techniques contained in ASME Section XI, various Boiling Water Reactor Vessel Internals Project (BWRVIP) inspection and examination guidelines, as well as selected augmented inspections identified in Section

3. The intent is to perform the highest quality inspections on all reactor pressure vessel (RPV) components including some BWRVIP guidelines that have not yet been formally approved by the NRC. This proactive approach will assure the continued structural integrity of RPV components. A detailed listing of inspections is provided in Section 3.Reinspections were performed on the 0 degree, Shroud Support Access Hole Cover (AHC) that had five cracks reported during RF12. No changes were noted in these flaw indications. The evaluation performed during RF 12 concluded that this condition would be acceptable for at least 2 cycles of operation without repair and it remains bounding.

A planned modification to install a clamping device over the cover (EDP-35798) was not completed.

Reinspections to monitor crack growth are scheduled forfuture outages following ASME Section XI guidance.Inspections were completed on accessible welds on Jet Pump pairs No. 6, 7/8, 13/14, and 1.5/16 to comply with the BWRVIP-41 re-inspection recommendations.

Re-inspection was also performed on the main wedges on Jet Pumps No. 1 -5 and 17 -20. No additional wear was identified on the restrainer bracket on Jet Pump No. 2 or at any other inspected location, and inspection scope expansion was not required.During RF06, a crack of approximately 1 3/4 inch in length was identified on the thermal sleeve to elbow weld (RS-1) on the riser of Jet Pump Nos. 7 and 8 at 120 degrees azimuth. This indication was previously evaluated and found acceptable for continued operation without repair. This indication has been reinspected each refueling outage since RF06, and there continues to be no observable change in length or width. This indication is within the allowable flaw acceptance tolerance for this location and repair is not necessary.

Reinspection of this indication will again be performed during RF 14. This crack is similar to indications identified in at least 5 other BWR plants.Inspections of the Steam Dryer were performed, which included VT-1 inspections, following the recommendations contained in BWRVIP- 139 and following the reinspection frequency approved in the NRC's safety evaluation of BWRVIP-139.

Approximately 20% of the Steam Dryer was inspected.

Several small new indications were identified on the Steam Dryer. These indications were evaluated and documented in CARD 09-22563.

The Steam Dryer is acceptable for continued operation.

Selected indications and conditions identified during previous outages were reinspected during RF 13 and no observable changes were noted.Reinspections were performed on the 3 Steam Separators identified with small cracks in the gusset plate material detected during RF 12. No changes were noted in these indications and this condition remains acceptable for continued operation without repair.The RPV internals are in very good condition.

There is no service related degradation that should impact plant performance during the next operating cycle. Internal inspections are achieving their goal of Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)74 detecting and monitoring for degradation, and effecting prudent repairs/replacement to maintain the plant in a safe and reliable manner.

5.1.2 RPV External Volumetric and ASME Piping Weld Examinations Four automated ultrasonic dissimilar metal (DM) weld examinations on the reactor recirculation system were performed as a result of RF 12 exams which identified that data quality for some circumferential scans were partially compromised due to hoop shrinkage.

The extent of this surface condition anomaly has been determined to vary from nozzle to nozzle. These additional locations were selected for RF 13 and satisfactory exams were completed for DM welds on recirculation nozzles N2B and N2K. The RF-1 3 welds will replace the previously limited exams in the ISI NDE Program selections as necessary.

Aconfirmatory exam was also performed on Nozzle N5B DM welds to ensure that previous exams were completed with an acceptable surface condition.

These exams were also found to be acceptable.

Manual NDE was conducted on 26 additional ASME Class 1 and 2 welds and components.

No service related degradation was noted during the RF 13 nondestructive examinations.

The RPV and associated piping systems are in satisfactory condition to support continued safe operation of the plant.The 2nd 10-year Interval will be ended earlier than the originally proposed date of 2/16/2010. The end date is being declared coincident with the completion of RF 13 to shorten the 2 nd interval to maintain the overall pattern of intervals within 1 year of the original schedule as established in accordance with IWA-2430(d).5.1.3 Component Supports 50 newly classified anchor supports were inspected during RF-13. These inspections resulted from adetailed review of equipment base anchors as supports (reference CARD 08-21085 and ISI-NDE Evaluation 08-030). The anchors were found in satisfactory condition.

Snubber functional testing found two mechanical snubbers that did not meet its acceptance criteria.

Thefailures were due to grease migration onto the capstan causing high acceleration.

The snubbers werereplaced with rebuilt and tested snubbers.

Evaluation of the failed snubbers found no adverse effects on its associated piping. The required sample expansions were completed to meet the requirements of the Technical Requirements Manual TR 5.1.1 (reference CARD 09-22187 and 09-22704).

5.2 Refuel-12The results of the inservice inspections performed indicate that vessels, piping, and components included in the Fermi ISI-NDE Program are in good structural condition and can support safe and reliable operation during the next operating cycle.5.2.1 Reactor Pressure Vessel (RPV) Internals During RF 12, inspections were conducted on numerous reactor vessel components using the recommended inspection methods and techniques contained in ASME Section XI, variousBoiling Water Reactor Vessel Internals Project (BWRVIP) inspection and examination guidelines, as well as selected augmented inspections identified in Section 3. The intent is to perform the highest quality inspections on all reactor pressure vessel (RPV) components including some BWRVIP guidelines that have not yet been formally approved by the NRC. This Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)75 proactive approach will assure the continued structural integrity of RPV components. A detailed listing of inspections is provided in Section 3.Ultrasonic inspections were performed on several components during RF12. Ultrasonic reinspections were performed on Core Shroud Welds H3, H4, H5, and H7. All welds were inspected from both sides, examination coverage exceeded 62% for all welds, and no indication of cracking was identified.

All 20 Jet Pump Hold Down Beams were also ultrasonically inspected and no indications of cracking were identified.

During EVT- 1 inspection of the 0 degree, Shroud Support Access Hole Cover (AHC) five linearcrack-like indications were identified in the vertical ring above the Adaptor Ring to Ring weld.The indications are located in the 316 SS ring material adjacent to the lower fillet weld and also along the ring weld butter fusion line. Fine branching can be seen at several locations.

An evaluation was performed per CARD 07-26611 which concluded that this condition should be acceptable for at least 2 cycles of operation without repair. Reinspections are needed to monitor crack growth and are scheduled for RF 13.Inspections were completed on accessible welds on several welds on the Jet Pumps, primarily on Jet Pump No. 6, 7/8, and 11/12 to comply with the BWRVIP-41 re-inspection recommendations.

Re-inspection was performed on the main wedges on Jet Pumps No. 1, 2, and 6 through 15. No additional wear was identified on the restrainer bracket on Jet Pump No. 2 or at any other inspected location, and inspection scope expansion was not required.

Auxiliary spring wedges installed on Jet Pumps No. 1 and 2, and the slip joint clamp installed on Jet Pump No. 2 during RF 11 were reinspected and no additional wear or damage was identified.

During RF06, a crack of approximately 1 3/ inch in length was identified on the thermal sleeve to elbow weld (RS-1) on the riser of Jet Pump Nos. 7 and 8 at 1200 AZ. This indication was evaluated and found acceptable for continued operation without repair. This indication has continuously been reinspected each refueling outage since and again during RF 12, and there continues to be no observable change in length or width. This indication is within the allowable flaw acceptance tolerance for this location and repair is not necessary. Reinspection of this indication will again be performed during RF 13. This crack is similar to indications identified in at least 5 other BWR plants.Inspections of the Steam Dryer were performed, which included VT-I inspections, following therecommendations contained in BWRVIP-139 and following the reinspection frequency prescribed in SIL 644. Several small new indications were identified on the Steam Dryer. These indications were evaluated and documented in CARD 07-25611.

The Steam Dryer is acceptable for continued operation.

Selected indications and conditions identified during previous outageswere again reinspected during RF 12 and no observable changes were noted.Inspections performed on the Steam Separator identified 3 gusset plates that had small cracks in the plate material.

This condition was evaluated in CARD 07-26175 and found acceptable forcontinued operation without repair.

The RPV internals are in very good condition.

There is no service related degradation that shouldimpact plant performance during the next operating cycle. Internal inspections are achieving their goal of detecting and monitoring for degradation, and effecting prudent repairs/replacement to maintain the plant in a safe and reliable manner.5.2.2 RPV External Volumetric and ASME Piping Weld Examinations Automated ultrasonic examinations were performed on three RPV longitudinal shell welds using a new ASME Section XI, Appendix VIII/PDI qualified phased array procedure.

Two of the Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)76 exams were scheduled inspections and found no reportable conditions.

One exam was a planned re-examination of a construction welding flaw in weld 15-308B reported in RF09 (reference paragraph 5.4.2). No change in indication size was detected; however, two additional flaws previously reported were able to have through wall extent sized with the new phased arraytechnique and a specific evaluation was conducted.

Technical Evaluation TE-B 11-07-069 and CARD 07-26861 document the acceptance of these original manufacturing welding flaws.Four automated ultrasonic dissimilar metal (DM) weld examinations were also performed.

As a result of recent industry issues involving inaccurate flaw characterization in Alloy 600weldments, industry lessons learned were considered to ensure that all analysis of the dissimilarmetal weld examinations performed were not affected by loss of transducer contact. Specificconsiderations included:

Identification of all areas where the data quality may be compromised due to surface condition limitations (i.e., remnant weld cap, rough scanning surface, hoop shrinkage etc.).* Identification of components that may contain suspect flaw indications (based on current inspection considerations and lessons learned).This evaluation concluded that the data quality for each axial scan on the welds examined is considered excellent with no limitation of volumetric coverage for the detection of circumferential flaw indications.The evaluation identified that data quality for circumferential scans was partially compromised for each of the nozzles examined due to hoop shrinkage, which resulted in a diametric differencebetween the OD of the nozzle material and the OD of the safe end and weld material.

The extent of this surface condition anomaly varied from nozzle to nozzle; with welds 2-303H and 2-303Jcontaining very minimal shrinkage

-while welds 4-303A and its selected alternate 2-303A containing significant shrinkage (reference CARD 07-26347).

Data quality in areas where the search unit was in full contact with the outside diameter surface prior to traversing over the hoopshrinkage area is also considered excellent.

No evidence of any suspect flaw indications was observed.Manual NDE was conducted on 74 additional ASME Class 1, 2, and 3 welds and components.No service related degradation was noted during these RF 12 nondestructive examinations.The RPV and piping systems are in satisfactory condition to support continued safe operation of the plant.5.2.3 Component Supports Four hangers were found with discrepancies between the installed condition and the configuration document.

It was determined that these conditions did not affect the component's operability and was not reportable.

All hangers found with discrepancies were evaluated under ISI-NDEEvaluations. Additional inspections of adjacent supports were performed.Snubber functional testing found one mechanical snubber that did not meet its acceptance criteria.This failure was due to grease migration onto the capstan causing a high acceleration.

The snubber was replaced with a rebuilt and tested snubber. Evaluation of the failed snubber found no adverse effects on its associated piping. The required sample expansion was completed to meet the requirements of the Technical Requirements Manual TR 5.1.1 (reference CARD 07-26093).Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)77 5.3 Refuel-11The results of the inservice inspections performed indicate that vessels, piping, and components includedin the Fermi ISI-NDE Program are in good structural condition and can support safe and reliable operation during the next operating cycle.5.3.1 Reactor Pressure Vessel (RPV)

Internals During RF 11, inspections were conducted on numerous reactor vessel components using the; recommended inspection methods and techniques contained in ASME Section XI, various Boiling Water Reactor Vessel Internals Project (BWRVIP) inspection and examination guidelines, as well as selected augmented inspections identified in Section 3. The intent is toperform the highest quality inspections on all reactor pressure vessel (RPV) components including some BWRVIP guidelines that have not yet been formally approved by the NRC. This proactive approach will assure the continued structural integrity of RPV components.

A detailed listing of inspections is provided in Section 3.During inspection of the source range monitor (SRM) and intermediate range monitor (IRM) Dry Tubes in RF 10, it was noted that 8 of the 12 Dry Tubes had linear crack-like indications in the collar region above the pressure boundary. During RF1 1, all 12 Dry Tubes were replaced.

A direct visual inspection was performed on each Dry Tube prior to replacement and proper engagement was verified after installation.

Inspections were completed on accessible welds on several welds on the Jet Pumps, primarily on Jet Pump No. 9/10 to comply with the BWRVIP-41 re-inspection recommendations.

Re-inspection was performed on the main wedge on Jet Pumps No. 1 through 5, and No. 16 through 20. Wear was identified on the restrainer bracket on Jet Pump No. 2 and inspection scope was expanded to include all wedges and additional locations on Jet Pumps No. 1 and 2 that share a common riser pipe. Condition Assessment Resolution Document (CARD) 06-22334 was initiated and this condition was evaluated and auxiliary spring wedges were installed on Jet Pumps No. 1 and 2, and a slip joint clamp was installed on Jet Pump No. 2.During RF06, a crack of approximately 1 3/ inch long was identified on the thermal sleeve toelbow weld (RS-1) on the riser of Jet Pump Nos. 7 and 8 at 1200 AZ. This indication was evaluated and found acceptable for continued operation without repair.

This indication was reinspected during RF07, RF08, RF09, RF10, and again in RF1 1, and there continues to be no observable change in length or width. This indication is within the allowable flaw acceptance tolerance for this location and repair is not necessary.

Reinspection of this indication will again be performed during RF 12. This crack is similar to indications identified in at least 5 other BWR plants.Inspections of the Steam Dryer were performed, which included VT-I inspections, following the recommendations contained in SIL 644, Rev. 1, and BWRVIP-139.

Based on these new inspection requirements, several new indications were identified on the Steam Dryer. These indications were evaluated and documented in CARD 06-21741.

The Steam Dryer is acceptablefor continued operation.

Selected indications and conditions identified during previous outageswere again reinspected during RF 11 and no observable changes were noted.The RPV internals are in very good condition.

There is no service related degradation that should impact plant performance during the next operating cycle. Internal inspections are achieving their goal of detecting and monitoring degradation, and effecting prudent repairs/replacement tomaintain the plant in a safe and reliable manner.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)78 5.3.2 RPV External Volumetric and ASME Piping Weld Examinations Automated ultrasonic examinations were performed on the upper RPV shell course welds including the shell to flange weld and four longitudinal seam welds. The exams were performedfrom the inside surface using ASME Section XI, Appendix VIIIIPDI qualified procedures.

Theexamination technique substantially increased the coverage obtained on the shell to flange weld from OD surface and flange face. The vertical welds were covered for essentially 100% of theweld length. Reliance on manual pickups to obtain greater than 90% coverage due to limitations caused by the RPV cavity bellows, stabilizer brackets and behind the bio-shield is no longer necessary.

No indications exceeding the criteria of IWB-35 10 were detected.During RF 11, Detroit Edison performed ultrasonic examinations of ASME Class 1 piping welds using degradation mechanism specific exam volumes and methods where applicable in accordance with the Risk Informed Inservice Inspection Program.

Four additional welds were selected on the reactor recirculation system due to industry operating experience (reference CARD 05-22440).

All other examinations were performed as required by ASME Section XI, 1989. Ultrasonic examination procedures and personnel were qualified in accordance with ASME Section XI, Appendix VIII and the Utility Performance Demonstration Initiative.

No service induced piping weld defects were detected.No service related degradation was noted during RF 11 nondestructive examination (NDE).

TheRPV and piping systems are in satisfactory condition to support future safe operation of the plant.5.3.3 Component SupportsThree hangers were found with discrepancies between the installed condition and the configuration document.

It was determined that this condition did not affect the component's operability and was not reportable. No additional supports were inspected as a result of this observation.

Snubber functional testing found four mechanical snubbers that did not meet its acceptance criteria.

Three of the failures were due to grease degradation. The other failure was due toimproper rebuild in 1996. All snubbers were replaced with rebuilt and tested snubbers.Evaluation of the failed snubbers found no adverse effects on their associated piping. All required sample expansions were completed to meet the requirements of the Technical Requirements Manual TR 5.1.1. Reference the following CARDs: 06-22020, 06-22183, 06-22108 and 06-22363.

5.4 Refuel-10The results of the inservice inspections performed indicate that vessels, piping, and components includedin the Fermi ISI-NDE Program are in good structural condition and can support safe and reliable operation during the next operating cycle.5.4.1 RPV Internals During RF 10, inspections were conducted on numerous reactor vessel components using therecommended inspection methods and techniques contained in ASME Section XI, various Boiling Water Reactor Vessel Internals Project (BWRVIP) inspection and examination guidelines, as well as selected augmented inspections identified in Section

3. The intent is to perform the highest quality inspections on all reactor pressure vessel (RPV) components including some BWRVIP guidelines that have not yet been formally approved by the NRC. This Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)79 proactive approach will assure the continued structural integrity of RPV components.

A detailed listing of inspections is provided in Section 3.During inspection of the source range monitor (SRM) and intermediate range monitor (IRM) Dry Tubes, it was noted that 8 of the 12 Dry Tubes had linear crack-like indications in the collar region above the pressure boundary.

A condition assessment resolution document (CARD) 04-25703 was initiated and evaluated, and no replacements were required during the outage.

Replacement of selected Dry Tubes will be performed during future outages.Inspections were completed on accessible welds on several welds on the Jet Pumps, primarily on Jet Pump No.5 to comply with the BWRVIP-41 reinspection recommendations.

Reinspection was performed on the auxiliary spring wedge installed on Jet Pump No. 15 and this revealed thatthe repair was effective.

A slight gap was identified at a restrainer screw for Jet Pump No.5;however, no main wedge wear was present. This condition was evaluated in CARD 04-25917and does not have any impact on plant operation.

During RF06, a crack of approximately 1 3/4 inch long was identified on the thermal sleeve to elbow weld (RS-1) on the riser of Jet Pump Nos. 7 and 8 at 1200 AZ. This indication was evaluated and found acceptable for continued operation without repair. This indication was reinspected during RF07, RF08, RF09 and again in RF10, and there continues to be no observablechange in length or width. This indication is within the allowable flaw acceptance tolerance for this location and repair is not necessary. Reinspection of this indication will again be performed during RF 11. This crack is similar to indications identified in at least 5 other BWR plants.Inspections of the Steam Dryer were performed, which included VT-1 inspections, following therecommendations contained in SIL 644, Supplement 1, and SIL 644, Rev. 1. Based on these new inspection requirements, several new indications were identified on the Steam Dryer. These indications were evaluated and documented in CARD 04-25416.

The Steam Dryer is acceptablefor continued operation and several indications will be reinspected during RF 11. Selected indications and conditions identified during previous outages were again reinspected during RF 10 and no observable changes were noted.The RPVinternals are in very good condition.

There is no service related degradation that should impact plant performance during the next operating cycle. Internal inspections are achieving their goal of detecting and monitoring degradation, and effecting prudent repairs/replacement to maintain the plant in a safe and reliable manner.5.4.2 RPV External Volumetric and ASME Piping Weld ExaminationsRPV weld ultrasonic examinations using ASME Section XI, Appendix VIII/PDI procedures continue to be performed for the first time on scheduled weld locations. These more sensitiveexaminations identify a significantly larger number of manufacturing flaws than reported duringamplitude based examinations performed prior to RF09. A reexamination of a large slag indication/combination in weld 15-308B, which was discovered during RF09, confirmed that there has been no change. The fracture mechanics evaluation performed as part of CARD 03-16383 determined that the flaw would not present a structural or leakage problem during the remaining service-life of the RPV with a projected 20 percent power uprate, including a 20-year life extension.

Another similar RPV Shell Weld (15-308A) was also examined. The remote inspection system recorded 66 relevant weld indications.

Two of the flaws had a measurable through wall dimension and were typical of those expected in welds fabricated with the sub-vert welding process. One of the flaws was accepted based on the criteria of IWB-3510 and the other was accepted based on the flaw handbook developed for Fermi in accordance with IWB-3600.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, M1 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)80 During RF 10, Detroit Edison continued to implement a Risk Informed Inservice Inspection Program for ASME Class 1 piping welds using degradation mechanism specific exam volumes and methods where applicable.

All other welds were examined as required in ASME Section XI.Ultrasonic examination techniques qualified in accordance with ASME Section XI, Appendix VIII and the Utility Performance Demonstration Initiative were used. No service induced piping weld defects were detected.One ASME Class 2 piping weld that in the previous inspection interval only required a surface examination based on the nominal material thickness, now also requires a volumetric exam under the updated Code requirements. The weld was found to have an ultrasonic exam scanning limitation. The limitation was due to welded support lugs and a Code Plate that prevented obtaining greater than 90 percent coverage (CARD 04-25787).

Therefore, another weld on the same line was selected. That weld had not been examined since construction.

The initial surface exam detected a manufacturing processing flaw that would have been permitted by the material specification.

The flaw was removed with a sanding disc and the required examinations werecompleted satisfactorily (CARD 04-25870).

No service related degradation was noted during RF 10 nondestructive examination (NDE). The RPV and piping systems are in satisfactory condition to support future safe operation of the plant.CARD 04-20518 was initiated well before RF 10 based on Performance Engineering review of industry operating experience (OE) 17638 that identified a potential problem with pressurization of the entire Class 1 boundary during a 10-year interval hydrostatic test. The OE was determined to be applicable to Fermi, and impacted the RF06 pressure test. The Operations test lineup procedure, 24.137.21, was revised and the test was completed as required during RF10.

5.4.3 Component Supports One hanger was found with a discrepancy between the installed condition and the configuration document.

It was determined that this condition did not affect the component's operability and was not reportable.

No additional supports were inspected as a result of this observation.

Snubber functional testing found six mechanical snubbers that did not meet its acceptancecriteria. Four of the failures were due to grease degradation. The other two failures were due to overload.

All snubbers were replaced with rebuilt and tested snubbers.

Evaluation of the failed snubbers found no adverse effects on their associated piping. All required sample expansions were completed to meet the requirements of the Technical Requirements Manual TR 5.1.1.Reference the following CARDs: 04-25816, 04-25845, 04-25663, 04-25662, 04-25612, and 04-25275.5.5 Refuel-09The results of the inservice inspections performed indicate that vessels, piping, and components included in the Fermi ISI-NDE Program are in good structural condition and can support safe and reliable operation during the next operating cycle.5.5.1 RPV Internals During RF09, inspections were conducted on numerous reactor vessel components using the recommended inspection methods and techniques contained in various Boiling Water Reactor Vessel Internals Project (BWRVIP) inspection and examination guidelines as well as selected augmented inspections identified in Section 3. The intent is to perform the highest quality Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)81 inspections on all RPV components including some BWRVIP guidelines that have not yet beenformally approved by the NRC. This proactive approach will assure the continued structural integrity of RPV components. A detailed listing of inspections is provided in Section 3.During vessel flange inspection after disassembly and prior to flood up, it was noted that a nail had been compressed between the flanges near stud No. 54. The nail was removed leaving a depression outside of the sealing surface.

A condition assessment resolution document (CARD) 03-10364 was initiated, and no repairs were required.

Additionally, after O-ring removal and prior to cleaning, the grooves were inspected and heavy silver deposits were noted to have beentransferred from the O-ring. The deposits were flaky in nature and were removed with scotch brite pads followed by light stoning (CARD 03-14819).

Inspections were completed on all accessible welds on two complete Jet Pump Risers andAssemblies (Nos.

3 and 4) to comply with the BWRVIP-41 reinspection recommendations.

Reinspection of a previously cracked restrainer set-screw on Jet Pump No. 15 revealed a second cracked tack weld (CARD 03-1,6929).

All 20 Jet Pumps restrainer assemblies were reinspected as recommended by SIL No. 629, including the wedge, restrainer screw contact, as well as the 80 restrainer screw tack welds. No additional cracked welds were found. The set-screw on Jet Pump No. 15 was staked to prevent backing out and an auxiliary spring wedge was installed per engineering design package (EDP) 32499.During RF06, a crack of approximately 1 3/4 inches long was identified on the thermal sleeve toelbow weld (RS-1) on the riser of Jet Pump Nos. 7 and 8 at 1200 AZ. This indication was evaluated and found acceptable for continued operation without repair.

This indication was reinspected during RF07, RF08, and RF09, and there continues to be no observable change in length or width. This indication is within the allowable flaw acceptance tolerance for this location and repair is not necessary.

Reinspection of this indication will again be performed during RF 10. This crack is similar to indications identified in at least 5 other BWR plants.Indications and conditions identified during previous outages were reinspected during RF09.

One additional tie rod on the steam dryer was found to have a cracked tack weld (TR-E-6) similar tothose noted previously.

There is little or no concern that this nut, or any others, will back out during the current cycle with the remaining sound welds. No other changes were noted.The RPV internals are in very good condition.

There is no service related degradation that shouldimpact plant performance during the next operating cycle. Internal inspections are achieving their goal of detecting and monitoring degradation and effecting prudent repairs/replacement to maintain the plant in a safe and reliable manner.5.5.2 RPV External Volumetric and ASME Piping Weld Examinations During RF09, Detroit Edison implemented a Risk Informed Inservice Inspection Program for ASME Class 1 piping welds. No piping weld defects were detected.

New utility performance demonstration initiative requirements (ASME Section XI, Appendix VIII, Supplement

10) were also implemented for two dissimilar metal weld inspections.

No indications of service related degradation were detected.RPV weld ultrasonic examinations using ASME Section XI, Appendix VIII/PDI procedures continue to be performed for the first time on scheduled weld locations. These more sensitiveexaminations identify a significantly larger number of manufacturing flaws than reported during previous amplitude based examinations. These more sensitive inspections detected 4indications/combinations that would have been unacceptable per IWB-3510.

These pre-existing welding flaws were confirmed by review of the construction radiographs and the pre-service UT Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)82 data. One large slag indication/combination was detected in lower intermediate shell course weld 15-308B and was accepted in accordance with IWB-3112 (b). However, due to its significant size, a fracture mechanics evaluation was performed as specified in CARD 03-16383 to verify theflaw will not present a structural or leakage problem during the remaining service-life of the RPV with a projected 20 percent power uprate, and including a 20-year life extension.

INPO OE16421 was issued to notify other licensees.During the performance of Category B-G-2 bolting inspections, loose nuts were detected on valve bolting at El 1-F009-VBB and CARD 03-16366 was initiated. Investigation determined that the loose bolting was related to torquing practices for pressure seal bonnet bolting. An initial sample expansion was made and additional loose bolting was detected.

The sample was extended to cover all pressure seal style bonnet bolting. Additional CARDs (03-16370, 03-16371, and 03-16372) were initiated for loose bolting during the expanded sample examinations of El 1-F060B-VBB, B21-FOl1B-VBB, and E11-F008-VBB.

Work requests (000Z031279, 000Z031430, 000Z031420, and 000Z0231490) were initiated to re-torque the pressure seal bonnet bolting with system pressure under the bonnets.No service related degradation was noted during RF09 NDE. The RPV and piping systems are insatisfactory condition to support future safe operation of the plant.5.5.3 Component SupportsSeveral hangers were found with discrepancies between the installed condition and their configuration documents.

It was determined that these conditions did not affect the components' operability and were not reportable.

No additional supports were inspected as a result of these observations.

Snubber functional testing found eight mechanical snubbers that did not meet its acceptancecriteria. Five of the failures were due to grease degradation. The other three failures were due tooverload. All snubbers were replaced with rebuilt and tested snubbers.

Evaluation of the failedsnubbers found no adverse effects on their associated piping. All required sample expansionswere completed to meet the requirements of the Technical Requirements Manual TR 5.1.1.Reference the following CARDs: 03-16111, 03-16112, 03-16921, 03-16933, 03-16934, 03-16935, and 03-16927.5.6 Refuel-08The results of the inservice inspections performed indicate that vessels, piping, and components included in the Fermi ISI-NDE Program are in good structural condition and can support safe and reliable operation during the next operating cycle.5.6.1 RPV Internals During RF08, inspections were conducted on numerous reactor vessel components utilizing therecommended inspection methods and techniques contained in various Boiling Water Reactor Vessel Internals Project (BWRVIP) inspection and examination guidelines as well as selectedaugmented inspections identified in Section 3. The intent was to perform the highest qualityvisual inspections on all RPV components utilizing some BWRVIP guidelines that have not yet been formally approved by the NRC. This proactive approach will assure the continued structural integrity of RPV components. A detailed listing of inspections is provided in Section 3.Inspections were completed on all accessible welds on two complete Jet Pump Risers and Assemblies (Nos. 1 and 2) to comply with the BWRVIP-41 reinspection recommendations.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)83 These inspection points included welds previously inspected and no recordable indications were identified.

Baseline inspections had been previously completed for all Jet Pump assembly welds (Nos. 1 through 20) during RF06 and RF07, with the exception of welds DF-3, AD-1 and AD-2.Inspection of these locations will be conducted during future outages when a technique isdeveloped and qualified.

During RF06, a crack of approximately 1 3/4 inches long was identified on the thermal sleeve to elbow weld (RS-1) on the riser of Jet Pump Nos. 7 and 8 at 1200 AZ. This indication was evaluated and found acceptable for continued operation without repair. This indication was reinspected during RF07 and again in RF08, and there continues to be no observable change in length or width. This indication is within the allowable flaw acceptance tolerance for this location and repair is not necessary.

Reinspection of this indication will again be performed during RF09. This crack is similar to indications identified in at least 5 other BWR plants.Because of recent industry findings, all 20 Jet Pumps restrainer assemblies were inspected as recommended by SIL No. 629, including the wedge, restrainer screw contact, as well as the 80 restrainer screw tack welds. The conditions on Jet Pump No. 15 were again unchanged, and it stillappears to have only one of 2 tack welds cracked. No additional cracked welds were found, therefore, no repairs were required this outage. In addition, there was no wedge damage identified and full contact (no gaps) was verified on all restrainer screws on all Jet Pumps.Extensive visual inspections of Core Spray internal piping and spargers were performed per BWRVIP-18 guidelines for reinspection. No indications of cracking were identified.

All accessible areas of the welds were inspected and no recordable indications were identified.Inspections were performed on selected integral attachments per the guidelines of BWRVIP-48 and on approximately 22 percent of the Shroud Support Ring as well as several Gussets per the guidelines of BWRVIP-38.

In addition, visual inspections were performed on several nozzle inner radius sections per Relief Request RR-A31 and A32. No recordable indications were identified on any of these inspections.

Two new indications were identified on the steam dryer assembly welds in areas not previously inspected.

The indications were identical to those previously reported. These indications were evaluated and no repairs were required during RF08. Visual and ultrasonic inspections will continue to be performed during future outages.

Indications and conditions identified during previous outages were reinspected during RF08. The reinspection included the following items with no further degradation identified:

Steam Dryer tie rod nut to washer tack welds cracks and support ring.* RPV internal surfaces -"Bathtub Ring".* SRM / IRM Dry Tubes.No adverse changes in existing indications were noted. The RPV internals are in very good condition.

There is no service related degradation that should impact plant performance during the next operating cycle. Internal inspections are achieving their goal of detecting and monitoring degradation and effecting prudent repairs/replacement to maintain the plant in a safe and reliable manner.5.6.2 RPV External Volumetric and ASME Piping Weld Examinations Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)84 During RF08, Detroit Edison implemented a Risk Informed Inservice Inspection Program for ASME Class 1 piping welds. No piping weld defects were detected.

New utility performance demonstration initiative requirements (ASME Section XI, AppendixVIII, Supplements 4 and 6) were also implemented for RPV weld inspection.

These more sensitive inspections detected existing fabrication flaws that were confirmed by review of construction radiographs.

During the performance of Class 2 weld inspections, one service related defect was detected at astiffener plate weld adjacent to a vessel support ring on the Division 2 RHR heat exchanger.

Thedefect appeared to have originated from a pre-existing construction flaw in the stiffener plate weld tie-in at the support ring weld and propagated into the base material in the heat affected zone of the stiffener plate. The inspection sample was expanded to include all of the stiffener plate welds at that location. No additional indications were detected.

The defect was documented on CARD 01-20653, and the defect was ground out and repaired by welding. The repaired area was then reinspected to verify defect removal.No other service related conditions were noted during RF08 inspections.

5.6.3 Component SupportsSeveral hangers were found with discrepancies between the installed condition and their configuration documents.

It was determined that these conditions did not affect the components' operability and were not reportable. No additional supports were inspected as a result of these observations.

Hanger P45-3353-G14, which was not in the sample scope, was found by plant personnel to be pulled from the wall. A new baseplate was mounted and the strut returned to design settings.

An inspection scope expansion was initiated and all other supports on the P45-3353 line were inspected.

One minor discrepancy (loose jamb nut) was found and corrected.

It was determined that this did not impact component operability.

5.7 Refuel-07 Nondestructive examinations have verified that RPV and internals piping systems and supports are ingood structural condition and can support safe and reliable operation during this operating cycle.5.7.1 RPV Internals During RF07, inspections were conducted on numerous reactor vessel components utilizing the recommended inspection methods and techniques contained in various Boiling Water Reactor Vessel Internals Project (BWRVIP) inspection and examination guidelines as well as the augmented inspections identified in Section

3. While it is true that many of the guidelines are not yet approved by the NRC, the intent was to perform the highest quality visual inspections on RPV components. This proactive approach will assure the structural integrity of RPV components.

Inspections were initially scheduled for 50 percent of the Jet Pump risers and assemblies (Nos. 11 through 20) to comply with BWRVIP-41 inspection recommendations. These inspection points included welds not previously inspected.

During RF06, a crack of approximately 1 3/4 inches long was identified on the thermal sleeve to elbow weld (RS-1) on the riser of Jet Pump Nos. 7 and 8 at 1200 AZ. This indication was evaluated and found acceptable for continued operation without Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)85 repair. This indication was reinspected during RF07 and there was no observable change in length or width. This indication is within the allowable flaw acceptance tolerance for thislocation and repair is not necessary.

Reinspection of this indication will again be performed during RF08. This crack is similar to indications identified in at least 5 other BWR plants.

All accessible welds and locations on Jet Pump assemblies Nos.

11 through 20 were inspected and no recordable indications were identified. A baseline inspection has been completed for all Jet Pump welds (Nos. 1 through 20) with the exception of welds DF-3, AD-1 and AD-2.Inspection of these locations will be conducted during future outages when a technique is developed and qualified. Reinspections on 1 of the 20 original control rod blades (02-39)identified very little change from the cracking on the sheath area near the handle on blade identified in RF06. These indications were evaluated and are not detrimental to the operation of the control blade. While not a code inspection, several blades were periodically inspected as recommended by General Electric, following the chemistry transient in 1993.No new indications were identified on the steam dryer assembly welds in areas not previously inspected.

Both ISI and General Electric previously evaluated the indications.

No repairs were required during RF07.

In addition, selected linear indications on the steam dryer support ring were ultrasonically inspected to determine the depth. The indications are shallow, less than V2inch in depth, and pose no threat to the integrity of the steam dryer assembly. Visual and ultrasonic inspections will be performed during future outages.

Indications and conditions identified during previous outages were reinspected during RF06. The reinspection included the following items with no further degradation identified:

Core Shroud ID linear indication above the H2 weld." Steam Dryer tie rod nut to washer tack welds cracks and support ring.* RPV internal surfaces -"Bathtub Ring"." SRM / IRM Dry Tubes.The Jet Pump restrainer screws were again inspected (80 tack welds). The conditions were unchanged this outage on Jet Pump No. 15, which had one of 2 tack welds cracked.

No additional cracked welds were found. The condition identified previously did not require repair this outage.Extensive inspection of Core Spray internal piping and spargers were performed per BWRVIP-18 Guidelines.

No indications of cracking were identified.

All accessible areas of welds were inspected with the exception of the P-1 weld, which is inaccessible for inspection.

No adverse changes in existing indications were noted. The RPV internals are in very good condition to date. There is no service related degradation that should impact plant performance during the next operating cycle. Internal inspections are achieving their goal of detecting and monitoring degradation and effecting prudent repairs/replacement to maintain the plant in a safeand reliable manner.5.7.2 RPV External Volumetric and ASME Piping Weld Examinations No service related defects were detected by nondestructive examinations performed during RF07.

5.7.3 Component Supports Hanger El 1-3184-G18 was found to have a loose jamb nut on the main strut and was tightened.

It was determined that this condition did affect component's operability.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)86 Hangers N30-3258-G02, G03, G08, G10, GI1, G12, G14, G15, G16, N30-3259-G06, G07 and G08 were found with notches worn on the threaded rod at the top of the support. This condition was evaluated and it was determined that this did not impact component's operability.

Hangers N30-3258-G07 and G08 the notches were blended to remove sharp edges.Hangers N30-3258-G04 and G15 were found to be slightly outside their cold setting. It wasdetermined that this condition did not impact component's operability.

The hangers were reset to their cold position. These conditions were not reportable.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)87 SECTION 6 PROGRAM STATUS, ASME SECTION XI CREDIT -IWB, IWC & IWF Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)88 6.0 PROGRAM STATUS, ASME SECTION XI CREDIT -IWB, IWC, & IWF Interval 2, Period 3, Refuel-12 (Excludes Pressure Testing)6.1 CATEGORY B-A 6.1.1 CATEGORY: ITEM NO: System B-A B1.11 Total Comp.Pressure Retaining Welds in Reactor Vessel Shell Welds-Circumferential Total Requiring Examination 4(1)4(1)Examined To Date 0 0 Examined To Date (%)100% (1)100% (1)RPV TOTALS: 4 4 NOTE: (1) Relief Request RR-A25 was written to alleviate the need for examination of these welds beyond the overlap zone of the intersecting longitudinal seam.6.1.2 CATEGORY: ITEM NO: System B-A B1.12 Total Comp.Pressure Retaining Welds in Reactor Vessel Shell Welds -Longitudinal Total Requiring Examination 14 14 Examined To Date 14 14 Examined To Date (%)100%100%RPV TOTALS: 14 14 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)89 6.1.3 CATEGORY:ITEM NO: B-A B1.21 Pressure Retaining Welds in Reactor VesselHead Welds

-Circumferential System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)RPV 2 2 2 100%Closure Head RPV 21 (1) 1 100%Bottom Head TOTALS 4 3(1) 3 100%NOTE: (1) Some of these examinations are subject to limitations as identified in ISIiNDE Program Plan, Table A. Relief Request RR-A1 documents these limitations.

6.1.4 CATEGORY:

B-A ITEM NO: B1.22 Pressure Retaining Welds in Reactor VesselHead Welds

-Meridional System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)RPV 13 13 13 100%Closure Head RPV 17 10(1) 10 100%Bottom Head TOTALS: 30 23(1) 23 100%NOTE: (1) Some of these examinations are subject to limitations or are inaccessible as identified in ISI/NDE Program Table A. Relief Request RR-Aldocuments these limitations.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)90 6.1.5 CATEGORY: ITEM NO: B-A B11.30 Pressure Retaining Welds in Reactor Vessel Shell-To-Flange System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%) (1)RPV 1 1 1 100%TOTALS: 1 1 1 100%NOTE: (1) The examination of shell-to-flange welds may be performed during the first and third inspection periods in conjunction with the nozzle examinations of Exam. Cat.B-D (Program B). At least 50% of shell-to-flange welds shall be examined by the end of the first inspection period, and the remainder by the end of the thirdinspection period. (Ref. IWB-2500-1, Category B-A, Footnote (4)).6.1.6 CATEGORY:

B-A ITEM NO: B1.40 Pressure Retaining Welds in Reactor Vessel Head-To-Flange System Total Comp.Total Requiring Examination 1 1 Examined To Date 1 1 Examined To Date (%)100%

100%RPV TOTALS: 1 1 Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)91 CATEGORY B-A TOTALS Item No. Total Requiring Examination (3)Examined To Date (2)Minimum Required (%)(1)Maximum Allowed (%)(2)B1.11 4 4(4) 100% N/A B1.12 14 14 (100%) 100% N/A B1.21 3 3(100%) 100% N/A B1.22 23 19 (100%) 100% N/A B1.30 1 1(100%) 100% N/A B1.40 1 1(100%) 100% N/A TOTALS: 46 46 (100%) 100% 100%NOTES: (1) Table IWB-2500-1 allows deferral to the end of the inspection interval.(2) Exam percentage requirements are based on category totals, not item totals. Item percentages are provided for information only.(3) Some of these examinations are subject to limitations or are inaccessible as identified in ISI/NDE Program Plan A Table. Relief Request RR-A1 documents these limitations.

(4) Category B 1.11 circumferential welds are only partially examined at the intersection of the Category B 1.12 longitudinal welds in accordance with RR-A25 (BWRVIP-05) and are not individually tracked.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)92 6.2 CATEGORY B-D 6.2.1 CATEGORY: ITEM NO: System B-D B3.90 Total Comp.Full Penetration Welds of Nozzles in VesselsNozzle-To-Vessel Welds Total Requiring Examination 30 30 Examined To Date 30 Examined To Date (%) (1)100%

100%RPV TOTALS: 30 30 30 NOTE: (1) At least 25% but not more than 50% (credited) of the nozzles shall be examinedby the end of the first inspection period and the remainder by the end of the inspection interval (Ref. Table IWB-2500-1, Category B-D, Footnote (2).6.2.2 CATEGORY: ITEM-NO: System B-D B3.100 Total Comp.Full Penetration Welds of Nozzles in VesselsNozzle Inside Radius Section Total Requiring Examination 30 30 Examined To Date 30 30 Examined To Date (%)(1)100%100%RPV TOTALS: 30 30 NOTE: (1) At least 25% but not more than 50% (credited) of the nozzles shall be examinedby the end of the first inspection period and the remainder by the end of the inspection interval (Ref. Table IWB-2500-1, Category B-D, Footnote (2)).Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)93 CATEGORY B-D TOTALS Item No.Total Requiring Examination Examined to Date Minimum Required (%)(1)Maximum Allowed (%)(1)B3.90 30 30 (100%) 100% N/A B3.100 30 30 (100%) 100% N/A TOTALS: 60 60(100%) 100% N/A NOTE: (1) At least 25% but not more than 50% (credited) of the nozzles shall be examined by the end of the first inspection period and the remainder by the end of the inspection interval (Ref. Table "WB-2500-1, Category B-D, Footnote (2)).Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)94 6.3 CATEGORY B-F 6.3.1 CATEGORY:

B-F ITEM NO: B5.10 Pressure Retaining Dissimilar Metal Welds RPV Nozzle to Safe End Butt Welds > 4" Dia.System Total Comp.Total Requiring Examination Examined To Date Examined To Date RRS 12 5 5 100%CS 2 2 2 100%RPV 3 1 1 100%TOTALS: 17 8 8 100%6.3.2 CATEGORY:

B-F ITEM NO: B5.20 Pressure Retaining Dissimilar Metal Welds RPV Nozzle to Safe End Butt Welds < 4" Dia.System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)SLC 1 1 1 100%TOTALS: 1 1 1 100%6.3.3 CATEGORY:ITEM NO: B-F B5.130 Pressure Retaining Dissimilar Metal Welds Piping Butt Welds

> 4" Dia.System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)RHR 3 2 2 100%CS 2 2 2 100%RWCU 2 0 0 N/A TOTALS: 7 4 4 100%Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)95 CATEGORY B-F TOTALS Item No.Total Requiring Examination Examined to Date Minimum Required (%)Maximum Allowed (%)B5.10 8 8(100%) (2) (2)B5.20 1(3) 1(100%) N/A N/A B5.130 4 4(100%) (2) (2)TOTALS: 13(1) 13 (100%) 100% 100%NOTES: (1) Risk Informed Inservice Inspection (RIISI) Program sample size is 12, Item B5.20 is an augmented requirement only.(2) Exam percentage requirements are based on Category totals, not item totals. Item percentages are supplied for information only.(3) The item listed under B5.20 is a GE SIL No. 571 recommended exam and is not counted for the purposes of Code inspection percentages.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, M1 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)96 6.4 CATEGORY B-G-1 6.4.1 CATEGORY:ITEM NO: System B-G-1 B6.10 Total Comp.Pressure Retaining Bolting Greater than 2" in Dia.Closure Head Nuts Total Requiring Examination 68 Examined To Date 68 Examined To Date (%)100%RPV 68 TOTALS: 68 68 68 100%6.4.2 CATEGORY: ITEM NO: System B-G-1 B6.20 Total Comp.Pressure Retaining Bolting Greater than 2" in Dia.Closure Studs in Place Total Requiring Examination 64(1)64(1)Examined To Date 64 64 Examined To Date (%)100%100%RPV TOTALS: 68 68 NOTE: (1) Inspections are performed in conjunction with Item No. B6.30.

Four (4) studs are removed at each Reactor Refueling Outage.6.4.3 CATEGORY:

B-G-1 ITEM NO: B6.30 Pressure Retaining Bolting Greater than 2" in Dia.Closure Head Studs when removed System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)RPV 68 4(1) 4 100%TOTALS: 68 4(1) 4 100%NOTE: (1) Inspections are performed in conjunction with Item No. B6.20.

Four (4) studs are removed at each Reactor Refuel.'Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)97 6.4.4 CATEGORY:ITEM NO: System RPV TOTALS: 6.4.5 CATEGORY:ITEM NO: B-G-1 B6.40 Total Comp.Pressure Retaining Bolting Greater than 2" in Dia.Reactor Vessel Threads in Flange Total Requiring Examination 68 68 Examined To Date 68 68 Examined To Date (%)100%100%68 68 B-G-1 B6.50 Pressure Retaining Bolting Greater than 2" in Dia.Reactor Vessel Closure Washers, Bushings (When Removed)System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)Washers RPV 68 68 68 100%Bushings 68 4(1) 4 100%(1)TOTALS: 136 72(1) 72 100%NOTE: (1) Inspection of bushings is only required for connections that are disassembled.

Studs 48-51 are removed to facilitate fuel movement.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)98 6.4.6 CATEGORY: B-G-1 Pressure Retaining Bolting Greater than 2" in Dia.ITEM NO: B6.180 Pumps, Bolts and Studs System Total Comp.Total Requiring Examination 32 32 Examined To Date 32 32 Examined To Date NO%100%100%RRS TOTALS: 32 32 6.4.7 CATEGORY:

B-G-1 ITEM NO: B6.200 Pressure Retaining Bolting Greater than 2" in Dia.Pumps, Nuts, Bushings and Washers (1)System Total Comp.Total Requiring Examination Examined To Date (1)Examined To Date (%)RRS 32 32 32 100%TOTALS: 32 32 32 100%NOTE: (1) Inspections are performed in conjunction with Stud UT inspection per item B6.180.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)99 Item No.B6.10 B6.20 B6.30 B6.40 B6.50 B6.180 B6.200 TOTALS: NOTES: (1) Ex pe CATEGORY B-G-1 TOTALS Total Examined Minimum Requiring To Date Required Examination

(%)68 68 (100%) (1)64 64(100%) (1)4 4(100%) (1)68 68 (100%) (1)72(2) 72(100%) (1)32 32 (100%) (1)32 32 (100%) (1)340 340 (100%) 100%Maximum Allowed (%)(1)(1)(1)(1)(1)(1)(1)100%am percentage requirement are based on Category totals, not item totals. Item rcentages are shown for information only.(2) Inspection of bushings is only required for connections that are disassembled.

Detroit Edison Co., One Energy Plaza, Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)100 6.5 CATEGORY B-G-2 6.5.1 CATEGORY: ITEM NO: System B-G-2 B7.10 Total Comp.Pressure Retaining Bolting 2" and smaller in Dia.Reactor Vessel-Bolts, Studs and Nuts Total Requiring Examination 3 (1)3(1)Examined To Date 3 Examined To Date (%)100%100%RPV TOTALS: 3 3 3 NOTE: (1) Represents Flanged/Bolted Connections-All bolts, studs and nuts were examined for each flanged connection examined.6.5.2 CATEGORY:ITEM NO: System B-G-2 B7.50 Total Comp.Pressure Retaining Bolting 2" and smaller in Dia.Piping-Bolts, Studs and Nuts Total Requiring Examination 2(1)Examined To Date 2 Examined To Date (%)100%HPCI& RCIC TOTALS: 2 2 2(1)2 100%NOTE: (1) Represents Flanged/Bolted Connections-All bolts, studs and nuts were examined for each flanged connection examined.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)101 6.5.3 CATEGORY:ITEM NO: System B-G-2 B7.60 Total Comp.Pressure Retaining Bolting 2" and smaller in Dia.Pump Bolts, Studs and Nuts, and Seal Bolting Total Requiring Examination 2(1)2(1)Examined To Date 2 2 Examined To Date (%)100%100%RRC TOTALS: 2 2 NOTE: (1) Represents flanged/bolted connections-all bolts, studs and nuts are examined for each connection examined.6.5.4 CATEGORY:ITEM NO: System B-G-2 B7.70 Total Comp.Pressure Retaining Bolting 2" and smaller in Dia.Valves-Bolts, Studs and Nuts Total Requiring Examination (1)Examined To Date (2)Examined To Date (%)MS RRS RHR CS HPCI RCIC RWCU FW 38 4 10 6 3 3 9 8 38 4 10 6 3 3 9 8 38 4 10 6 3 3 9 8 100%100%100%100%100%100%100%100%TOTALS: NOTES: 81 81 81 100%(1) Represents flanged/bolted connections-all bolts, studs and nuts were examined for each flanged connection examined.(2) All replacement bolting material utilized was visually inspected.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)102 6.5.5 CATEGORY: B-G-2 Pressure Retaining Bolting 2" and smaller in Dia.ITEM NO: B7.80 CRD Housings-Bolts, Studs and Nuts System Total Comp.Total Requiring Examination 185 (1)Examined To Date 118 sets*118 sets*Examined To Date (%)63.7%63.7%CRD TOTALS: 185 185 185 (1)* 100% of disassembled flange bolting.NOTE: (1) Inspections are only required when CRD Housing Flanges are disassembled (Ref.Table IWB-2500-1, Category B-G-2).Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)103 CATEGORY B-G-2 TOTALS Item No.Total Requiring Examination Examined To Date (2)Minimum Required (%)Maximum Allowed (%)B7.10 3 3(100%) (1) (1)B7.50 2 2(100%) (1) (1)B7.60 2 2(100%) (1) (1)B7.70 81 81(100%) (1) (1)B7.80 185(2) 118 (63.7%) (2) (2)TOTALS: 88 88 (100%) 100% 100%NOTES: (1) Exam percentage requirements are based on category totals not item totals. Item packages are supplied for information only.(2) Inspections are only required when CRD housing flanges are disassembled, therefore, they are not counted in the Code percentage totals.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)104 6.6 CATEGORY B-H 6.6.1 CATEGORY: B-H Integral Attachments for Vessels Reactor Vessel-Integrally Welded Attachments ITEM NO: B8.10 System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)RPV 1 1 1 100%Support Skirt Stabilizer 8 1 1 100%Bracket Welds Top Head 4 4 4 100%Lifting Lugs TOTALS: 13 6 6 100%6.7 CATEGORY B-J 6.7.1 CATEGORY:

B-J ITEM NO: B9.11 Pressure Retaining Welds in Piping Circumferential Welds > 4" Dia.System Total Comp.Total Requiring Examination (1)Examined To Date Examined To Date (%)MS RRS RHR CS HPCI RCIC RWCU FW RPV 113 109 71 42 14 16 70 123 5 11 15 5 3 2

2 7 18 0 11 15 5 3 2 2 7 18 0 100%100%100%100%100%100%100%100%N/A TOTALS: 563 63 63 100%NOTE: (1) Risk Informed Inservice Inspection (RIISI) Program sample size.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)105 CATEGORY B-J TOTALSItem No.Total Requiring Examination (1)63 Examined To Date Minimum Required (%)(1)100%Maximum Allowed (%)(1)100%B9.11 63 (100%)NOTE: (1) Fermi Risk Informed Inservice Inspection Program sample size.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, M1 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)106 6.8 CATEGORY B-K-1 6.8.1 CATEGORY: B-K-1 Integral Attachments for Piping Pumps and Valves ITEM NO: B 10.10/B 10.20 Piping-Integrally Welded Attachments System Total Comp.(1)Total Requiring Examination (2)Examined To Date Examined To Date (%)(3)All Class 1 13 2 locations 2 locations 100%Piping B 10.10 (8 welds) (8 welds)Pumps B10.20 3 1 1 100%TOTALS: 16 3 3 100%NOTES: (1) Total component supports with integral attachments selected for examination perCode Case N-491-1.(2) Total examinations required for integral attachments perCode Case N-509.

(3) One location examined each period.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)107 6.9 CATEGORY B-M-2 6.9.1 CATEGORY: B-M-2Valve Bodies Valve Body, exceeding 4" Nominal Pipe Size ITEM NO: B12.50 System Total Comp.MS RRS RHR CS HPCI RCIC RWCU FW 23 4 10 6 3 1 5 8 Total Requiring Examination 23 4 10 6 3 1 5 8 Examined To Date (1)8 1 3 2 1 0 0 6 Examined To Date (%)34.8%25%30%33.3%33.3%0%0%75%TOTALS: 60 60 21 35%(1)NOTE: (1) Per ASME Section XI JWB-2500-1, Table B-M-2 table note, the examinations are limited to one valve within each group of valves that are of the same constructional design and perform similar functions in the system. VT-3 inspections are performed on all Class 1 valves during disassembly for maintenance.

Specific percentages are not required.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date:

1-23-88 NB No. 21085 (RPV)108 6.10 CATEGORY B-O 6.10.1 CATEGORY: ITEM NO: System B-O B14.10 Total Comp.40 40 Pressure Retaining Welds in Control Rod Housings (2) Reactor Vessel-Welds in CRD Housings Total Examined Examined Minimum Max Requiring To To Date Required All Examination Date (%) (%) (%)8(1) 8 100% 100%

1C 8(1) 8 100% 100% 100 imumn owed%0%% (3)RPV TOTALS: NOTES: (1) 10% of peripheral housings (2 welds per housing).

(2) B 14.10 is the only Item for this Category.(3) Examinations evenly spaced during each period of the inspection interval.6.11 CATEGORY C-A 6.11.1 CATEGORY: ITEM NO: System C-A C1.10 Total Comp.1 1 Pressure Retaining Welds in Pressure Vessel Shell Circumferential Welds Total Examined Examine'Requiring To To DateExamination Date

(%)1 1 100%1 1 100%d RHR TOTALS: Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)109 6.11.2 CATEGORY: C-A Pressure Retaining Welds in Pressure Vessel Head Circumferential Welds ITEM NO: C1.20 System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)RHR 1 1 1 100%TOTALS: 1 1 1 100%CATEGORY C-A TOTALSItem No.Total Requiring Examination Examined To Date Minimum Required (%)Maximum Allowed (%)C1.10 1 1(100%) N/A N/A C1.20 1 1(100%)

N/A N/A TOTALS: 2 2(100%) N/A (1) N/A (1)NOTE: (1) Since there are only 2 items in this category requiring examination, the exams were scheduled for the 1 st and 3 rd period.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)110 6.12 CATEGORY C-B 6.12.1 CATEGORY: C-B Pressure Retaining Welds in VesselsNozzle-To-Shell (or Head) Weld ITEM NO: C2.21 System Total Comp.Total Requiring Examination 2 Examined To Date 2 Examined To Date (%)100%RHR 4 TOTALS: 4 2 2 100%6.12.2 CATEGORY:

C-B ITEM NO: C2.22 Pressure Retaining Nozzle Welds in VesselsNozzle Inside Radius Section System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)RHR 4 2 2 100%TOTALS: 4 2 2 100%CATEGORY C-B TOTALS Item No.Total Requiring Examination Examined To Date Minimum Required (%)Maximum Allowed (%)C2.21 2 2(100%) N/A N/A C2.22 2 2(100%) N/A N/A TOTALS: 4 4(100%)N/A(1)N/A (1)(1) Since there are only 2 nozzles in this category requiring examination, the exams were scheduled for the 1 st and 3 rd period.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)111 6.13 CATEGORY C-C 6.13.1 CATEGORY: ITEM NO: C-C C3.10 Integral Attachments for Vessels, Piping, Pumps and Valves Pressure Vessels System Total Total Comp. (1) Requiring Examination Examined To Date Examined To Date (%)(2)RHR 5 1 (19 welds) 19 welds 100%TOTALS: 5 1 (19 welds) 19 welds 100%NOTES: (1) Total component supports with integral attachment welds selected for examination per Code Case N-49 1-1.(2) Total examinations required for integral attachment welds per Code Case N-509.

6.13.2 CATEGORY: ITEM NO: C-C C31.20 Integral Attachments.

for Vessels, Piping, Pumps and Valves Piping Integrally Welded Attachments System Total Comp. (1)Total Requiring Examination (2)Examined To Date Examined To Date (%)All Class 2 46 5 5 100%Systems TOTALS: 46 5 5 100%NOTES: (1) Total component supports with integral attachment welds selected for examination per Code Case N-49 1-1.(2) Total examinations required for integral attachment welds per Code Case N-509.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)112 CATEGORY C-C TOTALS Item No.Total Requiring Examination Examined To Date Minimum Required (%)-Maximum Allowed (%)C3.10 1 1(100%) N/A N/A C3.20 5 5(100%) N/A N/A TOTALS: 6 6(100%) 100% 100%Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)113 6.14 CATEGORY C-F 6.14.1 CATEGORY: C-F-1 Socket Welds (1)NRC Augmented Commitment ITEM NO: N/A System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)SLC 131 16 16 100%TOTALS: 131 16 16 100%NOTE: (1) The Class 2 portion of the Standby Liquid Control System is < 4" NPS and is exempt per ASME Section XI. Fermi is committed to examine 16 of 131 systemwelds during each inspection interval.6.14.2 CATEGORY: C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel Piping ITEM NO: C5.51

/ C5.81 Piping Welds > 3/8" in Normal Wall Thickness for Piping > 4"NPS System Total Comp.Total Requiring Examination Examined To Date Examined To Date (%)MS 74 6 6 100%CRD 34 3 3 100%RHR 464 34 34 100%CGC 113 6 6 100%HPCI 154 12 12 100%CS 196 15 15 100%Containment Piping (1) 279 23 23 100%TOTALS: 1314 99 99 100%NOTE: (1) Containment piping includes augmented selections made in accordance with Relief Request RR-A26.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)114 CATEGORY C-F TOTALSItem No.Total Requiring Examination (1)Examined To Date Minimum Required (%)(2)Maximum Allowed (%)(2)C-F-1 (Augmented) 16 16 (100%) N/A N/A C-F-2 (C5.51 / C5.81) 99 99 (100%) N/A N/A TOTALS: 115 115(100%) 100% 100%NOTES: (1) Includes Augmented Class 2 selections.

(2) Exam percentage requirements are based on Category C-F totals, not item totals.Item percentages are supplied for information only.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)115 6.15 CATEGORY F-A 6.15.1 CATEGORY: ITEM NO: F-A Code Case N-491-1 F1.10-F1.40 (1)Section XI Class System No.System TD Class 1 F1.10 B21 B31 Ell E21 E41 E51 G33 N21 Steam SupplyReactor Recirc RHR CS HPCI RCIC RWCU Feedwater CLASS 1 TOTALS Total (1)Requiring Examination 8 3 3 3 1 1 5 5 29 Examined To Date 8 3 3 3 1 1 5 5 29 Examined To Date (%)100%100%100%100%100%

100%100%100%100%Class 2 F1.20 B21 Cll Ell E21 E41 N30 Pll T48 SRV CRD RHR CS HPCI MS Demin GCG 6 4 42 17 15 6 1 16 6 4 42 17 15 6 1 16 100%100%100%100%100%100%100%100%CLASS 2 TOTALS 107 107 100%Class 3 Eli RHRSW 15 15 100%F1.30 P42 RBCCW 1 1 100%P44 EECW 33 33 100%P45 EESW 18 18 100%R30 DGSW 12 12 100%CLASS 3 TOTALS 79 79 100%Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)116 CATEGORY F-A TOTALS Supports Other Than Piping Supports F1.40 Bll B31 C41 Ell E21 E41, P44 P45 R30 T23 RPVReactor Recirc SLC RHR CS HPCI EECW EESW DGSW PRIMARY CONT.F1.40 TOTALS 9 9 100%4 1 7 1 3 4 1 4 28 4 1 7 1 3 4 1 4 28 100%100%100%100%100%100%100%100%100%62 62 100%Item No.F-A F1.10 F-A F1.20 F-A F1.30 F-A F1.40 TOTALS: Total Requiring Examination 29 107 79 62 277 Examined To Date 29 107 79 62 277 Examined To Date (%)100%100%100%100%100%Minimum Required (%)N/A N/A N/A N/A 50%Maximum Allowed (%)N/A N/A N/A N/A 100%Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)117 SECTION 7 UPDATED PROGRAM TABLES Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)118 7.1 PROGRAM TABLES 7.1.1 Inservice Inspection Program (Plan) Tables (NDE)The accompanying table lists the components or areas that are to be examined during the interval as updated for this refueling outage. Listed in an order following the items presented in the ASME Section XI, Subsections IWB, IWC, and IWD, the tables contain the following information:

Code Class: is the ASME class as defined in accordance with the Code of Federal Regulations (10CFR50.55a), Regulatory Guide 1.26, and NUREG-0800.

Interval: refers to the 120 month inspection interval as identified in Section 1.0 of this document.Page/Rev.:

indicates the consecutive and total page numbers for the NDE program. Rev. or Revision indicates the revision of the individual page or entire document.Code Category:

is the Examination Category as defined by ASME Section XI, SubarticlesIWB-2500, IWC-2500 or IWD-2500.Item Number:

lists the Item No. as defined by ASME Section XI, Subarticles IWB-2500, IWC-2500, or IWD-2500.

Note: all Item Numbers are addressed even though they may not be applicable to Fermi 2.Description and Unique Identification: repeats the generic descriptions listed in tables IWB-2500-1, IWC-2500-1 or IWD-2500-1. The components to be examined are then listed by system and/or specific identification.

Exam Method-Exam Method Selected:

identifies the code required method of examination, i.e., Volumetric, Surface, or Visual. The specific examination selected is shown for the component, i.e., UT, PT, MT, or VT (see list of abbreviations for expanded definitions).

Relief Request: if applicable, indicates the request for relief applicable in accordance with 10CFR50.55a(g)(5)(iii).Augmented Exam Method: indicates the examination was required to meet a regulatory orlicensing commitment and its outage code when completed or scheduled.

Sel. Basis: shows the abbreviation for the basis for selection of a component for'examination.

Period: marks the 40 month period within the 120 month interval when the examination is scheduled (3 periods per interval).

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)119 NOTE A schedule of specific examinations is provided for the second 10-year interval.

All exams are scheduled for inspection in accordance with the rules of ASME Section

-XI, IWA, TWB, IWC, IWVD and IWF, and as augmented by specific commitments (i.e., NUREG-0313).

Revisions to this program (plan) shall be issued to reflect actual examinations to be performed during each refuel outage as well as all examinations completed during previous outages.Remarks: are reserved for additional information to explain, amplify, or provide added details necessary to clarify the examination requirements.

7.1.1.1 Examination methods delineated in the following tables are intended to be representative of the ISI practice to be used or of preservice methods utilized.

In either case, it should be recognized that either UT or RT is an acceptable volumetric exam and either PT or MT is an acceptable surface exam.Unique weld joint parameters may, of course, dictate more restrictive selection criteria (e.g., highbackground radiation will preclude RT, stainless materials will preclude MT, etc.). It is intended that the process which selects exam methods for inspections under this plan treat UT and RT as interchangeable and PT and MT as interchangeable with consideration given to past practice in light of the reproducibility of results.7.1.1.2 List of Abbreviations The following abbreviations are used: Plant Identification System (PIS) -Codes for Plant Systems B21 -PIS Number for the Nuclear Boiler System B31 -PIS Number for the Reactor Recirculation System Cli -PIS Number for the Control Rod Drive System C41 -PIS Number for the Standby Liquid Control System El1 -PIS Number for the Core Spray System E41 -PIS Number for the High Pressure Coolant Injection System E51 -PIS Number for the Reactor Core Isolation Cooling System G33 -PIS Number for the Reactor Water Cleanup System G41 -PIS Number for the Fuel Pool Cooling System N21 -PIS Number for the Feedwater System N30 -PIS Number for the Main Steam System T48 -PIS Number for the Combustible Gas Control System Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)120 Acronyms Used to Identify Plant Systems CGC -Combustible Gas Control CRD -Control Rod Drive CS -Core Spray FPC -Fuel Pool Cooling HPCI -High Pressure Coolant Injection RCIC -Reactor Core Isolation Cooling RHR -Residual Heat Removal RRC -Reactor Recirculation RWCU -Reactor Water Cleanup SDV -Scram Discharge Volume SLC -Standby Liquid Control Nondestructive Examination Method Abbreviations MT -Magnetic Particle Examination PT -Liquid Penetrant Examination UT -Ultrasonic Examination VT -Visual Examination VT-1 -Visual Examination per IWA-2211 VT-2 -Visual Examination per IWA-2212 VT-3 -Visual Examination per IWA-2213 UT Mech. -UT Mechanized UT Mech./Man.-

UT Mechanized or Manual Weld Selection Basis Abbreviations HCU -High Cumulative Usage HS -High Stress MS -Moderate Stress R -Random selection of structural discontinuity weld TE -Terminal End A -Augmented DM -Dissimilar Metal Weld RI -Risk Informed Methodology Degradation Mechanisms IGSCC -Intergranular Stress Corrosion Cracking CC -Crevice Corrosion TASCS -Thermal Fatigue Cracking Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)121 Plant Components and Weld Terminology Abbreviations CRDH -Control Rod Drive Housing EXPJT -Pipe Expansion FBC -Field Weld HX -Heat Exchanger HXS -Heat Exchanger Shell IBR -Inner Bore Region (Nozzle)IIH -Incore Instrumentation Housing LD -Longitudinal Downstream (Seam Weld)LU -Longitudinal Upstream (Seam Weld)PAD -Integral Attachment Weld Directly onto the Pressure Boundary of the Pipe PSFW -Piping Support Field Weld PS -Primary Steam (Nuclear Steam Supply System)RD -Recirculation Discharge RS -Recirculation Suction SDV -Scram Discharge Volume SW -Shop Weld TRUNION -Hanger Support Welded Directly onto the Pressure Boundary of the Pipe VBB -Valve Body and Bonnet Housing Generic Miscellaneous Abbreviations BWR -Boiling Water Reactor CRC -Corrosion Resistant Cladding DWG -Drawing DM -Dissimilar Metal Weld EF2 -Enrico Fermi 2 in. -Inches N/A -Not Applicable NUREG -Nuclear Regulatory Guide PWR -Pressurized Water Reactor RR -Relief Request RPV -Reactor Pressure Vessel Component Support Abbreviations A -Anchor C -Constant Support G -Guide R -Rigid Support SP -Spring Hanger Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)122 Outage Codes, x Exam Status "Y" can equal the following codes: C = Completed S = Scheduled CP = Completed Partial CPL = Completed Partial Limited____Refuel Outage Sequential Number Example: 07C 08S 08CP 08CPL= Seventh Refueling Outage, Completed Exam= Eighth Refueling Outage, Scheduled Exam= Eighth Refueling Outage, Completed Exam, Partial= Eighth Refueling Outage, Completed Exam, Partial Limited Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)123 7.1.2.2 List of Abbreviations For definitions of abbreviations used in the following tables, refer to Paragraph 10.1.2 of this document.7.1.2.3 Inservice Inspection Program (Plan) Tables (NDE)" Table A -Class 1, 2, and 3 Welds and Components

Table B -Supports* Table C -Snubbers 7.1.3 NOTES NOTE 1 Examination categories B-F and B-J contain duplicate examination requirements for dissimilar metal pressure retaining welds in piping. Category B-J does not have a separate item number for dissimilar metal (DM) welds. Because of this, all DM welds will be included in category B-F. This will aid in identifying those welds that may have additional augmented, regulatory, or PDI requirements applied to them.NOTE 2 In response to Generic Letter (GL) 88-01 and NUTREG-0313 Rev. 2, Detroit Edison had committed in NRC-88-0243, NRC-89-0297, and NRC-90-0103 to the inservice inspection requirements for austenitic stainless steel welds in accordance with the guidelines of Generic Letter 88-01. All applicable welds have been classified according to NUREG-0313 Rev. 2 requirements with the required percentages of welds being included in this program. The applicable category (GL 88-01) is identified in the remarks column. All inspections will be performed utilizing procedures and personnel qualified to current Utility PDI Guidelines.

In correspondence letter NRC-0 1-0038, Detroit Edison had committed to use the NRC approved Generic Letter 88-01 alternative inspection schedule requirements of BWRVIP-75.

Sample expansion will be as specified in the Fermi RiskInformed Inservice Inspection Program for Category A welds, and BWRVIP-75 for allother augmented weld selections. Methods and criteria for crack evaluation and repair shall be in conformance with IWB-3600 of Section XI of the 1989 Edition of ASME Boiler and Pressure Vessel Code. Detroit Edison requested that Non-Safety Related, Category D welds be removed from GL 88-01 scope per NRC-92-0090. The NRC response (TAC No. M84117, dated December 18,1992) modified the inspection interval such that inspection of the subject piping welds on a sampling basis of at least 10 percent of the weld population be performed during each refueling outage.NOTE 3 Per the EF-2 UFSAR Subsection 4.5.1.2.7, Detroit Edison had agreed to ultrasonically inspect the RPV Jet Pump Hold Down Beams at each Reactor Refueling Outage until sufficient experience was gained to change the frequency of inspection.

If a cracked beam were detected, it would be replaced prior to return to power operation. Due to the failure of a jet pump hold down beams at another plant, SIL No. 330, Supplements 1 and 2, and Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MN 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)125 RICSIL No. 065 were issued.

As a result, all jet pump hold down beams were replaced with beam assemblies that are less susceptible to IGSCC than the original assemblies during RF04. Subsequent UT and alternative inspections will be performed at futurerefueling outages based on industry experiences andthe recommendations provided in IE Bulletin 80-07, NUREG/CR-3052, and the latest edition of BWRVIP-41. All beams were reinspected in RF09 and RF 12.NOTE 4 ASME Section XI Category B-E requires inspection of the external surfaces of 25 percentnozzles among each group of penetrations of comparable size and function.

Fermi practice is to perform a VT-2 examination inside the RPV bioshield annulus for RPV instrumentation nozzles, and of the bottom head penetrations through the skirt hatches, and under vessel during the system leakage test each refueling outage. If leakage isidentified, further investigation will be made to identify the exact location.NOTE 5 Component supports and the associated integrally welded attachments are selected for examination in accordance with Code Cases N-491-1 (Alternative Requirements for Selection and Examination of Component Supports) and N-509 (Alternative Rules for the Selection and Examination of Integrally Welded Attachments).

NOTE 6 Visual examination of snubbers covers only the snubber unit, except for those snubber supports selected in accordance with Code Case N-49 1-1. The balance of the support (integral and nonintegral attachments including lugs, bolting, pins, clamps, and support steel) will be visually examined in accordance with subsection IWE requirements.

NOTE 7 Per SIL No. 420, an inspection will be performed on the jet pump sensing lines and support brackets when convenient.

This inspection will determine if the weld between the support brackets and the vertical run of the sensing line is intact. Additionally, the inspection should concentrate on the jet pumps closest to the recirculation outlet nozzles.Inspection will be performed on the Jet Pumps scheduled for inspections during the refueling outage. Per SIL 420, Revision 1 it was determined that inspections need to beperformed on exit lines closest to the Jet Pump Instrumentation Nozzles.

As a result inspections are performed more frequently on Jet Pump Lines 6, 7, 16, and 17.NOTE 8 Per NRC Information Notice No. 90-30, all dissimilar metal welds containing Inconel 600 series base materials, Alloy 82 and 182 weld butter, and/or filler metal shall be examined following the guidelines of SIL No. 455. It is essential and required that all examinations be performed by the use of multiple refracted longitudinal waves (450 and 600 recommended) for crack detection and sizing in the Alloy 182 material and the low alloy material.

All scanning of welds will be performed in both an axial and circumferential direction followed by a 45' shear wave if indications are identified using refractedlongitudinal techniques. Examination of nozzle welds shall include the full thickness volume and be extended into the area of Alloy 182 Weld Material Buttering.

The purpose of this additional/supplemental examination is to assure that Alloy 182 Butter Cracking in the nozzle bore has not occurred and extended into the low alloy nozzle material.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)126 Beginning with RF09, ASME Section XI, Appendix 8, Supplement 10 requirements as implemented by the Utility Performance Demonstration Initiative are mandatory.

NOTE 9 Per SIL No. 433, Supplement 1, an Ultrasonic (UT) inspection of the entire shroud head bolt length was performed on the 48 shroud head bolts for evidence of cracking during RF04. All bolts have been replaced with a new design that is more resistant to cracking.Based on industry experience, additional inspections will be performed at subsequent refuel outages.NOTE 10 During RF06, the Reactor Recirculation pumps were modified to the 4th generation design configuration.

This configuration was designed to mitigate known causes of shaft andcover cracking and provides for ultrasonic inspection of the shaft without requiring complete pump disassembly and removal. This modification also included a change out ofthe rotating element to a welded impeller and added rotating baffle. In addition, the hydrostatic bearing was modified to a non-welded design. The need to completely disassemble is reduced by modification to the 4th generation configuration.

The following augmented inspections will be performed if the pump is disassembled.

Per SIL No. 415, asupplemental liquid penetrant or volumetric inspection of the suction splitters will-be performed if visual inspections identify cracking of the suction splitters or attachment welds. Per RICSIL No. 038 and NRC Information Notice 89-20, inspections will be performed on the hydrostatic bearing and baffle plate. Inspection of the heater/cooler assembly should be performed if the pump is disassembled.

Disassembly of the pump for inspections will be evaluated prior to each refuel outage based upon industry experience and hours of operation.

NOTE 11 Per SIL No. 474, a visual inspection will be performed on steam dryer drain channel welds during refueling outages. Portions of the steam dryer assembly, dryer banks, and welds will be visually inspected each refueling outage, following inspection recommendations contained in BWRVIP-139 as detailed in PEP16, Appendix XII.NOTE 12 Per IE Bulletin 80-13, and SIL No. 289, Revision 1, Supplement 2, a visual inspection is performed on the core spray internal piping each refueling outage. Inspection points include those identified in IE Bulletin 80-13, SIL No. 289, Revision 1, Supplement 2, and BWRVIP-18. The inspection plan will follow the inspection recommendations and frequency provided in BWR VIP- 18 as detailed in the Performance Engineering Program (PEP) 16, Appendix III.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)127 NOTE 13 Per SIL No. 462, inspection of the shroud support access hole cover was performed at the end of the first 10-year interval. Subsequent reinspections will be based on industry experience and the inspection technique applied (Reference PEP 16, Appendix II).NOTE 14 All inservice examinations of the Reactor Pressure Vessel welds will be performed using both manual and mechanical examination techniques and will most likely be performedfrom the outside of the vessel.

Limitations encountered that affect the examination volume as prescribed by ASME Section XI will be documented in an examination report.

All previous examinations were conducted in accordance with the requirements of Regulatory Guide 1.150, Revision 1, to the extent practical (Reference NRC-87-0078).

Beginning with RF08, ASME Section XI, Appendix VIII, Supplements 4 and 6, requirements for vessel welds were implemented as specified in 10CFR50.55a.Indications, regardless of amplitude, will be recorded on tape during the mechanized examination for analysis. Similarly, signal responses will be scrutinized during themanual examination process and indications will be recorded for further analysis and resolution.

NOTE 15Visual inspections for leakage required by ASME Section XI Code Categories B-P, C-H, and D-B are performed using site procedures. Test packages for all tests performed aredeveloped utilizing the Inservice Inspection Classification Boundary Drawings listed on Table A-5-5.1 as the basis.All components on the following systems are included in the Class 1 inspections:

B21, B31, C41, El1, E21, E41, E51, G33, N21, and P34.All components on the following systems are included in the Class 2 inspections:

C11, C41, E11, E21, E41, G41, G51, Ni1, N30, P34, T4804, and T50.All components on the following systems are included in the Class 3 inspections:

El 1, P42, P44, P45, and R30.NOTE 16 Per RICSIL No. 059 and SIL No. 554, inspection of the top guide beams should be performed at grid locations where fuel and blade guides have been removed for otherreasons. Inspection of selected grid locations will be performed during refueling outages.Additionally, ultrasonic inspection should be considered if cracking is found or as recommended by SIL No. 554.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy.; Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)128 NOTE 17 The extent of inspection and frequency for Jet Pump components and welds will follow the recommendations provided in BWRVIP-4 1. BWRVIP-41 replaced/modified the recommendations of SIL Nos. 551 and 574. Inspections will continue to be performed per the recommendations of SIL No. 574 on the adjusting screw tack welds in conjunction with the inspection of those Jet Pump wedges scheduled for inspection each refueling outage or if wear damage is identified.

Repairs, if required, will be performed inaccordance with the recommendations of SIL No. 574 as appropriate.

In addition, verification of contact will be performed on the restrainer screws and wedge assembly to the inlet mixer on Jet Pump wedges selected for inspection if wear or damage is identified as per the recommendations of RICSIL No. 078 and BWRVIP-41, Rev 1.NOTE 18 Per recommendation of SIL No. 571, augmented inspection of this stainless steel nozzle should be performed after 15 years of operation.

The inspection boundary for this weld shall be extended to include all stainless steel material accessible for ultrasonic examination.

If linear surface indications are found, ultrasonic examination should be used to determine crack depth. Inspection frequency has been modified per BWRVIP-27 to a 10 -year reinspection period.NOTE 19 Visual inspection of the core shroud and shroud welds will be performed in accordance with the recommendations contained in BWRVIP, "BWR Core Shroud Inspection and Flaw Evaluation Guideline,"(BWRVIP-0

1) utilizing techniques detailed in BWRVIP,"Reactor Pressure Vessel and Internals Examination Guidelines," (BWRVIP-03).

SWL No.572, Revision 1 inspection recommendations have been superseded. Fermi 2 has committed to perform future inspections per the guidance of the BWRVIP. Visual inspections will be performed as an enhanced EVT- 1 inspection with the capability to resolve a 1/2-mil wire on the inspection surface. The BWRVIP has imposed additionalguidelines for inspection based on years of operation, materials, and conductivity. Basedon the above, during RF06, a baseline inspection of the shroud welds (H-3, H-4, H-5, and H-7) was completed (approximately 90 percent volumetric coverage) utilizing anaugmented ultrasonic phased array technique with no indication of service induced flaws.Future Core Shroud inspections will be performed in accordance with the BWRVIP guidelines in BWRVIP-07 and BWRVIP-76. Core shroud support inspections will follow BWRVIP-038 and BWRVIP-104 guidelines utilizing approved techniques. Evaluation of anomalies shall be in accordance with the BWR Core Shroud Evaluation Reports(BWRVIP-01 and GENE-523-A53-0494).

Additional references include SIL No. 572, Rev. 1, RICSIL No. 054, Rev. 1, RICSIL No.

068, RICSIL No. 077, Information Notices93-079 and 94-042, and Generic Letter (GL) 94-03. GL 94-03 required advanced notification to the NRC of the proposed plan for Core Shroud inspection, evaluationand/or repair.

Additional detail is provided in PEP 16, Appendix I. Core Shroud ultrasonic re-inspections were completed during RF12 (2007).

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)129 NOTE 20 Additional augmented examinations were performed during RF04 and changes were madeto the inspection schedule for selected nozzle welds following the Turbine Generator event and subsequent RPV chemistry transient for detection of IGSCC initiation.

NOTE 21 The new containment inspection requirements of ASME Section XI 1992 Edition, 1992 Addenda, in effect for the Second Ten-year inspection interval changed the way containment system piping (between the isolation valves) are classified for ISI. IWE-1220(d) specifies that containment system piping is exempt from IWE requirements; however, it shall be examined in accordance with the appropriate classification specified in the construction Design Specifications.

This varies from the assumptions made during the first interval, when no [WE requirements were imposed. Relief Request RR-A26 documents Detroit Edison's proposed alternative examination requirements.

NOTE 22 Inspections in addition to those listed for Item Nos. B13.10, B13.20, B13.30, and B13.40 will be scheduled and performed as detailed in PEP 16. Augmented inspection requirements for selected components and welds are detailed in PEP 16 Appendices, including the implementation of various BWRVIP inspection recommendations.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)130 ISI -NDE Program Rev. 6 Change 2 Page 1 INSERVICE INSPECTION NDE PROGRAMTABLE A DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 2 Category / Item Identification Exams Selection Basis Required Relief Inspection Period Isometric Request 1 2 3 Remarks B-A B1.11 1-313 4-308A 4-308B 9-307 Bl.12 1-308A 1-308B 1-308C 1-308D 15-308A 15-308B Circumferrential Shell Weld UT UT UT UT Longitudinal Shell Weld UT UT UT UT UT UT UT UT UT UT UT UT UT UT Circumferrential Head Weld UT All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 RR-A25 RR-A25 RR-A25 RR-A25 N/A N/A N/A N/A 08C 08C N/A N/A N/A N/A N/A N/A N/A N/A Examined only at intersecting long seams Examined only at intersecting long seams Examined only at intersecting long seams Examined only at intersecting long seams Note 14 Applies to all Category B-A Welds liC liC lOC 09C 10CP 12CP CARD 03-16383, RF10

& RF12 exam to sizeindication No.

124 only 15-308C 15-308D 2-307A 2-307B 2-307C 2-308A 2-308B 2-308C B1.21 4-319 08C 08C 12C 10C 09C 10C 09C 12C 08CP 09C 08 319C to 2-319E 40%9 319E to 2-319C 60%Inaccessible Weld 5-306 UT All B-A Welds 5360-5 RR-Al DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 3 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks B-A B1.21 5-319 6-306 B1.22 1-306A 1-306B 1-306C 1-306D 1-306E 1-306F 1-306G 1-306H 1-306J 1-306K 1-319A 1-319B 1-319C 1-319D 1-319E 1-319F 1-319G 1-319H 2-306A 2-306B 2-306C 2-306D 2-306E Circumferrential Head Weld UT UTMeridional Head Weld UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT All B-A WeldsAll B-A Welds All B-A Welds All B-A WeldsAll B-A WeldsAll B-A WeldsAll B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A WeldsAll B-A Welds All B-A WeldsAll B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds All B-A Welds 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 08CP 1OCPOne sided exam 180-360 Deg, RF08, 0-180 Deg, RF10 llC 08C 1oC 1OC 08C 08C 08C 12C llC 09C RR-Al RR-Al RR-Al RR-AI RR-Al RR-Al RR-Al RR-Al RR-A1 08C 08C 12C 12C 09C 1OC 1OC 12C 08C Inaccessible Weld Inaccessible Weld Inaccessible Weld Inaccessible Weld Inaccessible Weld DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 4 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks B-A B1.22 Meridional Head Wel 2-306F 2-306G 2-319A 2-319B-2-319C---

2-319D 2-319E B1.30 Shell to Flange Weld 13-308 (from flange)13-308 (from shell)

B11.40 Head to Flange Weld 3-319 Ud UT UT UT UT-U-T-UT UT All B-A Welds All B-A Welds All B-A Welds All B-A Welds All-B-A-Welds_

All B-A Welds All B-A Welds All B-A Welds All B-A Welds 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 53 60-5 RR-Al RR-AlInaccessible Weld Inaccessible Weld 08C 08C.08C-llC llC UT UT 5360-5 RR-Al 08CP 5360-5 RR-Al 08CP 0-180 Deg, RF-08; No longer required as RF-1 1exam achieved full coverage from ID.11C -120 Deg, RF-08 ; Complete exam at RF11 12CP 1/3 of weld each scheduled Inspection Period UT/MT All B-A Welds 5360-5 08CP 10CP B-D B3.100 RPV Nozzle Inside Radius Section 13-314A IRS VT13-314B IRS VT 13-314C IRS VT 13-314D IRS VT 13-314E IRS VT 13-314F IRS VT 13-314G IRS VT 13-314H IRS VT13-314J IRS VT 13-314K IRS VT 14-316A IRS VT 14-316B IRS VT All BD-IRS All BD-IRS All BD-IRS All BD-IRS All BD-IRS All BD-IRS All BD-IRS All BD-IRS All BD-IRS All BD-IRS All BD-IRS All BD-IRS 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 RR-A32 RR-A32 RR-A32 RR-A32 RR-A32 RR-A32 RR-A32 RR-A32 RR-A32 RR-A32 RR-A32 RR-A32 08C 08C 10C 09C 09C 09C 09C 12C 12C 12C 09C 08C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 5 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks B-D B3.100 15-315 IRS 19-314A IRS19-314B IRS 2-318 IRS 4-316A IBR 4-316A IRS 4-316B IBR 4-316B IRS 4-316C IBR 4-316C IRS 4-316D IBR 4-316D IRS 4-316E IBR 4-316E IRS 4-316F IBR4-316F IRS 4-318A IRS 4-318B IRS 5-314A IRS5-314B IRS 8-316A IRS 8-316B IRS 8-316C IRS 8-316D IRS B3.90 13-314A 13-314B RPV Nozzle Inside Radius Section VT VT VT VT UT UT UT UT UT UT UT UT UT UT UT UT VT VT VT VT VT VT VT VT All BD-IRS All BD Nozzles All BD Nozzles All BD Nozzles A All BD-IRS A All BD-IRS A-All BD-IRS A All BD-IRS A All BD-IRS A All BD-IRS All BD Nozzles All BD Nozzles All BD-IRS All BD-IRS All BD-IRS All BD-IRS All BD-IRS All BD-IRS All B-D Nozzles All B-D Nozzles 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 RR-A31 RR-A32 RR-A32 RR-A31 08C 08C IOC 10C 08CA 08CA 08CA 08CA 07CA 07CA 08CA 08CA 07CA 07CA 07CA 07CA NUREG-0619/GE-NE-523-A71-594 NUREG-0619/GE-NE-523-A71-594 NUJREG-0619/GE-NE-523-A71-594 NUREG-0619/GE-NE-523-A71-594 NUREG-0619/GE-NE-523-A71-594 NUREG-0619/GE-NE-523-A71:594 NUREG-0619/GE-NE-523-A71-594 NUREG-0619/GE-NE-523-A71-594 NUREG-0619/GE-NE-523-A71-594 NUREG-0619/GE-NE-523-A71-594 NUREG-0619/GE-NE-523-A71-594 NUREG-0619/GE-NE-523-A71-594 RR-A31 RR-A3 1 RR-A31 RR-A31 RR-A31 RR-A31 RR-A31 RR-A31 liC liC 12C 08C 08C 08C 12C 12C RPV Nozzle to Vessel Weld UT UT 5361-5 RR-A6 08C 5361-5 RR-A6 08C Note 14 Applies to all Category B-D Welds 13C DETROIT EDISON COMPANY -FERMI 2INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 6 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks B-D B3.90 13-314C 13-314D 13-314E 13-314F 13-314G 13-314H 13-314J 13-314K 14-316A 14-316B 15-315 19-314A 19-314B 2-318 4-316A 4-316B 4-316C 4-316D 4-316E 4-316F 4-318A 4-318B 5-314A 5-314B 8-316A 8-316B 8-316C RPV Nozzle to Vessel Weld UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles All B-D Nozzles 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 5361-5 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 RR-A6 08C 1OC 09C 09C 08C 12C 12C 13C.08C 08C 1OC 09C lOC lOC 08C 08C 08C 08C 09C 12C 12C lic llC 12C 08C 08C 08C 12C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 7 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks B-D B33-90 8-316D RPV Nozzle to Vessel Weld UT All B-D Nozzles 5361-5 RR-A6 12C B-E B4.11 17-315 Partial Penetration Vessel Nozzles VT-2 7-315 B4.12 VT-2 Partial Penetration CRD Nozzles 1-310-X_-Y_

(185)CRDH-Y-X (185)VT-2 VT-2 B4.13 2-315A 2-315B 2-315C 2-315D 2-315F Partial Penetration Instrumentation Nozzles VT-2 5361-5 5361-5 5363-5 5363-5 5361-5 5361-5 5361-5 5361-5 5361-5 5363-5 07C/ 09C/ I!C/08C 10C 12C 07C/ 09C/ 1 IC/08C IOC 12C 07C/ 09C/ i!C/08C 10C 12C 07C/ 09C/ liC/08C IOC 12C 07C/ 09C/ 11!C/08C 10C 12C 07C/ 09C/ I!C/08C 10C 12C 07C/ 09C/ 11!C/08C 10C 12C 07C/ 09C/ 11!C/08C 10C 12C 07C/ 09C/ 11C/08C 10C 12C 07C/ 09CI iIC Each Refuel Outage -Note 4 applies to all B-E Items Nozzle External Surfaces -Note 4 VT-2 VT-2 VT-2 VT-2 VT-2 IIH-X--Y-(55) 08C 10C 12C B-F B5.10 Dissimilar Metal RPV Nozzle to Safe End Weld 4" NPS and Larger 101-304E UT A, RI (IGSCC, CC) 5358-5 RR-A30 10C Notes 2 & 8 Cat. B DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 8 Category / Item Identification Exams Selection Basis Required Relief Inspection PeriodIsometric Request 1 2 3 Remarks B-F B5.10 2-303G 2-303H 2-303J 2-303K Dissimilar Metal RPV Nozzle to Safe End Weld 4" NPS and Larger UT A, RI (IGSCC, CC) 5356-5 UT UT UT A, RI (IGSCC, CC) 5356-5 A, RI (IGSCC, CC) 5356-5 A, RI (IGSCC, CC) 5356-5 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 09C 07C N5A UT A, (IGSCC, CC) 3053-5 N5B UT A, RI (IGSCC, CC) 3052-5-N-9 UT A, RI (IGSCC) 5361-5 B5.130 Dissimilar Metal Piping Butt Weld 4" NPS and Larger SW-El1-2298-6WC UT A, RI (IGSCC) 2298-5 SW-El1-2327-6WC UT A (IGSCC) 2327-5 SW-E21-3052-4WOX UT A, RI (IGSCC) 3052-5 SW-E21-3053-4WOX UT A (IGSCC) 3053-5 B5.20 Dissimilar Metal RPV Nozzle to Safe End Weld Less Than 4" NPS 5-315 PT A RI-91 5-315 UT A 08C 10C 09C Notes 2 & 8 Cat. B. No expanded CC exam volume for Trombone style safe-ends on recirc.12C Notes2 & 8 Cat. B, 12C Notes 2 & 8 Cat. B, Replaced original selection 102-304A, CARD 07-25329 13C Notes 2 & 8 Cat. B, Replaced original selection 4-303A CARD 07-26347 Notes 2 & 8 Cat. B 13C Notes2 & 8 Cat. B Notes 2 & 8 Cat. B Note 1 & 2, Category B 1IC Notes 1 & 2, Category B 13C Notes 1 ,2 & 8 Category B (IGSCC)Notes 1 ,2 & 8 Category B (IGSCC)Note 18 Note 18 RR-A30 08C RR-A30 08C 10C 07C 07C B-G-1 B6.10 RPV Closure Head Nuts Greater Than 2" 326-02, 1 through 68 VT >2 dia." B6.180 Pump Studs Greater Than 2" RRC Pump A, Studs 1 through 16 UT >2 dia." RRC Pump B, Studs 1 through 16 UT >2 dia." B6.190 Pump Flange Surface, When Disassembled RRC Pump A, Flange VT-1 >2 dia." RRC Pump B, Flange VT-1 >2 dia."B6.20 RPV Closure Studs Greater Than 2", In-place 5362-5 5365-5 5365-5 5365-5 5365-508CP 09CP 1lCP 1/3 Each Period, Code Case N-627 08C liC Perform if disassembled -N/A for 2nd Interval Perform if disassembled

-N/A for 2nd Interval DETROIT EDISON COMPANY

-FERMI 2INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE ProgramRev. 6 Change 2Page 9 Category / Item Identification Exams RequiredSelection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks B-C-1 B6.20 RPV Closure Studs Greater Than 2", In-place 326-01, 1 through 68 UT >2 dia." B6.200 Pump Nuts, Bushings, and Washers RRC Pump A Nuts, Bushings

& VT-1 >2 dia." Washers Set 1 -16 RRC Pump B Nuts, Bushings

& VT-i >2 dia." Washers Set I -16 B6.30 RPV Closure Studs Greater Than 2", When Removed 326-01, 1 through 68 MT/UT >2 dia." 5362-5 5365-5 5365-5 5362-5 5362-5 5362-5 5362-5 08CP 10CP llCP 1/3 EachPeriod 08C lic 08C 48-51 Removed for refueling, RG 1.65 applies--use ASME Section III Acceptance Criteria B6.40 RPV, Threads in Flange 1 through 68 UT >B6.50 RPV Closure Washers and Bushings 326-03, Washers 1 through 68 VT-i >Bushings 1 through 68 VT-I >2 dia." 2 dia." 2 dia." 08CP 09CP 08CP 09CP 11CP 1/3 Each Period 11CP 12CP 1/3 Each Period Only required when studs are removed (48-51 removed with refueling shute)B-G-2 B7.10 RPV Bolts, Studs, and Nuts 2" and LessInstrumentation Nozzle VT- I < 2 dia." Spare Flange FBC-01 (180 Deg) VT-1 < 2 dia." Spare Flange FBC-02 (0 Deg) VT-I < 2 dia." B7.50 Piping Bolts, Studs, and Nuts 2" and Less FBC-E41-2297-01 VT-i < 2 dia." FBC-E51-2192-01 VT-1 < 2 dia." B7.60 Pump Bolts, Studs, and Nuts 2" and Less RRC Pump A Seal Bolting VT-1 < 2 dia." RRC Pump B Seal Bolting VT-1 < 2 dia." B7.70 Valve Bolts, Studs, and Nuts 2" and Less B21-FOIOA-VBB VT-i < 2 dia." 5361-5 5361-5 5361-5 2297-5 2192-5 5365-5 5365-5 lic lic lic 09C 08C 10C 12C 3537-5 12C DETROIT EDISON COMPANY -INSERVICE INSPECTION NDE PROGRAM ISI -NDE Program FERMI 2 TABLE A Rev. 6 Change 2 FERMI 2 NUCLEAR POWER PLANT Page 10 Exams Selection Basis Relief Inspection Period Category / Item Identification Required Isometric Request 1 2 3 Remarks B-G-2 B7.70 Valve Bolts, Studs, and Nuts 2" and Less B21-FOIOB-VBB VT-1 < 2 dia." 3536-5 09C B21-FO11A-VBB VT-1 < 2 dia." 3537-5 08C B21-FOIIB-VBB VT-I < 2 dia." 3536-5 09C B21-FO13A-VBB VT-1 < 2 dia." 5355-5 07C B21-F013B-VBB VT-I < 2 dia." 5354-5 08C B21-FO13C-VBB VT-1 < 2 dia." 5353-5 10C B21-FO13D-VBB VT-1 < 2 dia." 5353-5 07C B21-FO13E-VBB VT-1 < 2 dia." 5354-5 10C B21-FO13F-VBB VT-I < 2 dia." 5353-5 10C B21-FO13G-VBB VT-1 < 2 dia." 5353-5 08C B21-FO13H-VBB VT-1 < 2 dia." 5354-5 12C B21-FO13J-VBB VT-I < 2 dia." 5354-5 07C B21-FO13K-VBB VT-I < 2 dia." 5353-5 08C B21-FO13L-VBB VT-1 < 2 dia." 5352-5 08C B21-FO13M-VBB VT-I < 2 dia." 5352-5 07C B21-FO13N-VBB VT-I < 2 dia." 5352-5 11C B21-FO13P-VBB VT-I < 2 dia." 5355-5 12C B21-FO13R-VBB VT-I < 2 dia." 5354-5 12C B21-F022A-VBB VT-I < 2 dia." 5352-5 11C B21-F022B-VBB VT- I < 2 dia." 5353-5 12C B21-F022C-VBB VT- I < 2 dia." 5354-5 10C B21-F022D-VBB VT-1 < 2 dia." 5355-5 12C B21-F028A-VBB VT-1 < 2 dia." 5352-5 10C B21-F028B-VBB VT-1 < 2 dia." 5353-5 08C B21-F028C-VBB VT-1 < 2 dia." 5354-5 11C B21-F028D-VBB VT-1 < 2 dia." 5355-5 08C B21-F032A-VBB VT-1 < 2 dia." 3537-5 09C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 11 Category / Item Identification Exams Required Selection BasisRelief Inspection Period Isometric Request 1 2 3 Remarks B-G-2 B7.70 Valve Bolts, Studs, and Nuts 2" and Less B21-F032B-VBB VT-1 < 2 dia." B21-F076A-VBB VT-1 < 2 dia." B21 -F076B-VBB B31-F023A-VBB B31-F023B-VBB B3 l-F031A-VBB B3 l-F031iB-VBB El1-F008-VBB El l-F009-VBB El1-FO15A-VBB Ell-FO15B-VBB E11-F050A-VBB El1-F050B-VBB E11 -F060A-VBB El1-F060B-VBB El1-F067-VBB E11-F608-VBB E2 1 -F005A-VBB E21-FO05B-VBB E21-F006A-VBB E21 -F006B-VBB E21-F007A-VBB E21-F007B-VBB E41-F002-VBB

E41-F003-VBB E41-F006-VBB VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1 VT-1< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia.< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia."< 2 dia." 3536-5 3537-5 3536-5 5357-5 5359-5 5357-5 5359-5 2299-5 2299-5 2298-5 2327-5 2298-5 2327-5 2298-5 2327-5 2299-5 2299-5 3052-5 3053-5 3052-5 3053-5 3052-5 3053-5 2297-5 2297-5 3537-5 11C 11C/12C lIC/12C liC 11C 12C 09C 09C 09C 07C 07C 07C liC 12C 10C 09C 09C 09C liC 08C 07C 12C 12C 12C liC 08C 10C DETROIT EDISON COMPANY -INSERVICE INSPECTION NDE PROGRAM ISI -NDE Program FERMI 2 TABLE A Rev. 6 Change 2 FERMI 2 NUCLEAR POWER PLANT Page 12 Exams Selection Basis Relief Inspection Period Category / Item Identification Required Isometric Request 1 2 3 Remarks B-G-2 B7.70 Valve Bolts, Studs, and Nuts 2" and Less E51-F007-VBB VT-1 < 2 dia." 2192-5 09C 12C E51-F008-VBB VT-1 < 2 dia." 2192-5 07C 12C E51-F013-VBB VT-1 < 2 dia." 3536-5 liC FBC-B21-5352-O1L VT-1 < 2 dia." 5352-5 08C FBC-B21-5352-01M VT-1 < 2 dia." 5352-5 07C FBC-B21-5352-01N VT-1 < 2 dia." 5352-5 11C FBC-B21-5353-01C VT-1 < 2 dia." 5353-5 10C FBC-B21-5353-01D VT-1 < 2 dia." 5353-5 07C FBC-B21-5353-O1F VT-1 < 2 dia." 5353-5 10C FBC-B21-5353-0IG VT-1 < 2 dia." 5353-5 08C FBC-B21-5353-OIK VT-1 < 2 dia." 5353-5 08C FBC-B21-5354-01B VT-1 < 2 dia." 5354-5 08C FBC-B21-5354-01E VT-1 < 2 dia." 5354-5 10C FBC-B21-5354-01H VT-I < 2 dia." 5354-5 12C FBC-B21-5354-01J VT-1 < 2 dia." 5354-5 07C FBC-B21-5354-OIR VT-1 < 2 dia." 5354-5 12C FBC-B21-5355-OIA VT-1 < 2 dia." 5355-5 07C FBC-B21-5355-01P VT-1 < 2 dia." 5355-5 12C G33-FOOI-VBB VT-1 < 2 dia." 3096-5 08C G33-F004-VBB VT-1 < 2 dia." 3096-5 09C G33-FIOO-VBB VT-1 < 2 dia." 5351-5 10C G33-FIOI-VBB VT-1 < 2 dia." 3096-5 12C G33-FI02-VBB VT-1 < 2 dia." 5351-5 12C G33-F106-VBB VT-1 < 2 dia." 5351-5 11C G33-FI20-VBB VT-1 < 2 dia." 3536-5 08C G33-FI21-VBB VT-I < 2 dia." 3536-5 07C G33-F220-VBB VT-I < 2 dia." 3536-5 10C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 13 Category / Item Identification Exams Selection Basis Required Relief Inspection Period Isometric Request 1 2 3 Remarks B-G-2 B7.80 CRD Bolts, Studs, and Nuts 2" and Less 185 sets of Bolts, Studs and Nuts Visual

< 2 dia." VT-1 08CP 09CP/1OCP When Disassembled (24 sets, 08), (23 sets, 09), (23 sets, 10), (19 sets, 11), (15 sets 12)B-H B8.10 10-324A 3-306/4-309 3-306/4-309 8-319A 8-319B 8-319C 8-319D RPV Integral Attachment Weld MT MT UT MT MT MT MT B-H Weld B-H Weld B-H WeldB-H Weld B-H WeldB-H Weld B-H Weld 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 5360-5 08C 08CP 08CP Code Case N-509, B-K, B 10.10 10% of Weld length 10% of Weld length 12C Supplemental exam for weld 1-391A, RR-A1 12C Supplemental exam for weld 1-391C, RR-A1 Supplemental exam for weld 1-391 E, RR-A1 12C Supplemental exam for weld 1-391G, RR-A1 loC B-J B9.11 Circumferential Piping Weld 4" NPS or Larger 3-316A UT RI (TASCS, CC)3537-5 RR-A30 08C No expanded CC exam volume for piston style safe-ends for FW.3-316D 3-316E 7-316A FW-E 11-2298-6W0 FW-E 11-2299-2WF3 FW-E11-2327-OW1 FW-E11-2327-0W6 FW-E 11-2327-6W0 FW-E21-3052-4WF 1 FW-E41-2297-0W4

FW-E41-2297-2W3 FW-E51-2192-1W2 UT UT UT UT UT UT UT UT UT MT UT UT RI (TASCS, CC)RI (TASCS, CC)RI A, (IGSCC)RI RI RI A (IGSCC)RI RI RI RI 3536-5 3536-5 5352-5 2298-5 2299-5 2327-5 2327-5 2327-5 3052-5 2297-5 2297-5 2192-5 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 12C 12C 08C 08C 08C Note 2, Category B 09C liC 11CL 12C Note 2, Category B 08C 08C 09C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 14 Category / Item Identification Exams Required Selection Basis Relief Inspection PeriodIsometric Request 1 2 3 Remarks B-J B9.11 Circumferential Piping Weld 4" NPS or Larger FW-E51-2192-2W3 UT RI FW-G33-3096-10WF3 UT A, RI (IGSCC)FW-G33-3096-6WF5 UT RI FW-G33-3096-8W11 UT RI FW-G33-3096-8W9 UT RI FW-G33-3096-9WF1 UT RI FW-N21-2336-13W14 UT RI FW-N21-2336-14WF1 UT RI FW-N21-2336-15W0 UT RI (TASCS)FW-N21-2336-16W19 UT RI FW-N21-2336-3W4 UT RI FW-PS-2-A6 UT RI FW-PS-2-C3 UT RI FW-RD-2-A1 1 UT A (IGSCC)FW-RD-2-A16 UT RI, A (IGSCC)FW-RD-2-A17 UT RI, A (IGSCC)FW-RD-2-A18 UT RI, A (IGSCC)2192-5 5351-5 3096-5 5351-5 5351-5 5351-5 3537-5 3537-5 3537-5 3537-5 3536-5 5352-5 5354-5 5356-5 5356-5 5356-5 5356-5 5357-5 5358-5 5357-5 3537-5 3536-5 3536-5 3053-5 3053-5 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 09C 08C lic 10C 10C 10C 10C 10C 08C 09C 10c 09C llC 12C RCIC Selection FW-RD-2-A9 FW-RD-2-B 19 FW-RS-2-A1 N4A UT UT UT UT UT UT UT UT RI, A (IGSCC)A, (IGSCC)A (IGSCC)RI (TASCS, CC)RI (TASCS,CC)

RI (TASCS, CC)RI RI RR-A30 08CA 11CL Note 2, Category B (CRC)Note 2, Category B (CRC)12C Note 2, Category B (CRC)12C Note 2, Category B (CRC) Replacement for original selection SW-RS-2-Al-W1, CARD 07-26347 Note 2, Category B Note 2, Category B (CRC)12C Note 2, Category B No expanded CC exam volume for piston style safe-ends for FW.12C 12C 10C RR-A30 08C N4D N4E SW-E21-3053-3WN SW-E21-3053-3WP RR-A30 RR-A30 RR-A30 RR-A30 09C 09C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 15 Category / Item Identification Exams Selection Basis Required Relief Inspection Period Isometric Request 1 2 3 Remarks B-J B9.11 Circumferential Piping Weld 4" NPS or Larger SW-G33-3096-5WD UT RI SW-G33-3096-5WH UT RI SW-N21-2336-13WC UT RI Sw-N21-2336-13WE UT RI SW-N21-2336-15WP UT RI (TASCS)SW-N21-2336-1WD UT RI SW-N21-2336-1WL UT RI (TASCS)SW-N21-2336-1WU UT RI SW-N21-2336-3WC UT RI SW-PS-2-Al-A UT RI SW-PS-2-A1-B UT RI SW-PS-2-A4-B UT RI SW-PS-2-C3-A UT RI SW-PS-2-C3-C UT RI SW-PS-2-C3-D UT RI SW-PS-2-C3-J UT RI SW-PS-2-C3-K UT RI SW-RD-2-A3-W7 UT A (IGSCC)SW-RD-2-A4-W2 UT RI SW-RD-2-B4-W2 UT RI, A SW-RD-2-B8-Wl UT RI, A SW-RD-2-B8-W2 UT RI, A SW-RS-2-A2-Wl UT A (IGSCC)SW-RS-2-A3-W4 UT RI, A (IGSCC)3096-5 3096-5 3537-5 3537-5 3537-5 3536-5 3536-5 3536-5 3536-5 5352-5 5352-5 5352-5 5354-5 5354-5 5354-5 5354-5 5354-5 5356-5 5356-5 5358-5 5358-5 5358-5 5357-5 5357-5 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 RR-A30 lic lic 08C 10C 10C 09C 09C 09C 09C RCIC Selection RCIC Selection RCIC Selection 08C 08C 12C IOC 1OC 1OC 08C 08C 08C 08C 09C 11CL Note 2, Category B 11C Note 2, Category A 12C Note 2, Category A Note 2, Category A Note 2, Category A Note 2, Category B 11CL Note 2, Category B, Replacement for original selection FW-RD-2-Al-W1, CARD 07-26900 11CL Note 2, Category B, Replacement for original selection FW-RD-2-A1-W1, CARD 07-26900 11C Note 2, Category B SW-RS-2-A3-W5 SW-RS-2-B 1-Wi UT RI, A (IGSCC)5357-5 RR-A30 UT RI, A (IGSCC) 5359-5 RR-A30 DETROIT EDISON COMPANY -FERMI 2 Category / Item Identification B-J INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT Exams Selection Basis Relief Required Isometric Request ISI -NDE Program Rev. 6 Change 2 Page 16Inspection Period 1 2 3 Remarks B9.11 Circumferential Piping Weld 4" NPS or Larger SW-RS-2-B3-W4 UT RI, A (IGSCC)SW-RS-2-B3-W5 UT RI, A (IGSCC)5359-5 5359-5 RR-A30 RR-A30 11CL 11CL Note 2, Category B, Replacement for original selection FW-RD-2-B1-W 1, CARD 07-26900 Note 2, Category B, Replacement for original selection FW-RD-2-B 1-W1, CARD 07-26900 B-K-1 B10.10 Piping Integral Attachment Weld SW-N21-2336-20WB MT SW-N21-2336-20WC MT SW-N21-2336-20WD MT SW-N21-2336-20WE MT SW-PS-2-A2-AA1 MT SW-PS-2-A2-AA2 MT SW-PS-2-A2-AA3 MT SW-PS-2-A2-AA4 MT B10.20 Pump Integral Attachment Weld SW-B31-5365-Pump A-WA PT 10% of lWF Selections 10% of IWF Selections 10% of IWF Selections 10% of IWF Selections 10% of IWF Selections 10% of IWF Selections 10% of IWF Selections 10% of IWF Selections 10% of IWF Selections 3537-5 3537-5 3537-5 3537-5 5352-5 5352-5 5352-5 5352-5 5365-5 1OC IOC 1OC 1OC 07C 07C 07C 07C ISI Eval.99-055; Code Case N-509, B 10.20ISI Eval.99-055; Code Case N-509, B110.20 ISI Eval.99-055; Code Case N-509, B110.20 ISI Eval.99-055; Code Case N-509, B 10.20 ISI Eval.99-055; Code Case N-509, B 10.20 ISI Eval.99-055; Code Case N-509, B 10.20 ISI Eval.99-055; Code Case N-509, B 10.20 ISI Eval.99-055; Code Case N-509, B 10.20 12C ISI Eval.99-055; Code Case N-509, B10.30 Only if Disassembled, Note 10 Only if Disassembled, Note 10 B-L-2 B12.20 RRC Pump A RRC Pump B Pump Casing VT-3 VT-3 Visual VT-3 Visual VT-3 5365-5 5365-5 DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 17 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks B-M-2 B12.50 B21FO10A Valve Body B21FO1OB B21FO11A B21FO11B B21FO13A VT-3 VT-3 VT-3 VT-3 VT-3 B21FO13B B21FO13C B21FO13D B21FO13E B21FO13F B21FO13G B21F013H B21FO13J B21FO13K B21FO13L B21FO13M B21FO13N B21FO13P B21FO13R B21F022A B21F022B B21F022C VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3>4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS" 3537-5 3536-5 3537-5 3536-5 5355-5 IOC 5354-5 5353-5 5353-5 5354-5 5353-5 5353-5 5354-5 5354-5 5353-5 5352-5 5352-5 5352-5 5355-5 5354-5 5352-5 5353-5 5354-5 1OC 08C08C 09C 11C/12C 07C 09C/ 12C 1OC Only if Disassembled Only if Disassembled 08C loC 09C 09C Only if Disassembled Only if DisassembledSRV's (B21FO13A-R) are inspected, rebuilt, and functionally tested on a rotating basis.

A portion of pilots and bodies are rotated each outage.Details of VT-3 inspections completed are contained in the Purchase Order records for each outage.Only if Disassembled Only if Disassembled 11C Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled 11C Only if Disassembled Only if Disassembled Only if Disassembled 11C Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled 13C Only if Disassembled Only if Disassembled 08C 09C 08C 09C 09C DETROIT EDISON COMPANY -FERMI 2INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 18 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks B-M-2 B12.50 B21F022D B21F028A B21F028B B21F028C B21F028D B21F032A B21F032B B21F076A B21F076B B31F023A B31F023B B31FO31A B31FO31B ElIF008 ElIF009 ElIF015A ElIF015B ElIF050A ElIF050B EllF060A ElIF060B El1F067 E11F608 E21FO05A E21FO05B E21F006AValve Body VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3>4 NPS">4 NPS';>4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS"

>4 NPS">4 NPS">4 NPS"

>4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS" 5355-5 5352-5 5353-5 5354-5 5355-5 3537-5 3536-5 3537-5 3536-5 5357-5 5359-5 5357-5 5359-5 2299-5 2299-5 2298-5 2327-5 2298-5 2327-5 2298-5 2327-5 2299-5 2299-5 3052-5 3053-5 3052-5 07C 07C 07C 07C 07C 07C 07C 09C 07C 07C 09C 07C 09C 08C Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled llC/ Only if Disassembled 12C 12C Only if Disassembled Only if Disassembled Only if Disassembled 11C Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 19 Category / Item Identification Exams RequiredSelection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks B-M-2 B12.50 E21FO06B E21FO07A E21FO07B E41F002 E41F003 E41F006 E51FO13 G33F001 G33F004 G33F100 G33F102 G33F106 Valve Body VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3>4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS">4 NPS" 3053-5 3052-5 3053-5 2297-5 2297-5 5352-5 3536-5 3096-5 3096-5 5351-5 5351-5 5351-5 07C 09C 12C Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled 10C Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled Only if Disassembled B-N-1 B13.10 Reactor Vessel Interior -Vessel Internals are examined using remote visual techniques.

Exams listed are code required exams.techniques are utilized as per BWRVIP I&E Guidelines (Note 22).Access Hole Cover VT-i Vessel Interior, A 09C 12C Note No. 13 CDP and SLC Line VT-3 Vessel Interior Only if Accessible Control Rod Drive Housings VT-3 Vessel Interior Only if AccessibleCore Shroud VT-i Vessel Interior, A 07CP/ Note No. 19 08CP More detailed Core ShroudCore Shroud Welds Core Spray Sparger and Interior Piping VT-3 UT VT-3 /VT-i VT-3 Vessel InteriorVessel Interior, A Vessel Interior, A Vessel Interior 07CP/08CP Note No. 19 12C Note No. 19 07C/0 09CP/ 1lCP NoteNo. 12 8CP 1OCP /12C P07CP/ 09CP/

12C NUREG 0619 at least once every 4 Cycles 08CP 1OCP Feedwater Sparger DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 20 Category / Item Identification Exams Selection Basis Required Relief Isometric Request Inspection Period 1 2 3 Remarks B-N-1 B13.10 Reactor Vessel Interior -Vessel Internals are examined using remote visual techniques.

Exams listed are code required exams. More detailed techniques are utilized as per BWRVIP I&E Guidelines (Note 22).Flux Monitor Housings VT-3 Vessel Interior Only if AccessibleGuide Rod Holders

/ Brackets Instrumentation Lines VT-3 VT-3 Vessel Interior Vessel Interior, A Jet Pump Components VT-3 / UT Vessel Interior, A 07CP/ 1OCP 12CP 08CP 07CP/ 09CP/I lCP Note No. 7 08CP 1OCP /12C P 07CP/ 09CP/ 1lCP Note No. 17 08CP 1OCP /12C P 09C 12C Note No. 3 07CP/ 09CP/08CP 1OCP Jet Pump Hold Down Beams Jet Pump Hold Down Beams Recirculation Inlet Nozzle Sample Holders Shroud Head *Shroud Head Bolts UT VT-3 VT-3 VT-3 VT-3 VT-3 UT VT-3 VT-3 VT-3Vessel Interior, A Vessel Interior Vessel Interior Vessel Interior Vessel Interior Vessel Interior Vessel Interior, AVessel Interior Vessel Interior Vessel Interior 08CP 09CP/1 OCP 08CP 1OCP 12CP 07CP/ 09CP/ IlCP 08CP 1OCP /12C P 07CP/ 09CP/ 1lCP 08CP 1OCP /12C P 12CP Shroud Head Bolts Steam Dryer Assembly

/ Hold Downs Steam Separator Assy.Note No. 9 12CP Note No. 11 07CP/ 09CP/08CP 1OCP 07CP/ 09CP/ llCP 08CP 1OCP /12C P Top Guide 07CP/ 09CP/08CP 1OCP 1lCP Note No. 16/12C P DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 21 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks B-N-2 B13.20 RPV Interior Welded Attachments Within Beltline Region -Vessel Internals are examined using remote visual techniques.

Exams listed are code required exams. More detailed techniques are utilized as per BWRVIP I&E Guidelines (Note 22).Jet Pump Riser Brace Arms VT-1 Vessel Interior, A 07CP/ 09CP/

11 CP 08CP 10CP /12C PSurveillance Specimen Bracket VT-I Attachment Weld 07CP/ 10CP 12CP 08CP B13.30 RPV Interior Welded Attachments Beyond Beltline Region -Vessel Internals are examined using remote visual techniques. Exams listed are code required exams. More detailed techniques are utilized as per BWRVIP I&E Guidelines (Note 22).Core Spray Piping Brackets VT-3 Interior Attachment 07CP/ 09C/Beyond Beltline 08CP 10CPFeedwater Sparger Brackets Shroud Support WeldsSteam Dryer Support Lugs VT-3 Interior Attachment Beyond Beltline EVT- 1 / Interior Attachment UT Beyond Beltline 07CP/ 09CP/ 12C 08CP 10CP 09CP/ IlCP Note No. 191OCP /12C P 07CP/ 10C 12C 08CP VT-3 Interior AttachmentBeyond Beltline B13.40 Welded Core Support Structure

-Vessel Internals are examined using remote visual techniques.

Exams listed are code required exams. Moredetailed techniques are utilized as per BWRVIP I&E Guidelines (Note 22).Core Support Assy. & Bolts VT-3 A 07CP/ BWRVIP-25 Lower Core Shroud Peripheral Fuel Support VT-3 VT-3 Core Support, A A 08CP 07CP 09CP 07CP/ 09CP 08CP 12CP NoteNo. 19 B-O B14.10 Welds in CRD Housing CRDH-X02-Y27-W1 PT 10% Peripheral Housing Welds 10% Peripheral Housing Welds 5363-5 5363-5 08C 08C CRDH-X02-Y27-W2 PT DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 22 Category / Item Identification Exams Required Selection Basis Relief Inspection PeriodIsometric Request 1 2 3 Remarks B-0 B14.10 Welds CRDH-X02-Y3 1-WI CRDH-X02-Y3 1-W2 CRDH-X02-Y35-WI CRDH-X02-Y35-W2 CRDH-X02-Y39-Wl CRDH-X02-Y39-W2 n CRD Housing PT PT PT PT PT PT 10% Peripheral Housing Welds 10% Peripheral Housing Welds 10% Peripheral Housing Welds 10% Peripheral Housing Welds 10% Peripheral Housing Welds 10% Peripheral Housing Welds 5363-5 5363-5 5363-5 5363-5 5363-5 5363-5 10C 10C llC lic 12C 12C B-P B15.X Class 1 Pressure Retaining Boundary (Note 15)B 11, B21, B31, C41, E 11, E21, VT-2 Classl Pressure E41, E51, G33, N21, P34 Retaining Boundary07C/ 09C/

lIC/08C 10C 13C 12C X Includes items -B15.10, B15.50, B15.60 and B 15.70. Each Refueling Outage; Note 15 X Includes items -B15.11, B15.51, B15.61 and B15.71. Each Interval, Code Case N-498-1 Bll, B21, B31, C41, Ell, E21, E41, E51, G33, N21, P34 VT-2 Classl Pressure Retaining Boundary C-A C1.10 Shell Circumferential Weld SW-E I1-D2-HX-1 1 UT C1.20 Head Circumferential Weld SW-E 11-D2-HX-05 UT C-B C2.21 Nozzle to Shell (or Head) Weld SW-E 11-D2-HX-01 MT Gross Structural Discontinuity Gross Structural Discontinuity 5370-5 5370-5 08C 12C llC/12C Shell -T >.5" 5370-5 08C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 23 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks C-B C2.21 Nozzle to Shell (or Head) WeldSW-El l-D2-HX-01 UT SW-El l-D2-HX-10 UT SW-El l-D2-HX-10 MT C2.22 Nozzle Inside Radius Section SW-E 11-D2-HX-01 IRS UT SW-El1-D2-HX-10 IRS UT Shell -T >.5" Shell -T >.5" Shell -T >.5" Selected Nozzle Selected Nozzle 5370-5 5370-5 5370-5 08C lIlC lIC 08C lic C-C C3.10 Intregally Welded Attachment (Vessel)SW-El l-D2-HXS-05 MT 10%SW-E l I-D2-HXS-06 MT 10%SW-E 11-D2-HXS-07 MT 10%SW-E 11-D2-HXS-09 MT 10%SW-El1-D2-HXS-10 MT 10%SW-El1-D2-HXS-11 MT 10%SW-E 11-D2-HXS-12 MT 10%SW-Ell-D2-HXS-13 MT 10%SW-Ell-D2-HXS-14 MT 10%SW-Ell-D2-HXS-15 MT 10%SW-Ell-D2-HXS-16 MT 10%SW-El1-D2-HXS-17 MT 10%SW-E 11-D2-HXS-18 MT 10%SW-Ell-D2-HXS-19 MT 10%SW-E 11-D2-HXS-20 MT 10%SW-E 11-D2-HXS-21 MT 10%SW-E 11-D2-HXS-22 MT 10%SW-Ell-D2-HXS-23 MT 10%SW-E 11-D2-HXS-24 MT 10%5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 5370-5 08C 08C 08C 08C 08C 08C 08C 09C 09C 09C 09C Code Case N-509 Code Case N-509 Code Case N-509Code Case N-509Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 llC llC llC llC liC liC liC liC DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 24 Category / Item Identification Exams RequiredSelection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks c-c C3.20 Intregally Welded Attachment (Piping)C11-50-2113-G262A MT 10%C11-50-2113-G262B MT 10%C11-50-2113-G262C MT 10%C11-50-2113-G262D MT 10%C1 1-50-2113-G262E MT 10%C11-50-2113-G262F MT 10%C11-50-2113-G262G MT 10%CI1-50-2113-G262H MT 10%FW-X-223A-W 11 MT 10%FW-X-223A-W 12 MT 10%PSFW-E21-3147-301 MT 10%PSFW-E41-3167-IWE MT 10%PSFW-E41-3167-IWF MT 10%PSFW-E41-3167-IWG MT 10%PSFW-E41-3167-IWH MT 10%SW-E 11-3151-4WE MT 10%SW-E 11-3151-4WF MT 10%SW-E 11-3151-4WG MT 10%SW-E 11-3151-4WH MT 10%SW-E 11-3151-4WJ MT 10%SW-E 11-3151-4WK MT 10%5375-5 5375-5 5375-5 5375-5 5375-5 5375-5 5375-5 5375-5 3153-5 3153-5 3147-5 3167-5 3167-5 3167-5 3167-5 3151-5 3151-5 3151-5 3151-5 3151-5 3151-5 2979-5 2979-5 2979-5 2979-5 07C 1OC IOC 1OC 1OC 1IC Code Case N-509 1IC Code Case N-509 1IC Code Case N-509 11C Code Case N-509 1IC Code Case N-509 1IC Code Case N-509 1IC Code Case N-509 1IC Code Case N-509 13C Code Case N-509 13C Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 12C Code Case N-509 12C Code Case N-509 12C Code Case N-509 12C Code Case N-509 12C Code Case N-509 12C Code Case N-509 EF2-53.873 12C EF2-53.873

EF2-53.873 EF2-53.873 C-F-1 Augmented NRC Commitment FW-C41-2979-1 1S12 FW-C41-2979-17S 18 FW-C41-2979-1 S2 FW-C41-2979-2S3 PT PT PT PT A A A A 10C 08C 08C DETROIT EDISON COMPANY -FERMI 2INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 25 Category / Item Identification Exams RequiredSelection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks C-F-i Augmented NRC Commitment FW-C41-2979-50S51 FW-C41-2979-63S64 FW-C41-2979-64S65 FW-C41-2979-72S73 FW-C41-2979-81 S82 FW-C41-2979-L FW-C41-2979-P FW-C41-3361-02W1 FW-C41-3361-1WF22 FW-C41-3361-1WF25

FW-C41-5058-54S55 FW-C41-5058-65S66 C-F-2 C5.51 Circumferential Weld FW-C 11-2113-249-B FW-C 11-2113-249-B FW-E1 1-3146-5WO FW-E1 1-3146-5WO FW-E11-3146-6W10 FW-E11-3146-6W10 FW-E11-3146-OWl FW-E11-3146-OW1 FW-E11-3151-1OWO FW-E11-3151-1OWO FW-E 11-3151-3WF2 FW-E 11-3151-3WF2 FW-E11-3151-7W11 PT PT PT PT PT PT PT PT PT PT PT PT A A A A A A A A A A A A 2979-5 2979-5 2979-5 2979-5 2979-5 2979-5 2979-5 3361-5 3361-5 3361-5 5374-5 5374-5 09C 09C 08C 10C 11C EF2-53.873 EF2-53.873 EF2-53.873 EF2-53.873 12C EF2-53.873 EF2-53.873 13C EF2-53.873 13C EF2-53.873 12C EF2-53.873 liC EF2-53.873 EF2-53.873 liC EF2-53.873 07C 07C 09C MT UT UT MT UT MT MT UT UT MT MT UT MT R R MS MS MS MS TE TE TE TE MS MS MS 5372-5 5372-5 3146-5 3146-5 3146-5 3146-5 3146-5 3146-5 3151-5 3151-5 3151-5 3151-5 3151-5 12C 12C 08C 08C 07C 07C liC liC llC liC 09C 09C 10C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 26 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks C-F-2 C5.51 Circumferential Weld FW-E11-3151-7W11 FW-E1 1-3154-13WO FW-E1 1-3154-13WO FW-E1 1-3154-4WO FW-E11-3154-4WO FW-E1 1-3157-OW6 FW-E1 1-3157-OW6 FW-E11-3158-1OWF4 FW-E11-3158-1OWF4 FW-E11-3158-1W2

FW-E11-3158-1W2 FW-E1 1-3158-9WF2 FW-E1 1-3158-9WF2 FW-E 11-3159-OWl FW-E 11-3159-OWl FW-E11-3160-OW2 FW-E 11-3161-4WF5 FW-E1 1-3164-4W5 FW-E 11-3164-4W5 FW-E11-4611-1W2 FW-E11-4611-1WF2 FW-E1 1-4612-3WF4 FW-E11-4612-4W5 FW-E11-4612-4WF1 FW-E1 1-4612-7W8 FW-E1 1-4612-8WF3 FW-E11-4612-9WO UT UT MT UT MT UT MT MT UT UT MT MT UT UT MT VT-1 VT-1 MT UT VT-1 VT-1 VT-1 VT-1 VT-1 VT-I VT-1 VT-1 MS TE TE TE TE TE TE TE TE R R R R HS HS R R R R R R R R R R R R 3151-5 3154-5 3154-5 3154-5 3154-5 3157-5 3157-5 3158-5 3158-5 3158-5 3158-5 3158-5 3158-5 3159-5 3159-5 3160-5 3161-5 3164-5 3164-5 4611-5 4611-5 4612-5 4612-5 4612-5 4612-5 4612-5 4612-5 boc 09C 09C 12C 12C 07C 07C 07C 07C 09C 09C 09C 09C 08C 08C RR-A26 RR-A26 RR-A26 RR-A26 RR-A26 RR-A26 RR-A26 RR-A26 RR-A26 RR-A26 11C 12C 12C 12C Note 21 Note 21 1OC 1OC 1OC 12C Note 21 12C Note 21 12C Note 21 Note 21 12C Note 21 Note 21 Note 21 l1C Note 21 DETROIT EDISON COMPANY -INSERVICE INSPECTION NDE PROGRAM ISI -NDE Program FERMI 2 TABLE A Rev. 6 Change 2 FERMI 2 NUCLEAR POWER PLANT Page 27 Exams Selection Basis Relief Inspection Period Category / Item Identification Required Isometric Request 1 2 3 Remarks C-F-2 C5.51 Circumferential Weld FW-E21-3144-0W4 MT TE -3144-5 10C FW-E21-3144-0W4 UT TE 3144-5 10C FW-E21-3144-OW1 MT TE 3144-5 07C FW-E21-3145-11WO MT R 3145-5 10C FW-E21-3147-16W17 MT R 3147-5 07C FW-E21-3147-16W17 UT R 3147-5 07C FW-E21-3148-0W8 MT TE 3148-5 12C FW-E21-3148-0W8 UT TE 3148-5 12C FW-E21-3148-7W0 UT TE 3148-5 09C FW-E21-3148-7W0 MT TE 3148-5 09C FW-E41-3162-11WF1 VT-i R 3162-5 RR-A26 09C Note 21 FW-E41-3162-11WF4 VT-1 R 3162-5 RR-A26 09C Note 21 FW-E41-3162-11WF5 VT-i R 3162-5 RR-A26 09C Note 21 FW-E41-3162-11WO VT-1 R 3162-5 RR-A26 08C Note 21 FW-E41-3162-1W2 UT R 3162-5 10C FW-E41-3162-1W2 MT R 3162-5 10C FW-E41-3162-9WFO MT TE 3162-5 12C FW-E41-3162-9WFO UT TE 3162-5 12C FW-E41-3163-7W0 MT TE 3163-5 07C FW-E41-3163-7W0 UT TE 3163-5 07C FW-E41-3163-8W0 UT TE 3163-5 11C FW-E41-3163-8W0 MT TE 3163-5 1iC FW-E41-3167-1W2 MT R 3167-5 12C FW-E41-3167-1W2 UT R 3167-5 12C FW-E41-3167-9WO UT TE 3167-5 11C FW-E41-3167-9WO MT TE 3167-5 biC FW-E41-3167-OW1 UT TE 3167-5 09C DETROIT EDISON COMPANY -FERMI 2INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE ProgramRev. 6 Change 2 Page 28 Category / Item Identification Exams RequiredSelection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks C-F-2 C5.51 Circumferential Weld FW-E41-3167-OWl FW-E41-3169-2W0

FW-E41-3169-2W0 FW-E41-3172-OW1

FW-E41-3172-OWl FW-E41-3172-0W8 FW-E41-3172-0W8 FW-G41-3669-0W9

FW-N30-3259-4WO FW-N30-3259-4WO FW-T48-04-2095-11W12 FW-T48-04-2095-19WO FW-T48-04-2095-7W8 FW-T48-04-2097-2OW21 FW-T48-04-2097-8W9 SW-C11-2113-172-A SW-CI1-2113-172-A SW-C11-2113-303-A

SW-Cl1-2113=303-ASW-El l-3035-5WE

SW-El l-3035-7WB SW-El 1-3146-6WE SW-El 1-3146-6WE SW-El 1-3146-6WH SW-El 1-3146-6WH SW-El 1-3153-13WD SW-El 1-3153-13WD MT MT UT UT MT MT UT MT MT UT MT MT MT MT MT UT MT UT MT MT MT UT MT MT UT MT UT TE R R TE TE R R MS TE TE R MS MS R R R R R R R HS HS HS HS R R 3167-5 3167-5 3169-5 3172-5 3172-5 3172-5 3172-5 3669-5 3259-5 3259-5 2095-5 2095-5 2095-5 2097-5 2097-5 5375-5 5375-5 5372-5 5372-5 3035-5 3035-5 3146-5 3146-5 3146-5 3146-5 3153-5 3153-5 09C 09C 09C 1oc 1oc 12C 12C 12C 08C 08C 07C RR-A26 08C RR-A26 07C 07C 1oc Note 21 Note 21 09C 09C lic lic 07C 09C 1oc 1oc 07C 07C 08C 08C DETROIT EDISON COMPANY -FERMI 2INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 29 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks C-F-2 C5.51 Circumferential Weld SW-El 1-3154-4WC SW-E 11-3154-4WC SW-El1-3157-IWB SW-El1-3157-IWB SW-El1-3158-4WD SW-El 1-3158-4WD SW-El 1-3158-8WG SW-El 1-3158-8WG SW-Ell-3161-IWH SW-E 11-3161-4WB SW-El 1-3161-4WK SW-El -3177-6WD SW-El 1-3177-6WD SW-El 1-3177-9WE SW-El 1-3177-9WE SW-E21-3145-9WD SW-E21-3147-15WF SW-E21-3147-15WF

SW-E21-3147-15WG SW-E21-3147-15WG SW-E21-3147-19WB SW-E21-3147-19WB SW-E21-3147-5WJ SW-E21-3147-5WJ SW-E21-3148-5WD SW-E21-3149-4wD SW-E21-3149-4WD UT MT UT MT UT MT MT UT MT VT-1 VT-1 MT UT UT MT VT-1 MT UT MT UT MT UT MT UT MT MT UT 3154-5 3154-5 3157-5 3157-5 3158-5 3158-5 3158-5 3158-5 3161-5 3161-5 3161-5 3177-5 3177-5 3177-5 3177-5 3145-5 3147-5 3147-5 3147-5 3147-5 3147-5 3147-5 3147-5 3147-5 3148-5 3149-5 3149-5 09C 09C 12C 12C 11C liC 11C liC 12C 12C liC liC RR-A26 RR-A26 RR-A26 08C IOC Note 21 Note 21 09C 09C Note 21 liC liC 10C 10C 08C 08C 08C 08C 08C 07C 07C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE ProgramRev. 6 Change 2 Page 30 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks C-F-2 C5.51 Circumferential Weld SW-E21-3149-6WC SW-E21-3149-6WC SW-E21-3149-6WL

SW-E21-3149-6WL SW-E41-3162-11WC SW-E41-3162-2WC SW-E41-3162-2WC SW-E41-5373-GW3 SW-E41-5373-GW3 SW-G41-3669-3WB SW-N30-3258-13WJ

SW-N30-3258-13WJ SW-N30-3258-19WJ SW-N30-3258-19WJ

SW-N30-3258-1WJ SW-N30-3258-1WJ SW-N30-3258-7WK SW-N30-3258-7WK SW-T48-04-2095-5WD SW-T48-04-2095-WSW3 SW-T48-04-2097-18WC

SW-T48-04-2097-20WD SW-T48-04-2097-21WB SW-T48-04-2097-25WF C5.52 Longituinal Weld SW-E41-3162-1 iWOLD SW-N30-3258-13WJLU MT UT UT MT VT-1 UT MT UT MT MT UT MT UT MT UT MT UT MT MT MT MT MT VT-1 VT-1 VT-1 MT R R R R R R R R R R MS MS MS MS MS MS MS MS R R

R MS R R 3149-5 3149-5 3149-5 3149-5 3162-5 3162-5 3162-5 5373-5 5373-5 3669-5 3258-5 3258-5 3258-5 3258-5 3258-5 3258-5 3258-5 3258-5 2095-5 2095-5 2097-5 3258-5 2097-5 2097-5 3162-5 3258-5 12C 12C lic llC RR-A26 08C 10C 10C 09C 09C 10C Note 21 CARD 04-25787 Replaced SW-E41-3162-1WU 12C 12C 07C 07C 10C 10C 09C 09C lic lic 10C RR-A26 RR-A26 RR-A26 07C 07C 11C Note2l Note 21 Note 21 R RR-A26 08C Note 21 12C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 31 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks C-F-2 C5.52 Longituinal Weld SW-N30-3258-13WJLU U]SW-N30-3258-19WJLU U]SW-N30-3258-19WJLU M SW-N30-3258-1WJLU M SW-N30-3258-7WKLU U1 SW-N30-3258-7WKLU M C5.81 Branch Connection Weld FW-El1-3146-15FWOI M FW-El1-3157-4WFO Ml SW-El 1-3146-5WC M SW-E11-3146-5WM M SW-E 11-3146-7WC M SW-E 11-3151-8WD M SW-E 11-3160-1WD M SW-E21-3144-5WE M SW-N30-3258-13WB M F F r T T F T T T T T T MS R MS HS HS HS HS R R 3258-5 3258-5 3258-5 3258-5 3258-5 3258-5 3146-5 3157-5 3146-5 3146-5 3146-5 3151-5 3160-5 3144-5 3258-5 07C 07C 10C 09C 09C 12C 12C 12C 07C 10C 12C 08C 09C llC 08C C-H C7.X Class 2 Pressure Retaining Boundary (Note 15)B21 Main Steam VT-2 Class 2 Boundary B21 Main Steam C 1I Control Rod Drive System C 11 Control Rod Drive System VT-2 VT-2 VT-2 Class 2 Boundary Class 2 Boundary Class 2 Boundary Class 2 Boundary 5808-1 5808-2 5808-1 5808-2 5810-1 5810-1C C C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 C X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1C C C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 C41 Standby liquid Control System VT-2 5811 DETROIT EDISON COMPANY -FERMI 2 Category / Item Identification C-HINSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT Exams Selection Basis Relief Required Isometric Request ISI -NDE Program Rev. 6 Change 2 Page 32Inspection Period 1 2 3 Remarks C7.X Class 2 Pressure Retaining Boundary (Note 15)C41 Standby liquid Control System VT-2 Class 2 Boundary ElI Residual Heat Removal System VT-2 Class 2 Boundary E II Residual Heat Removal System E21 Core Spray System E21 Core Spray System E41 High Pressure Coolant Injection E41 High Pressure Coolant Injection G41 Fuel Pool Cooling & Cleanup System G41 Fuel Pool Cooling & Cleanup System G51 Torus Water Management System G51 Torus Water Management System N30 Main & Reheat Steam System N30 Main & Reheat Steam System P34 Post Accident Sampling VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 Class 2 Boundary Class 2 Boundary Class 2 Boundary Class 2 Boundary Class 2 Boundary Class 2 Boundary Class 2 Boundary Class 2 Boundary Class 2 Boundary Class 2 Boundary Class 2 Boundary Class 2 Boundary, Code Case N-522 5811 5813-1 5813-2 5813-3 5813-1 5813-2 5813-3 5814 5814 5815 5815 5819 5819 5820 5820 5822 5822 5824 C C C C RR-A19 RR-A19 C C C C C C C C C C C C C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period CP X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 C X includes items C7.20, C7.40, C7.60 andC7.80. Perform each Interval; Code Case N498-1 C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 C X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 33 Category / Item Identification Exams Required Selection Basis Relief Inspection Period Isometric Request 1 2 3 Remarks C-H C7.X Class 2 Pressure Retaining Boundary (Note 15)P34 Post Accident Sampling VT-2 Class 2 Boundary T48-04 Containment Atmosphere, Control System T48-04 Containment Atmosphere, Control System T50 Primary Containment Monitoring System T50 Primary Containment Monitoring System VT-2 VT-2 VT-2 VT-2 D-B D2.10 Pressure Retaining Components E 11 Residual Heat RemovalSystem Visual, Functional Boundary VT-2 P44 Emergency Equipment Visual, Cooling Water VT-2 P45 Emergency Equipment Service Visual, Water VT-2R30 Emergency Diesel Generator Visual,& Service Water VT-2 D2.20 Intregal Attachment (Supports and E11-2179-G20 VT-I E11-2184-G12 VT-i E11-3184-G08 VT-I E11-3185-G40 VT- I P44-3084-GIO VT- I P44-3336-GOI VT-I P44-3337-G13 VT-1 P44-3347-G14 VT-I Class 2 Boundary, Code Case N-522 Class 2 Boundary Class 2 Boundary, Code Case N-522 Class 2 Boundary System Function System Function System Function System Function Restraints) 10% Selection 10% Selection 10% Selection 10% Selection 10% Selection 10% Selection 10% Selection 10% Selection 5824 5830-1 5830-2 5830-1 5830-2 5831 5831 C X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 C C C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C X includes items C7.20, C7.40, C7.60 andC7.80. Perform each Interval; Code Case N498-1 C C C X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 Class 3 Systems Class 3 Systems Class 3 Systems Class 3 Systems 2179-2 2184-2 3184-2 3185-2 3084-2 3336-2 3337-2 3347-2 C C C Note 15 Perform Each Period; Code Case 498-1 C C C Note 15 Perform Each Period; Code Case 498-1C C C Note 15 Perform Each Period; Code Case 498-1 C C C Note 15 Perform Each Period; Code Case 498-1 07C 10C 09C 09C 09C Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 Code Case N-509 12C Code Case N-509 12C Code Case N-509 07C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE A FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 34 Category / Item Identification Exams Selection Basis Required Relief Inspection Period Isometric Request 1 2 3 Remarks D-B D2.20 Intregal Attachment (Supports and Restraints)

P44-3348-G12 VT-1 10% Selection P44-3559-G12 VT-1 10% Selection P45-2178-G09 VT-1 10% Selection P45-2204-G I1 VT-1 10% Selection P45-3352-G06 VT-1 10% Selection P45-3353-GO5 VT-1 10% Selection P45-4626-G08 VT- 1 10% Selection P45-4627-G06 VT-1 10% Selection R30-2176-G28 VT-1 10% Selection D2.40 Intregal Attachment P44-3048-GIO VT-1 10% Selection 3348-2 3559-2 MN-2178 2204-2 3352-2 3353-2 -4626-2 4627-2 MN-2176 07C 10C 09C 07C 10C 16CCode Case N-509Code Case N-509 Code Case N-509 11C Code Case N-509Code Case N-509Code Case N-509 12C Code Case N-509 12C Code Case N-509 Code Case N-509Code Case N-509 3048-2 07C N/A N/A ANSI B31.1 Augmented FW-N20-3105-22WO UT FW-N20-3105-0W13 UT FW-N20-3105-OW 15 UT FW-N20-3105-0W23 UT FW-N20-3105-14WO UT FW-N20-3105-16W0 UT FW-N20-3105-24W0 UT FW-N20-3105-OW21 UT FW-N20-3107-OWl UT FW-N20-3107-OW 17 UT FW-N21-3109-18W0 UT FW-N21-3109-29WO UT SW-N20-03-B009-BWSE UT SW-N20-03-B010-B WSE UT NUREG 0313 NUREG 0313 NUREG 0313 NUREG 0313 NUREG 0313 NUREG 0313 NUREG 0313 NUREG 0313 NUREG 0313 NUREG 0313 NUREG 0313 NUREG 0313 NUJREG 0313 NUREG 0313 3105-1 3105-1 3105-1 3105-1 3105-1 3105-1 3105-1 3105-1 3107-1 3107-1 3109-1 3109-1 3105-1 3105-1 09C 08C 09C 07C 10C 10C Note 2, Category D Note 2, Category D 12C Note 2, Category D Note 2, Category D 12C Note 2, Category D Note 2, Category D Note 2, Category D 11C Note 2, Category D Note 2, Category D Note 2, Category D Note 2, Category D 11C Note 2, Category D 11C Note 2, Category D Note 2, Category D 07C 08C 08C ISI -NDE Program Rev. 6 Change 2 Page 1 INSERVICE INSPECTION NDE PROGRAM TABLE B DETROIT EDISON COMPANY -FERMI 2INSERVICE INSPECTION NDE PROGRAMTABLE B FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 2 Code Class 1 1 1 1 1 1 1 1 1-1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 Identification Number Exams Method Component Support Type Relief Request RI 1-5360-Skirt VT-3 A Inspection Pe 1 2 08C 08C R aod 3 Remarks Bi1-5360-STAB-A Bl1-5360-STAB-B Bl1-5360-STAB-C B 11-5360-STAB-D B 11-5360-STAB-E B 11-5360-STAB-F B 11-5360-STAB-G B 11-5360-STAB-H B21-2192-G02 B21-2192-G13 B21-2297-G14 B21-5352-HAI B21-5353-HB2 B21-5354-AC1 B21-5354-HC3 B21-5355-GD1 B31-5356-HA4 B31-5357-HAl

B31-5357-HA7 B31-5357-RR17A B31-5358-HB3 B31-5359-HB6 B31-5359-HB7 Drywell Pen X- 10 Anchor Structure Drywell Pen X- 11 Anchor Structure Drywell Pen X-12 Anchor Structure Drywell Pen X-13B Anchor Structure VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 G G G G G G G G SP G G SP SP A SP G SP SP C R SP C C A A A A 10c 07C 08C 08C 07C F1.40 (100% RPV Supports) RPV Skirt

&Bolting 11C F1.40 (100% RPV Supports) RPV Stabilizer F1.40 (100% RPV Supports) RPV Stabilizer 11C F1.40 (100% RPV Supports) RPV Stabilizer 11C F1.40 (100% RPV Supports) RPV Stabilizer 11C F1.40 (100% RPV Supports) RPV Stabilizer 12C F1.40 (100% RPV Supports)

RPV Stabilizer 11C F1.40'(100% RPV Supports)

RPV Stabilizer 11C F 1.40 (100% RPV Supports)

RPV Stabilizer 12C F1.10 12C FI.10 Fl.10 Fl.10 FI.10 1lC FI.10 F1.10 F1.10 12C FI.10 F1.10 F1.40 13C F1.40 Fl.10 F1.40 F1.40 13C F1.40 (RCIC, Ref. M-2192-5)13C F1.40 (HPCI, Ref. M-2297-5)13C F1.40 (RHR, Ref. M-2299-5)13C F1.40 (RHR Return, Ref. M-2298-5)10c 08C 07C loC 09C DETROIT EDISON COMPANY -FERMI 2'INSERVICE INSPECTION NDE PROGRAM TABLE B ISI -NDE Program Rev. 6 Change 2 Page 3 FERMI 2 NUCLEAR POWER PLANT Code Class Identification Number Drywell Pen X-16A Anchor Structure Drywell Pen X-43 Anchor StructureDrywell Pen X-7A Anchor StructureDrywell Pen X-9B Anchor Structure El1-2298-GO1 E11-2299-G03 E11-2327-G03 E21-3052-G02 E21-3053-GOI E21-3053-G03

E41-2297-G05 E51-2192-G1 1 G33-3096-GOI G33-3096-G04 G33-3096-G09 G33-3096-G1O G33-3096-G32 N21-3536-G02 N21-3536-G03 N21-3536-G07

N21-3537-G04 N21-3537-G06 B21-2586-G02 B21-2587-G06 B21-2590-G12 B21-2592-G04 B21-2594-G06 B21-4095-G06 C11-2113-G262 Exams Method VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Component Support Type A A A A SP SP R SP SP R SP SP SP SP R SP G SP SP SP SP SP R SP SP R SP R G Relief RequestInspection Pe 1 2 09C 09C 09C R aod 3 Remarks 07C 07C 1OC IOC 09C 1OC IOC lOC 09C 13C F1.40 (CS, Ref. M-3053-5)13C F1.40 (RWCU, Ref. M-3096-5)13C F1.40 (MS, Ref. M-5352-5)13C F1.40 (FW, Ref. M-3536-5)llC FI.10 llC F1.10 FI.10 Fl.10 Fl.10 12C FI.10 12C FI.10 FI.10 F1.10 F1.10 Fl.10 llC F1.10 llC F1.10 Fl.10 12C F1.10 llC F1.10 F1.10 Fl.10 12C Augmented exam -See ISI 99-056 1lC Augmented exam -See ISI 99-056 Augmented exam -See ISI 99-056 Augmented exam -See ISI 99-056 Augmented exam -See ISI 99-056 Augmented exam -See ISI 99-056 11C F1.20 07C 07C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE B FERMI 2 NUCLEAR POWER PLANT ISI -NDE ProgramRev. 6 Change 2 Page 4 Code Class Identification Number C11-2113-G266 C 11-2113-G274 C 11-2113-G294 C4103COO1A Pump Base Anchor El 102002B Pump Base Anchor El 1-3035-G02 E 11-3035-G05 E11-3035-G19 E11-3035-G24 El 1-3146-G30 E11-3146-G32E 11-3146-G36 E11-3151-G05 E11-3151-G25A E11-3151-G29 El1-3153-GIO E11-3153-G12 E11-3153-G16 E11-3154-G05

E11-3154-G09 E11-3154-G22 E11-3154-G28 El 1-3157-G04 El 1-3157-G24 El 1-3157-G29 E11-3158-G33 El 1-3158-G46 E11-3158-G50 E11-3159-G06 Exams Method VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Component Support Type R G G A A R SP G R G SP R SP R R G SP R SP R R R SP R R R R SP R Relief RequestInspection Pe 1 2 09C 09C R aod 3 07C Remarks 1OC 09C IOC 09C 1OC 07C 08C 09C 09C lOC F1.20 F1.20 F1.20 13C F1.40 (SLC, Ref. M-3361-5)13C F1.40 (RHR, Ref. M-3153-5)F1.20 F1.20 F1.20 12C F1.20 12C F1.20 F1.20 F1.20 llC F1.20 F1.20 F1.20 F1.20 F1.20 12C F1.20 F1.20 F1.20 llC F1.20 F1.20 F1.20 F1.20 F1.20 F1.20 F1.20 12C F1.20 F1.20 08C 07C 09C 09C 10C 09C 09C 07C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE B FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 5 Code Class Identification Number El 1-3159-G09 Ell-3160-GOI E11-3160-G19 Ell-3161-GIl E11-3161-G15 El 1-3164-G 11 E11-3164-G17A El1-3164-G21 E11-3177-G18 E11-3177-G19 El 1-3177-G30 E11-461 1-G04 E11-461 1-G09 E11-461 1-G15 El1-4612-GIO E11-4612-G12 El1-5370-GO1 El 1-5370-G02 El 1-5370-G03 El 1-5370-G04 El 1-5370-GO5 E2101COO1A Pump Base Anchor E21-3144-G03 E21-3144-G06 E21-3144-GI1 E21-3144-G16 E21-3144-G20 E21-3145-G05 E21-3147-G13 Exams Method VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Component Support Type R SP G R R G R SP R R G SP R R R G G G G G A A SP A R R R SP R Relief Request Inspection Pe 1 2 08C 08C 07C 08C 08C IOC IOC 08C 08C 08C riod 3 Remarks 11C F1.20 F1.20 12C F1.20 12C F1.20 F11.20 F1.20 12C F1.20 F1.20 F1.20 F1.20 F1.20 12C F1.20 12C F1.20 F1.20 1lC F1.20 F1.20 11C F1.40 (100% Div 2 RHR HTX Supports)

F1.40 (100% Div 2 RHR HTX Supports)

F 1.40 (100% Div 2 RHR HTX Supports) 11C F 1.40 (100% Div 2 RHR HTX Supports)

F 1.40 (100% Div 2 RHR HTX Supports) 13C F1.40 (CS, Ref. M-3144-5)F1.20 1lC F1.20 12C Fl.20 F1.20 11C F1.20 12C F1.20 12C F1.20 09C 08C 07C 08C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE B FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 6 Code Class Identification Number E21-3147-G20 E21-3147-G35 E21-3147-G39 E21-3148-G29 E21-3148-G37 E21-3148-G48

E21-3149-G05 E21-3149-G06 E21-3150-G02 E4101COO1A Pump Base Anchor E4101COO1B Pump Base Anchor E4101C002 Turbine Base Anchor E41-3162-GO1 E41-3162-G03 E41-3162-G13 E41-3163-GO1 E41-3163-G12 E41-3167-GOI E41-3167-G13

E41-3167-G15 E41-3169-G100 E41-3169-G13 E41-3169-G17 E41-3172-GO1 E41-3172-G14 E41-3172-G18 N30-3258-G02 N30-3258-G07 N30-3258-G17(A-D)

Exams Method VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Component Support Type G R SP R SP R SP R R A A A SP R G SP R R SP R G SP R SP R G C C R Relief Request Inspection Pe 1 2 09C 07C 10C 09C 10C 07C 09C 09C eriod 3 Remarks F1.20 F1.20 F1.20 F1.20 F1.20 12C F1.20 11C F1.20 llC F1.20 F11.20 13C F1.40 (HPCI, Ref. M-3167-5)13C F1.40 (HPCI, Ref. M-3163-5)13C F1.40 (HPCI, Ref. M-3162-5)F11.20 F1.20 12C F1.20 F1.20 12C F1.20 F1.20 F1.20 12C F1.20 F1.20 F1.20 F1.20 F1.20 llC F1.20 11C F1.20 F1.20 F1.20 F1.20 I 08C 07C 10C 08C 09C 10C 07C 07C 07C 10C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAMTABLE B FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 7 Code Class 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 3 3 3 Identification Number N30-3259-G02 N30-3259-G25 N30-3259-G73 P1 1-3566-GIO T48-2095-GO1 T48-2095-GO7B T48-2095-G10A T48-2095-G19 T48-2095-G22 T48-2095-G24A T48-2095-G25 T48-2095-G26A T48-2097-G07 T48-2097-G1 3B T48-2097-G17 T48-2097-G19 T48-2097-G21 T48-2097-G22A T48-2097-G25A T48-2097-G34 Torus Earthquake Ties (4 locations)

Torus Pen X-223A Pipe Anchor Torus Pen X-223B Pipe Anchor Torus Pen X-224B Pipe Anchor Torus Pen X-225 Pipe Anchor Torus Support Girders (16 locations)

El 1-2179-G20 El 1-2180-G14 El 1-2183-G07 Exams Method VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Component Support Type C R SP SP SP R R G R R R R R R R G R R R G A A A A A A R G G Relief Request Inspection Pe 1 2 07C 09C 07C 08C lOC 09C 1OC 07C 10C 07C 07C 08C eriod 3 Remarks F1.20 F11.20 12C F1.20 F1.20 F1.20 11C F1.20 F1.20 11C F1.20 F11.20 F1.20 F11.20 12C F1.20 F1.20 F1.20 llC F1.20 11C F1.20 F1.20 F1.20 F1.20 F1.20 13C F1.40 (Containment, Ref. CB&I No. 1)13C F1.20 (RHR, Ref. M-3153-5)13C F1.20 (RHR, Ref. M-3153-5)13C F1.20 (CS, Ref. M-3148-5)13C F1.20 (HPCI, Ref. M-3163-5, M-5373-5)13C F1.40 (Containment, Ref. CB&I No. 1)F1.30 12C F1.30 F1.30 09C 09C 07C 10C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE B FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 8 Code Class 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 Identification Number E11-2183-G15 E11-2184-G12 E11-2184-G22 El 1-3184-G04 El 1-3184-G08 El1-3184-G10 E11-3184-G18 El 1-3185-G40 E11-3185-G53 El 1-3185-G58 E11-3185-G60 El 151COOIA Pump Base Anchor P42-3340-G06 P4400BOO1C HX Base Anchor P4400COO1A Pump Base Anchor P44-3047-G28 P44-3048-G10 P44-3084-G10

P44-3084-G15 P44-3189-G38 P44-3189-G42 P44-3189-G47 P44-3336-GOI P44-3336-G15 P44-3337-G13 P44-3337-G16 P44-3345-G02 P44-3345-G08 P44-3346-G02 Exams Method VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Component Support Type R R G G R R R R SP SP G A SP A A G SP R R SP R R A R R R G R G Relief Request Inspection Period 1 2 3 Remarks 08C 1OC 08C 09C 07C 09C 09C 09C 09C F1.30 F1.30 F1.30 12C F1.30 F1.30 llC F1.30 F1.30 F1.30 F1.30 12C F1.30 F1.30 13C F1.40 (RHRSW, Ref. M-N-2179-2)

F1.30 13C F1.40 (EECW, Ref M-3351-2)13C F1.40 (EECW, Ref. M-3351-2)llC F1.30 F1.30 F1.30 F1.30 F1.30 F1.30 F1.30 F1.30 lC F1.30 12C F1.30 F1.30 F1.30 F1.30 llC F1.30 07C 07C 08C 07C 1OC 1OC 09C lOC 09C 08C DETROIT EDISON COMPANY -FERMI 2 INSERVICE INSPECTION NDE PROGRAM TABLE B FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 9Code Class 3 3 3 3 3 3 3 3 3 3 3 3 3 3.3 3 3 3 3 3 Identification Number P44-3346-G12 P44-3347-GIO P44-3347-G14

P44-3348-G12 P44-3351-G28 P44-3351-G41 P44-3362-G31 P44-3362-G41 P44-3368-G31

P44-3368-G38 P44-3558-G14 P44-3559-G12 P44-4624-GO1 P44-4624-G 12 P44-4625-G03 P44-4625-G13 P44-4628-G02 P44-4629-GO5 P44-4629-G08 P44-EECW Head Tank Sprts (Div. 2)Exams Method VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Component Support Type R R R A R SP R G R R R R G R G R R G R Relief Request Inspection Pe 1 2 07C 07C 08C 10C 09C 10C 09C riod 3 Remarks 12C F1.30 F1.30 12C F1.30 F1.30 F1.30 12C F1.30 12C F1.30 12C F1.30 liC F1.30 12C F1.30 12C F1.30 F1.30 liC F1.30 12C F1.30 liC F1.30 F1.30 F1.30 F1.30 F1.30 F1.40 (100% Div 2 EECW Head Tank Supports)12C F1.40 (100% Div 1 EECW Heater Supports)13C F1.40 (EESW, Ref. M-N-2178-2)

F1.30 liC F1.30 12C F1.30 F1.30 F1.30 F1.30 08C 08C 3 3 3 3 3 3 3 3 P44-EECW Htr Sprts (Div. 1)P4500C002A Pump Base Anchor P45-2178-G09P45-2204-GI l P45-3352-G02 P45-3352-G06 P45-3353-GO5 P45-3359-G03 A R R G R R G 09C 07C 08C IOc DETROIT EDISON COMPANY -FERMI 2INSERVICE INSPECTION NDE PROGRAMTABLE B FERMI 2 NUCLEAR POWER PLANT ISI -NDE Program Rev. 6 Change 2 Page 10 Code Class Identification Number P45-3360-G04 P45-3360-G07 P45-4626-G03 P45-4626-G08 P45-4627-G06 P45-4627-G12 P45-4630-G04 P45-4631-G04 P45-4631-G13 P45-4632-G08 P45-4632-GI0 R3001B002 Oil Cooler Anchor R3001B017 Jckt. Cooler Anchor R3001C005 Pump Base Anchor R30-2176-G17 R30-2176-G28 R30-2176-G31 R30-2177-G04

R30-2177-G27 R30-2177-G31 R30-218 1-G04 R30-2181-G15 R30-2182-G02 R30-2182-G14RHR Complex Pipe Pen Seal MK101RHR Complex Pipe Pen Seal MK102 RHR Complex Pipe Pen Seal MK145RHR Complex Pipe Pen Seal MK149 T300 1B025 Air Cooler Anchor Exams Method VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 Component Support Type R G G A A R R R G R G A A A G A G R R G R R G R A A A A A Relief RequestInspection Pe 1 2 10C 09C 09C 09C 10C riod 3 Remarks F11.30 F11.30 12C F1.30 12C F1.30 12C F1.30 llC F1.30 F1.30 F1.30 llC F1.30 F11.30 llC F1.30 13C F1.40 (EDGSW, Ref M-N-2176-2) 13C F1.40 (EDGSW, Ref M-N-2176-2) 13C F1.40 (EDGSW, Ref. M-N-2176-2)

F1.30 F1.30 F1.30 F1.30 llC F1.30 F1.30 llC F1.30 F1.30 F1.30 F11.30 13C F1.30 (EESW, Ref. M-N-2178-2) 13C F1.30 (RHRSW, Ref. M-N-2179-2) 13C F1.30 (EDGSW, Ref. M-N-2176-2) 13C F1.30 (EDGSW, Ref. M-N-2176-2) 13C F1.40 (EDGSW, Ref M-N-2176-2) 07C 08C 10C 09C 08C 1OC 09C 07C SECTION 8

SUMMARY

OF CONTAINMENT INSPECTIONS (IWE)

ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE ACTIONS TAKEN UPDATED PROGRAM TABLE Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)131 8.0

SUMMARY

OF CONTAINMENT INSPECTIONS (IWE)8.1 PROGRAM STATUS, ASME SECTION XI CREDIT

-IWE 8.1.1 CATEGORY:ITEM NO: E-A E1.11 Containment Surfaces Accessible Surface Areas (each period)Description Total Total Com Requiring Examination(l) 2 2 Examined To Date 2 Examined To Date (%)100%Minimum Required (%)100%Maximum Allowed (%)100%Accessible Liner Surfaces TOTAL 2 2 2100%100%100%

NOTE: (1) Per 10CFR50.55a, 100% of the accessible surfaces of the containment were required to be inspected (General Visual) during the first period (RF07) and once every period after.During RF09, a 100% inspection was completed of the accessible areas of the primary containment, which completed the inspection requirement for the 2 nd period. During RF 11, again 100% of the accessible surface was inspected. The RF 11 inspection completes therequirements for the 3rd period (ISI/IST Evaluation 06-038). A General Visual inspection is also required prior to each Type A Test. A Type A Test was performed during RF 12 as well as a 100% "General Inspection" of the accessible surface of the primary containmentpressure retaining boundary.

8.1.2 CATEGORY:ITEM NO: E-A E1.12 Containment Surfaces Accessible Surface Areas Description Total Total Comp. Requiring Examination(l)

Examined To Date Examined To Date (%)Minimum Required (%)Maximum Allowed (%)Accessible 1 1 1 91% 80% 100%Liner Surfaces TOTAL 1 1 1 91% 80% 100%NOTE: (1) Inspections (VT-3) will be performed during the 3 rd Period, RF1 1 and RF12 (91% of containment surface inspected during RF11). IWE-1230(a)(4) requires that 80% of the surface area identified in Table IWE-2500-1, Examination Category E-A be inspectedInspections completed through R.F11 are 78% (ISI/IST Evaluation 06-035). Additional VT-3 inspections were completed during RF 12 of the Tour Vent system. The total area inspected now is 91.2% (ISI/IST Evaluation 08-006).Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)132 8.1.3 CATEGORY: ITEM NO: E-A E1.20 Containment Surfaces Vent System -Accessible Surface Areas Description Total Comp.Total Requiring Examination(l)

Examined To Date Examined To Date (%)Minimum Required (%)Maximum Allowed (%)Accessible 1 1 1 98% 80% 100%Liner Surfaces TOTAL 1 1 1 98% 80% 100%NOTE: (1) Inspections (VT-3) will be performed during the 3 rd Period, RF1 1 and RF12 (25% of Vent System surface inspected during RF1 1). IWE-1230(a)(4) requires that 80% of the surface area identified in Table IWE-2500-1, Examination Category E-A be inspected.

Inspections completed through RF1 1 are 78% (ISI/IST Evaluation 06-035). Additional VT-3 inspections were completed during RF 12 of the Tour Vent system. The total area inspected now is 91.2% (ISI/IST Evaluation 08-006).8.1.4 CATEGORY:ITEM NO: E-B E3.10 Pressure Retaining Welds Containment Penetration Welds Description Total Comp Total Requiring Examination (1)0 Examined To Date 0 Examined To Date N/A Minimum Required N/A Maximum Allowed (%)N/A Visual Surfaces 0 TOTAL 0 0 0 N/A N/A N/A NOTE: (1) 1OCFR 50.55a(b)(2)(x)(c) lists this an as optional inspection because there is no currently identified degradation mechanism. Current visual examinations are satisfactory.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)133 8.1.5 CATEGORY: ITEM NO: E-B E3.20 Pressure Retaining Welds Flange Welds Description Total Comp Total Requiring Examination (1)0 Examined To Date 0 Examined To Date N/A Minimum Required (%)N/A Maximum Allowed (%)N/A Visual Surfaces 0 TOTAL 0 0 0N/AN/AN/A NOTE: (1) 10CFR 50.55a(b)(2)(x)(c) lists this as an optional inspection because there is no currentlyidentified degradation mechanism. Current visual examinations are satisfactory.

8.1.6 CATEGORY: ITEM NO: E-B E3.30 Pressure Retaining Welds Nozzle To Shell Welds Description Total Comp Total Requiring Examination (1)0 Examined To Date 0 Examined To Date N/A Minimum Required (%)N/A Maximum Allowed (%)N/A Visual Surfaces 0 TOTAL 0 0 0 N/A N/A N/A NOTE: (1) 1OCFR 50.55a(b)(2)(x)(c) lists this as an optional inspection because there is no currently identified degradation mechanism. Current visual examinations are satisfactory.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)134 8.1.7 CATEGORY:ITEM NO: E-C Containment Surfaces Requiring Augmented Examination E4.11 Visible Surface Description Total Comp Total Requiring Examination (1)0 Examined To Date 0 Examined To Date (%)N/A Minimum Required (%)N/A Maximum Allowed N/A Visual Surfaces 0 TOTAL 0 00N/A N/A N/A NOTE: (1) No Visual augmented examinations have been identified through RF12.8.1.8 CATEGORY:ITEM NO: E-C Containment Surfaces Requiring Augmented Examination E4.12 Surface Area Grid, Min Wall Thickness Locations Description Total Comp Total Requiring Examination (1)0 Examined To Date 0 Examined To Date (%)N/A Minimum Required (%)N/A Maximum Allowed (%)N/A Surface Area Grid TOTAL 0 0 0 0N/AN/A N/A NOTE: (1) No Visual augmented examinations have been identified through RF112.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)135 8.1.9 CATEGORY:ITEM NO:E-D Seals, Gaskets, and Moisture Barriers E5.10 Seals Description Total Comp Total Requiring Examination(l) 61 Examined To Date (1)Examined To Date N/A Minimum Required N/A Maximum Allowed (%)N/A Seals 61 TOTAL 61 61 (1)N/A N/A N/A NOTE: (1) Code requires a visual examination, VT-3, of all seals, gaskets, and other devices once each interval. Request for Relief CISI-00 1 has been approved to verify the leak tightness of seals and gaskets in accordance with the 1 OCFR50, Appendix J Program.8.1.10 CATEGORY:ITEM NO: E-D E5.20 Seals, Gaskets, and Moisture Barriers Gaskets Description Total Comp Total Requiring Examination(l)

Examined To Date Examined To Date (%)Minimum Required (%)Maximum Allowed (%)Gasket 31 31 (1) N/A N/A N/A TOTAL 31 31 (1) N/A N/A N/A NOTE: (1) Code requires a visual examination, VT-3, of all seals, gaskets, and other devices onceeach interval. Request for Relief CISI-001 has been approved to verify the leak tightness of seals and gaskets in accordance with the 10CFR50, Appendix J Program.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)136 8.1.11 CATEGORY: ITEM NO: E-D E5.30 Seals, Gaskets, and Moisture Barriers Moisture Barrier Description Total Comp Total Requiring Examination 1 Examined To Date 1 Examined To Date (%)100%Minimum Required (%)100%Maximum Allowed (%)100%Moisture Barrier 1 TOTAL 1 1 1 100%100%100%NOTE: During RF07, 100% of the moisture barrier was inspected and replaced. There was no damage tothe liner at this location.

During RF08, RF09 and RF10, it was inspected again with nodegradation identified.

67% credited for RF08, RF09 and RF10. During RF 11, again 100% ofthe moisture seal was inspected with no damage noted. 100% credited for RF 11. In RF 13 100%of the moisture seal was again inspected.

8.1.12 CATEGORY: ITEM NO: E-F E7.10 Pressure Retaining Dissimilar Metal Welds Dissimilar Metal Welds Description Total Comp Total Requiring Examination (1)0 Examined To Date 0 Examined To Date (%)N/A Minimum Required (%)N/A Maximum Allowed (%)N/A Visual Surfaces 0 TOTAL 0 0 0 N/A N/A N/A NOTE: (1) 1OCFR 50.55a(b)(2)(x)(c) lists this as an optional inspection because there is no currentlyidentified degradation mechanism.

Current visual examinations are satisfactory.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)137 8.1.13 CATEGORY: ITEM NO: E-G E8.10 Pressure Retaining Bolting Bolting Connections Description Total Comp Total Requiring Examination 89 Examined To Date 89 Examined To Date (%N 100%Minimum Required (%)100%Maximum Allowed (%)100%Bolting Connections 89 TOTAL 89 89 89 100%100%100%8.1.14 CATEGORY: ITEM NO: E-G E8.20Pressure Retaining BoltingBolting Connections Description Total Comp Total Requiring Examination(l) 89 Examined To Date (1)Examined To Date (%)N/A Minimum Required (%)N/A Maximum Allowed (%)N/A Bolting Connections Torque TOTAL 89 89 89 (1)N/A N/A N/A NOTE: (1) Code requires a bolt torque or tension test for bolted connections not disassembled.

Request for Relief CISI-007 has been approved to verify the leak tightness of bolted connections in accordance with the 10CFR50, Appendix J Program.8.1.15 CATEGORY:ITEM NO: E-P E9.10 Pressure Retaining Components Pressure Retaining Boundary Description Total Comp Total Requiring Examination(1) 1 Examined To Date (1)Examined To Date (%)N/A Minimum Required N/A Maximum Allowed (%)N/A Pressure Retaining Boundary TOTAL 1 1 1 (1)N/A N/A N/A NOTE: (1) Will be tested in accordance with the 1 OCFR50, Appendix J Program.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV) 138 8.1.16 CATEGORY: ITEM NO: E-P E9.20 Pressure Retaining Components Containment Penetration Bellows Description Total Comp Total Requiring Examination(1) 29 Examined To Date (1)Examined To Date (%)N/A Minimum Required (%)N/A Maximum Allowed N/A Containment Penetration Bellows TOTAL 29 29 29 (1)N/AN/AN/A NOTE: (1) Will be tested in accordance with the 10CFR50, Appendix J Program.8.1.17 CATEGORY: ITEM NO: E-P E9.30 Pressure Retaining Components Airlocks Description Total Comp Total Requiring Examination(l) 1 Examined To Date (1)Examined To Date (%)N/A Minimum Required (%)N/A Maximum Allowed (%)N/A Airlock 1 TOTAL 1 1 (1)N/AN/AN/A NOTE: (1) Will be tested in accordance with the 1 OCFR50, Appendix J Program.8.1.18 CATEGORY:ITEM NO: E-P E9.40 Pressure Retaining Components Seals and Gaskets Description Total Comp Total Requiring Examination(l)

Examined To Date Examined To Date (%)Minimum Required (%)Maximum Allowed (%)Seals 92 92 (1) N/A N/A N/A And Gaskets TOTAL 92 92 (1) N/A N/A N/A NOTE: (1) Will be tested in accordance with the 10CFR50, Appendix J Program.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)139 8.2 Refuel 13 This is a summary of the IWE inspection activities completed at Fermi 2 during the RF 13 refueling outage.The inspection scope during RF 13 was limited as all required Code inspection for the 10 yearinterval were completed during RF12. The areas that were inspected were areas with a history of degradation from past inspection. These areas were the drywell floor to containment liner moisture seal and repaired coatings in the torus.ABSTRACT OF CONDITION NOTED AND CORRECTED ACTIONS TAKEN Three CARDs were generated as a result of the inspections.

There are CARD 09-22447 "TorusInterior Degraded Coating Repairs", 09-23021 "Degraded Moisture Seal", and 09-23022"Degraded Protective Coating". CARD 09-22447 identified the failure of coating repairs in the torus, all areas were repaired on the primary containment shell. CARD 09-23021 identified damaged areas in the moisture seal at the drywell floor to primary containment shell interface, these areas will be repaired in RF14. CARD 09-23002 identified damaged paint also at thedrywell floor to primary containment shell interface, this is scheduled for repair in RF-14.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)140 Refuel 12 This is a summary of the IWE inspection activities completed at Fermi 2 during on-lineinspections completed during cycle 12, and inspections completed RF 12 refueling outage. On-line inspections included the inspection of two bolted connection, Examination Category E8.10.On-line inspections included the complete; both vapor space and immersed space, VT-3 inspections of the Torus interior, as well as all the vent system located in the torus. All inspections were by direct methods. Also, 100% to the drywell floor to containment liner moisture seal was inspected.

During RF 12 an Integrated Leak Rate Test (Type A Test) was performed.

Per Examination Category El. 10, a General Visual inspection is required prior to the performance of a Type A Test. This General Inspection of 100% of the Primary Containment assessable surface was also completed during RF 12.The completion of RF 12 marks the completion of the first 10 year interval of the IWE at Fermi 2.The total surface area of the primary containment pressure boundary, which received a VT-3 inspection, was 92.1% for the 10 year interval.ABSTRACT OF CONDITION NOTED AND CORRECTED ACTIONS TAKENOne CARD was generated as a result of the inspections during RF12. CARD 07-26887 identifiedtwo areas of degraded coatings, which will be re-inspected during RF 13 and trended.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)141 Refuel-i 1 This is a summary of the IWE inspection activities completed at Fermi 2 during on-line inspections completed during cycle 11, and inspections completed RF 11 refueling outage.

On-line inspections include VT-3 inspections of 100% of the torus exterior and portions of the drywell to torus expansions bellows. The inspection scope during RF 11 consisted of VT-3 inspections 100% of the exposed drywell interior and exterior, Percentages of the containment bellows, and of the containment vent system. Also, 100% to the drywell floor to containment liner moisture seal was inspected, as well as, a representative sample of the primary containment bolting was examined.During all VT-3 inspections, the protective coatings as well as the metallic shell was examined.The on-line inspections, as well as the refuel inspections were completed by using both by direct and remote visual inspection methods.General inspections during RF 10 identified six areas as requiring coating repairs in the drywell basement area. These repairs were completed during RF111 under WR #000Z043787.

After therepairs were completed the areas received baseline general visual inspections of the protective coating.ABSTRACT OF CONDITION NOTED AND CORRECTED ACTIONS TAKEN During Cycle 11 and RF11 the following inspections were performed:

VT-3 inspection of 100% of the torus exteriors protection coatings and metallic shell." VT-3 inspection of 100% of the drywell exposed interior and exterior protection coatings and metallic shell.* VT-3 inspection of 100% of the drywell floor to metallic shell moisture seal.* VT-3 inspection of four drywell to torus downcomers expansion bellows.* VT-3 inspection of eight drywell expansion bellows.* VT-1 inspection of 26 primary containment bolted connections.

General visual inspection of coating repairs in the drywell basement.The following discrepancies were identified during the above inspections:

Degraded protective coatings on the torus exterior, 16 locations identified for repair(CARD 05-25459).

During the week of 6/19/2006 these areas had their protectivecoatings repaired under Work Request 000Z052922 and were re-inspected under Job 144206023.

Minor tool punch marks on torus exterior, CARD generated to document condition, norepair required (CARD 05-25341).

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)142 Refuel-10 This is a summary of the IWE inspection activities completed at Fermi 2 during the tenth refueling outage. RF10 concluded the second period in the interval and now aligns with the ISINDE Program.

The inspection scope was limited as the majority of the second period inspections were completed during RF09. Inspections consisted of the protective coating areas that were repaired during RF09, the drywell basement moisture seal, primary containment bolting on relief valves that were removed for testing, along with other miscellaneous bolting.

ABSTRACT OF CONDITION NOTED AND CORRECTED ACTIONS TAKEN During RF 10, the following inspections were performed:

A general visual inspection of the protective coatings in the drywell basement area.* The moisture seal at the drywell basement floor to steel liner was inspected.

18 bolted primary containment connections were inspected, 9 while the bolting material wasunder tension and 9 while the flanged connection was disassembled.

While not credited, an inspection was also performed of the interior of the torus vent header during its closeout.* During the cycle, the exterior of the torus was inspected.The following discrepancies were identified during the above inspections:

Degraded protective coating in the drywell basement area, eight locations were identified(CARD 04-26062).," Degraded protective coatings in the torus vent header (CARD 04-26143).

Evaluation of degraded protective coating in the drywell basement (CARD 04-26144).

Additionally, in preparation for torus diving inspections and coating repairs schedule for RF 10,past inspection reports were reviewed.

In the RF08 Torus Desludge, Inspection

& Coating Repair Report, the review identified a corrosion pit in the torus shell that had not previously been brought to the attention of Fermi 2 personnel. The corrosion pit is located in Bay 3, Quadrant 2.The pit is 1/4 inch in diameter and has a depth of 0.0285 inches. The pit and the surrounding area was cleaned and the protective coating was reapplied.

The pit was evaluated and accepted in CARD 04-21434.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)143 8.3 Refuel-09 This is a summary of the IWE inspection activities completed at Fermi 2 during the ninth refueling outage. The RF09 scope included the required 2 nd period 100 percent inspection of the accessible surfaces of the primary containment and a representative sample of VT-I and VT-3 inspections of primary containment bolted components.

This is the second refueling outage of the 2 nd period, which consist of three refueling outages, with RF09 containing the majority of the inspections.

ABSTRACT OF CONDITION NOTED AND CORRECTED ACTIONS TAKEN Locations where degraded coating was identified during RF07 and RF08 were reinspected prior to repair. Areas identified showed no further degradation in their condition.

These areas had a thin layer of surface rust, which was a result of condensation from overhead lines dripping down onto the primary containment shell.During RF09, 11 locations below the 583 feet elevation had their protective coating replaced.During the protective coating prep work, no material loss of the primary containment shell was noted. In addition to these 11 areas, a pit at the I-Beam weld, at elevation 583 feet, azimuth 77 deg, was cleaned and repainted. Finally, seven arc strikes, which had been previously blendground, were recoated.

During RF09, areas that were repaired during RF07 were reinspected with particular attention given to the moisture seal located at the concrete floor to drywell shell interface and the paintedsurface in this area. These inspections identified no new or unexpected degradation.The inspections of the remainder of the primary containment resulted in the issuance of 7 condition assessment resolution documents (CARDs). CARD 03-14450, "Water Accumulation in Torus Downcomer to Vent Header Tee Connections," was generated to address the water accumulation in the ring header. None of the other CARDs were an operability concern and were issued for trending and cleanliness issues.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)144 8.4 Refuel-08 This is a summary of the IWE inspection activities completed at Fermi 2 during the eighth refueling outage. The RF08 inspection scope was limited. This was a result of 10CFR50.55a being reissued with the requirement that IWE be implemented on an expedited basis and that all of the lStperiod inspections be completed by September 2001. As a result, Fermi 2 was requiredto complete all the l't period inspections during RF07. This resulted in the 2 nd period consisting of three refueling outages, with RF09 containing the majority of the inspections.

ABSTRACT OF CONDITION NOTED AND CORRECTED ACTIONS TAKEN Locations where degraded coating was identified during RF07 were reinspected to reassess their condition. No further degradation was identified.

These areas were mapped and will bescheduled for re-coating during RF09.

During RF08, areas that were repaired during RF07 were reinspected with particular attention given to the moisture seal located at the concrete floor to drywell shell interface and the painted surface in this area. These inspections identified no new degradation since the repair work was completed.

During RF08, the immersed areas of the torus was desludged, after which both the immersed and vapor spaces were inspected by certified VT inspectors.

All areas of coating degradations were recorded.

None of the areas where the protective coating was degraded exhibited any pitting or degradation of the containment liner. After the initial VT inspections, locations with degraded protective coating were repaired.

Detroit Edison Co., One Energy Plaza, Detroit, MI 48226* Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)145 8.5 Refuel-07 This is a summary of the IWE inspection completed at Fermi 2 during the seventh refuelingoutage. 10CFR50.55a was reissued with the requirement that IWE be implemented on an expedited basis and that all of the 1 st period inspections be completed by September 2001. As a result, Fermi 2 was required to complete all the 1 " period inspections during the seventh refueling outage as the eighth refueling outage is not scheduled until October 2001.ABSTRACT OF CONDITION NOTED AND CORRECTED ACTIONS TAKENDuring the general visual inspections of the containment liner, several conditions were reported which required corrective actions. The reported conditions are listed as follows:* Degradation of the moisture seal at the drywell floor to drywell liner interface.

Loose protective coating in the area of the drywell floor to steel liner interface, from the floor and up one foot.* Penetration radiation shield plate was found wedged into the penetration without the required tack welds.* Outer drywell airlock seal had a crack in the rubber gasket.* Material loss on a single tie-down eyebolt on the north equipment hatch.All of the above conditions were repaired or replaced by corrective maintenance activities." Arc strikes on the south equipment hatch sealing area.* Degradation of the protective coating at various locations on the containment liner, both interior and exterior." A pit of 0.093 inches in depth at the liner to I beams interface.

The above conditions were evaluated using prudent engineering analysis and were determined to be acceptable for the eighth operating cycle. Corrective maintenance for the above is being planned for future refueling outages.Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)146 IWE Containment Program Component Examination Schedule ISI-NDE Program Rev.6; Change 0 Period 1 Period 2 Period 3 Appendix F4.7 Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RFll RF12 Relief Request Remarks I 1 Drywell E-A (Drywell inspections consisted of items 3 through 35.)2 Suppression Chamber (Torus) E-A (Torus inspections consisted of items 36 through 120.) 3 Drywell Interior 563' to 583' (Az 0 to E-A 90)4 Drywell Interior 563' to 583' (Az 90 E-A to 180)5 Drywell Interior 563' to 583' (Az 180 E-A to 270)6 Drywell Interior 563' to 583' (Az 270 E-A to 0)7 Drywell Interior 583' to 613' (Az 0 to E-A 90)8 Drywell Interior 583' to 613' (Az 90 E-A to 180)9 Drywell Interior 583' to 613' (Az 180 E-A to 270)10 Drywell Interior 583' to 613' (Az 270 E-A to 0)11 Drywell Interior 613' to 641' (Az 0 to E-A 90)12 Drywell Interior 613' to 641' (Az 90 E-A to 180)13 Drywell Interior 613' to 641' (Az 180 E-A to 270)E1.11 VT-G E1.11 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G GC GC GC GC GC GC N\A Once per Period, Prior to each Type A Test GC GC NMA Once per Period, Prior to each Type A Test GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC VTC VTC VTC VTC VTC VTC VT-C VTC VTC VTC VTC GC GC GC GC GC N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings GC N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings NMA Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings NMA Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings GC GC GC GC GC GC GC GC GC GC Monday, July 13, 2009 Page 1 of 23 Component Examination Schedule ISI-NDE Program Rev.6; Change 0 Period I Period 2 Period 3 Appendix F4.7 Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF1O RF11 RF12 Relief Request Remarks 14 Drvwell Interior 613' to 641' (Az 270 E-A E1.12 VT-3 VTC GC to 0)15 Drywell Interior 641'to 659'(Az 0 to E-A 90)16 Drywell Interior 641' to 659' (Az 90 E-A to 180)17 Drywell Interior 641' to 659' (Az 180 E-A to 270)18 Drywell Interior 641' to 659' (Az 270 E-A to 0)19 Drywell Dome Interior and Exterior E-A 20 Drywell Exterior 563' to 583' (Az 0 E-A to 90)21 Drywell Exterior 563' to 583' (Az 90 E-A to 180)22 Drywell Exterior 563' to 583' (Az E-A 180 to 270)23 Drywell Exterior 563' to 583' (Az E-A 270 to 0)24 Drywell Exterior 583' to 613' (Az 0 E-A to 90)25 Drywell Exterior 583' to 613' (Az 90 E-A to 180)26 Drywell Exterior 583' to 613' (Az E-A 180 to 270)27 Drywell Exterior 583' to 613' (Az E-A 270 to 0)28 Drywell Exterior 613' to 641' (Az 0 E-A to 90)VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 Vr-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 Vr-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G E1.12 VT-3 VT-G GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC'I-O VTO VTOC VTO VTO VTOC'/TO VTO\,1-0 VTOC VTO VTO VTO VTOC GC GC GC GC GC NA Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings NMA Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings NMA Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings NMA Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure,stiffingrings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings NMA Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings NMA Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings Monday, July 13, 2009 Page 2 of 23 Component Examination Schedule I Period 11 Period 2 1 Period 3 I ISI-NDE Program Rev.6; Change 0 Appendix F4.7 f Request Remarks Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 Relie 29 Drywell Exterior 613' to 641' (Az 90 E-A E1.12 VT-3 VTC to 180)VT-G 30 Drywell Exterior 613' to 641' (Az E-A E1.12 VT-3 180 to 270) VT-G 31 Drywell Exterior 613' to 641' (Az E-A E1.12 VT-3 270 to 0) VT-G 32 Drywell Exterior 641' to 659' (Az0 E-A E1.12 VT-3to 90) VT-G 33 Drywell Exterior 641' to 659' (Az 90 E-A E1.12 VT-3 to 180) VT-G 34 Drywell Exterior 641' to 659' (Az E-A E1.12 VT-3 180 to 270) VT-G 35 Drywell Exterior 641' to 659' (Az E-A E1.12 VT-3 270 to 0) VT-G 36 Torus Interior Bay 1 E-A E1.12 VT-3 VT-G 37 Torus Interior Bay 2 E-A E1.12 VT-3 VT-G 38 Torus Interior Bay 3 E-A E1.12 VT-3 VT-G 39 Torus Interior Bay 4 E-A E1.12 VT-3 VT-G 40 Torus Interior Bay 5 E-A E1.12 VT-3 VT-G 41 Torus Interior Bay6 E-A E1.12 VT-3 VT-G 42 Torus Interior Bay 7 E-A E1.12 VT-3 VT-G 43 Torus Interior Bay 8 E-A E1.12 VT-3 VT-G GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC-VTO C-VTC-VTOC --VVTC --VTC --VTO --VTPC VTc-VTPC VTC-VTPC VTC-VTPC VTC-VTPC VTC-VTPC V-c-VTPC VTC N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openingsMonday, July 13, 2009 Page 3 of 23 Component Examination Schedule ISI-NDE Program Rev.6; Change 0 I Period II Period 2 1 Period3 1 Appendix F4.7 Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 Relief Request Remarks 44 Torus Interior Bay 9 E-A E1.12 VT-3 VTPC VTC N\A Includes parts of reinforcing structure, VT-G 45 Torus Interior Bay 10 46 Torus Interior Bay 11 47 Torus Interior Bay 12 48 Torus Interior Bay 13 49 Torus Interior Bay 14 50 Torus Interior Bay 15 51 Torus Interior Bay 16 52 Torus Exterior Bay 1 53 Torus Exterior Bay 2 54 Torus Exterior Bay 3 55 Torus Exterior Bay 4 56 Torus Exterior Bay 5 57 Torus Exterior Bay 6 58 Torus Exterior Bay 7 E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openingsIncludes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings VTC VT-C VTC-VTC VT-C VT-C GC GC GC GC GC GC GC Monday, July 13, 2009 Page 4 of 23 Component Examination ScheduleISI-NDE Program Rev.6; Change 0 Period 1 Period 2 Period 3 Appendix F4.7 Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF1O RF11 RF12 Relief Request Remarks 59 Torus Exterior Bay 8 E-A E1.12 VT-3 -VTC VT-G 60 Torus Exterior Bay 9 61 Torus Exterior Bay 10 62 Torus Exterior Bay 11 63 Torus Exterior Bay 12 64 Torus Exterior Bay 13 65 Torus Exterior Bay 14 66 Torus Exterior Bay 15 67 Torus Exterior Bay 16 100 Drywell Penetration Expansion Bellow X-007A 101 Drywell Penetration Expansion Bellow X-007B 102 Drywell Penetration Expansion Bellow X-007C 103 Drywell Penetration Expansion Bellow X-007D 104 Drywell Penetration Expansion Bellow X-008 105 Drywell Penetration Expansion Bellow X-009A E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC VTC VTC VTC VTC VTC VTC VTC VTC VTC VTC VT-C VTC GC GC GC GC GC GC GC GC N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings GC N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers GC GC GC GC GC GC Monday, July 13, 2009 Page 5 of 23 Component Examination Schedule ISI-NDE Program Rev.6; Change 0 I Period 1I Period 2 Period 3 1 Appendix F4.7 Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 Relief Request Remarks 106 Drvwell Penetration Expansion E-A E1.12 Vl'-3 N\A Includes all welds, reinf. plates shell Bellow X-009B 107 Drywell Penetration Expansion Bellow X-010 108 Drywell Penetration Expansion Bellow X-01 1 109 Drywell Penetration Expansion Bellow X-012 110 Drywell Penetration Expansion Bellow X-013A 111 Drywell Penetration Expansion Bellow X-013B 112 Drywell Penetration Expansion Bellow X-016A 113 Drywell Penetration Expansion Bellow X-016B 114 Drywell Penetration Expansion Bellow X-01 7 115 Drywell Penetration Expansion Bellow X-035B 116 Drywell Penetration ExpansionBellow X-035C 117 Drywell Penetration Expansion Bellow X-035D 118 Drywell Penetration Expansion Bellow X-035E 119 Drywell Penetration Expansion Bellow X-035F 120 Drywell Penetration ExpansionBellow X-043 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VTr-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 VT-G E-A E1.12 VT-3 V-I-G GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC VTC VTC VTC VT-C GC GC GC GC GC GC surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers GC N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent headerand downcomers GC N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent headerand downcomers GC N'A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers NA Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent headerand downcomers NMA Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers GC N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent headerand downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent headerand downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers GC GC GC E1.20 Monday, July 13, 2009 Page 6 of 23 Component Examination Schedule ISI-NDE Program Rev.6; Change 0 I Period 1i Period 2 1 Period 3 1 Appendix F4.7 Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 Relief Request Remarks 68 Drvwell to Torus Downcomer to E-A E1.20 VT-3 VTPC N\A Includes parts of reinforcing structure, Bay 2 -Exterior VT-G 69 Drywell to Torus Downcomer to E-A E1.20 VT-3Bay 4 -Exterior VT-G 70 Drywell to Torus Downcomer to E-A E1.20 VT-3 Bay 6 -Exterior VT-G 71 Drywell to Torus Downcomer to E-A E1.20 VT-3 Bay 8 -Exterior VT-G 72 Drywell to Torus Downcomer to E-A E1.20 VT-3 Bay 10 -Exterior VT-G 73 Drywell to Torus Downcomer to E-A E1.20 VT-3 Bay 12 -Exterior VT-G 74 Drywell to Torus Downcomer to E-A E1.20 VT-3 Bay 14 -Exterior VT-G 75 Drywell to Torus Downcomer to E-A E1.20 VT-3 Bay 16 -Exterior VT-G 76 Drywell to Torus Expansion Bellows E-A E1.20 VT-3 Downcomer to Bay 2 VT-G 77 Drywell to Torus Expansion Bellows E-A E1.20 VT-3 Downcomer to Bay 4 VT-G 78 Drywell to Torus Expansion Bellows E-A E1.20 VT-3 Downcomer to Bay 6 VT-G 79 Drywell to Torus Expansion Bellows E-A E1.20 VT-3 Downcomer to Bay 8 VT-G 80 Drywell to Torus Expansion Bellows E-A E1.20 VT-3 Downcomer to Bayl0 VT-G 81 Drywell to Torus Expansion Bellows E-A E1.20 VT-3 Downcomer to Bayl2 VT-G 82 Drywell to Torus Expansion Bellows E-A E1.20 VT-3 Downcomer to Bayl4 VT-G GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC VTPC VTPC VTPC VTPC VTPC VTPC VTPC VTPC VTPC GC GC GC GC GC GC GC stiffing rings, manhole covers and reinforcement around openings N\A. Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers andreinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N'A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings NýA Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings GC N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings GC GC GC GC GC GC GC VTPC Monday, July 13, 2009 Page 7 of 23 Component Examination Schedule I Period 1 1 Period 2 1 Period 3 ISI-NDE Program Rev.6; Change 0 Appendix F4.7 I Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF1O RFll RF12 Relief Request Remarks 83 Drvwell to Torus Expansion Bellows E-A E1.20 VT-3 VTPC GC Downcomer to Bay16 84 Flow Channeling Devices (Ring Header) In Bay 1 -Exterior 85 Flow Channeling Devices (Ring Header) In Bay 2 -Exterior 86 Flow Channeling Devices (Ring Header) In Bay 3 -Exterior 87 Flow Channeling Devices (Ring Header) In Bay 4 -Exterior 88 Flow Channeling Devices (Ring Header) In Bay 5 -Exterior 89 Flow Channeling Devices (Ring Header) In Bay 6 -Exterior 90 Flow Channeling Devices (Ring Header) In Bay 7 -Exterior 91 Flow Channeling Devices (Ring Header) In Bay 8 -Exterior 92 Flow Channeling Devices (Ring Header) In Bay 9 -Exterior 93 Flow Channeling Devices (Ring Header) In Bay 10 -Exterior 94 Flow Channeling Devices (Ring Header) In Bay 11 -Exterior 95 Flow Channeling Devices (Ring Header) In Bay 12- Exterior 96 Flow Channeling Devices (Ring Header) In Bay 13 -Exterior 97 Flow Channeling Devices (Ring Header) In Bay 14- Exterior VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC GC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC VTPC VTC N\A Includes parts of reinforcing structure, stiffing rings, manhole covers and reinforcement around openings N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers Monday, July 13, 2009 Page 8 of 23 Component Examination Schedule ISI-NDE Program Rev.6; Change 0 I Period 1i Period 2 1 Period 3 1 Appendix F4.7 Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF1O RF11 RF12 Relief Request Remarks 98 Flow Channeling Devices (Ring E-A E1.20 VT-3 VTPC VTC Header) In Bay 15 -Exterior 99 Flow Channeling Devices (Ring Header) In Bay 16- Exterior401 Flow Channeling Devices (Ring Header) In Bay 1 -Interior 402 Flow Channeling Devices (Ring Header) In Bay 2 -Interior 403 Flow Channeling Devices (Ring Header) In Bay 3 -Interior 404 Flow Channeling Devices (Ring Header) In Bay 4 -Interior 405 Flow Channeling Devices (Ring Header) In Bay 5 -Interior 406 Flow Channeling Devices (Ring Header) In Bay 6 -Interior 407 Flow Channeling Devices (Ring Header) In Bay 7 -Interior 408 Flow Channeling Devices (Ring Header) In Bay 8 -Interior 409 Flow Channeling Devices (Ring Header) In Bay 9 -Interior 410 Flow Channeling Devices (Ring Header) In Bay 10- Interior 411 Flow Channeling Devices (Ring Header) In Bay 11 -Interior 412 Flow Channeling Devices (Ring Header) In Bay 12 -Interior 413 Flow Channeling Devices (Ring Header) In Bay 13- Interior VT-G GC GC GC GC E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 V--G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 V--3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G VTPC VTC N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers Monday, July 13, 2009 Page 9 of 23 Component Examination Schedule ISI-NDE Program Rev.6; Change 0 I Period 1i Period 2 Period 3 Appendix F4.7 Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 Relief Request Remarks 414 Flow Channeling Devices (Rinq E-A E1.20 VT-3 N/A Includes all welds, reinf. plates shell Header) In Bay 14 -Interior 415 Flow Channeling Devices (Ring Header) In Bay 15 -Interior 416 Flow Channeling Devices (Ring Header) In Bay 16- Interior 417 Drywell to Torus Downcomer to Bay 2 -Interior 418 Drywell to Torus Downcomer to Bay 4 -Interior 419 Drywell to Torus Downcomer to Bay 6 -Interior 420 Drywell to Torus Downcomer to Bay 8 -Interior 421 Drywell to Torus Downcomer to Bay 10 -Interior 422 Drywell to Torus Downcomer to Bay 12 -Interior 423 Drywell to Torus Downcomer to Bay 14 -Interior 424 Drywell to Torus Downcomer to Bay 16- Interior E4.11121 Drywell Interior 123 Drywell Exterior 125 Suppression Chamber Interior 127 Suppression Chamber Exterior E4.12 122 Drywell Interior VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-G E-A E1.20 VT-3 VT-GE-C E4.11 VT-1E-C E4.11 VT-1E-C E4.11 VT-1E-C E4.11 VT-1 E-C E4.12 VOLU surfaces on the ventline, the vent headerand downcomers N/A Includes all welds, reinf. plates shell surfaces on the ventline, the vent headerand downcomers N/A Includes all welds, reinf..plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers N\A Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers NMA Includes all welds, reinf. plates shell surfaces on the ventline, the vent header and downcomers NA No areas identified for augmented exams at this time N\A No areas identified for augmented exams at this time N\A No areas identified for augmented exams at this time N\A No areas identified for augmented exams at this time N\A No areas identified for augmented exams at this time Monday, July 13, 2009 Page 10 of 23 Component Examination Schedule ISI-NDE Program Rev.6; Change 0 Period 1 Period 2 Period 3 Appendix F4.7 Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 Relief Request Remarks 124 Drywell Exterior E-C E4.12 VOLU N\A No areas identified for augmented exams at this time 126 Suppression Chamber Interior E-C E4.12 VOLU N'A No areas identified for augmented exams at this time 128 Suppression Chamber Exterior E-C E4.12 VOLU N\A No areas identified for augmented exams at this time E5.10 129 Drywell Head Flange Seal X-001A 130 South Equipment Hatch Seal X-001 B 131 North Equipment Hatch Seal X-001(132 Drywell Personnel Airlock Seals (2)X-001D 133 Reactor Vessel Stablization Manhole Seal X-001 E 134 Reactor Vessel Stablization Manhole Seal X-001F 135 Reactor Vessel Stablization Manhole Seal X-001 G 136 Reactor Vessel Stablization Manhole Seal X-001 H 137 Reactor Vessel Stablization Manhole SeaIX-001J 138 Reactor Vessel Stablization Manhole Seal X-001 K 139 Reactor Vessel Stablization Manhole Seal X-001 L 140 Reactor Vessel Stablization Manhole Seal X-001 M 141 CRD Hatch Seal X-006142 TIP Penetration Seal X-035A143 TIP Penetration Seal (2) X-035B 144 TIP Penetration Seal (2) X-035C145 TIP Penetration Seal (2) X-035D 146 TIP Penetration Seal (2) X-035E147 TIP Penetration Seal (2) X-035F E-D E-D E-D E-D E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 CISI-001 CISI-001 CISI-001 CISI-001 No Examinations Required, In Appendix J Program No Examinations Required, In Appendix J Program No Examinations Required, In Appendix J Program No Examinations Required, In Appendix J Program E-D E5.10 VT-3 E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E5.10 Vr-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program Monday, July 13, 2009 Page 11 of 23 Item Exam Area Identification 148 Electrical Penetration Bolting X-100A (X-100A)149 Electrical PenetrationSeal X-100B (X-102A)150 Electrical Penetration Seal (100C)151 Electrical Penetration Seal (X-100E)152 Electrical Penetration Seal X-100F (X-103B)153 Electrical Penetration Seal X-100G (X-100G)154 Electrical Penetration Seal X-101A (X-101A)155 Electrical Penetration Seal X-101B (X-101B)156 Electrical PenetrationSeal X-101C (X-101C)157 Electrical Penetration Seal X-101D (X-1 01 D)158 Electrical Penetration Seal X-101E (X-101E)159 Electrical Penetration Seal X-1 01F (X-101 F)160 Electrical Penetration Seal X-102A (X-105B)161 Electrical Penetration SealX-102B (X-102B)162 Electrical PenetrationSealX-102C (X-100B)163 Electrical Penetration SealX-102D (X-105C)164 Electrical Penetration Seal X-103A (X-103A)165 Electrical Penetration Seal X-103B (X-107B)166 Electrical Penetration Seal X-104A (X-104A)167 Electrical Penetration Seal X-104B (X-1046)168 Electrical Penetration Seal X-104C (X-104C)169 Electrical Penetration Seal X-104D (X-104D)170 Electrical Penetration Seal X-104E (X-104E)Monday, July 13, 2009 Cat.E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D Component Examination Schedule Period 1 Period 2 Period 3 Code NDE Method RF07 RF08 RF09 RF10 RIFll RF12 E5.10 VT-3 E5.10 V'-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 Vr-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 E5.10 VT-3ISI-NDE Program Rev.6; Change 0 Appendix F4.7 I Relief Request Remarks CISI-001 No Examinations Required, In Appendix J Program ClSI-001 No Examinations Required, In Appendix J Program ClSI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program ClSI-001 No Examinations Required, In Appendix J Program ClSI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program ClSI-001 No Examinations Required, In Appendix J Program C0SI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program ClSI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program ClSI-001 No Examinations Required, In Appendix J Program ClSI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program ClSI-001 No Examinations Required, In Appendix J Program ClSI-001 No Examinations Required, In Appendix J Program Page 12 of 23 Item 171 172 173 174 175 176 177 178 179 180 181 182 183 E5.20Exam Area Identification Electrical Penetration Seal X-104F (X-1 04F)Electrical Penetration Seal X-105A (X-105A)Electrical Penetration Seal X-105D (X-105D)Electrical Penetration Seal X-106A (X-100D)Electrical Penetration Seal X-106B (X-106B)South Torus Hatch Seal Penetration X-200A NorthTorus Hatch Seal Penetration X-200B Electrical Penetration Seal X-209A Electrical Penetration Seal X-209C Vacuum Breaker-Electrical Penetration Seal X-228A Vacuum Breaker-Electrical Penetration Seal X-228B Vacuum Breaker-Electrical Penetration Seal X-228C Vacuum Breaker-Electrical Penetration Seal X-228D Cat.E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-D E-DComponent Examination Schedule Period 1I Period 2 Period 3 Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 E5.10 VT-3 -E5.10 VT-3 -E5.10 VT-3 --E5.10 VT-3 --E5.10 VT-3 --E5.10 VT-3 --E5.10 VT-3 --E5.10 VT-3 --E5.10 VT-3 --E5.10 VT-3 E5.10 VT-3 E5.10 VT-3 -E5.10 VT-3 -E5.20 VT-3 -E5.20 VT-3 --E5.20 VT-3 --E5.20 VT-3 --E5.20 VT-3 --E5.20 VT-3 --E5.20 VT-3 --E5.20 VT-3 --E5.20 VT-3 --ISI-NDE Program Rev.6; Change 0 Appendix F4.7 I Relief Request Remarks CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program I 184 Penetration Flange Rupture Disk Gasket X-018 185 Penetration Flange Rupture Disk Gasket X-019 186 Spectacle Flange Gasket X-020 187 Penetration Flange Gasket X-039A 188 Penetration Flange Gasket X-039B 189 Butterfly Valve Flange Gasket Penet. X-205C190 Butterfly Valve Flange Gasket Penet. X-205D 191 RHR Test Line Orifice D008B Gasket Penetration X-210A 192 RHR Test Line Orifice D009B Gasket Penetration X-210A Monday, July 13, 2009 Page 13 of 23 Component Examination Schedule ISI-NDEProgram Rev.6; Change 0 Period I Period2 Period3 Appendix F4.7 Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RFl1 RF12 Relief Request Remarks 193 Relief Valve Flange Gasket E-D E5.20 VT-3 -CISI-001 No Examinations Required, In Appendix E1100F001B Penetration X-210A J Program 194 Relief Valve Flange Gasket E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix E1100F025B Penetration X-210A J Program 195 RHR Blind Flange Gasket E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix Penetration X-21 OA J Program 196 RHR Test Line Orifice D008A E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix Gasket Penetration X-210B J Program 197 RHR Test Line Orifice D009A E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix Gasket Penetration X-210B J Program 198 Relief Valve Flange Gasket E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix E110F001A Penetration X-210B J Program 199 Relief Valve Flange Gasket E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix E1100F025A Penetration X-210B J Program 200 Relief Valve Flange Gasket E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix E1100F029 Penetration X-210B J Program 201 RHR Blind Flange Gasket E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix Penetration X-210B J Program 202 TWMS Spool Gasket 4055-1 E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix Penetration X-213A J Program 203 TWMS Spool Gasket 4055-2 E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix Penetration X-213A J Program 204 TWMS Spool Gasket 4056-1 E-D E5.20 VT-3 --CISI-001 No Examinations Required, In Appendix Penetration X-213B J Program 205 TWMS Spool Gasket 4056-2 E-D E5.20 VT-3 ---CISI-001 No Examinations Required, In Appendix Penetration X-213B J Program 206 Relief Valve Flange Gasket E-D E5.20 VT-3 ----CISI-O01 No Examinations Required, In'Appendix T4804F016A Penetration X-218 J Program 207 Relief Valve Flange Gasket E-D E5.20 VT-3 -----CISI-001 No Examinations Required, In Appendix T4804F016B Penetration X-218 J Program 208 Relief Valve Flange Gasket E-D E5.20 VT-3 -----CISI-001 No Examinations Required, In Appendix E 1100F030D Penetration X-223A J Program 209 Relief Valve Flange Gasket E-D E5.20 VT-3 -----CISI-001 No Examinations Required, In Appendix E1100F030B Penetration X-223B J Program 210 Relief Valve Flange Gasket E-D E5.20 VT-3 -----CISI-001 No Examinations Required, In Appendix E1100F030C Penetration X-223C J Program 211 Relief Valve Flange Gasket E-D E5.20 VT-3 -----CISI-001 No Examinations Required, In Appendix E1100F030A Penetration X-223D J Program 212 Relief Valve Flange Gasket E-D E5.20 VT-3 ------CISI-001 No Examinations Required, In Appendix E2100FO11B Penetration X-227A J Program 213 Relief Valve Flange Gasket E-D E5.20 VT-3 ------CISI-001 No Examinations Required, In Appendix E2100F012B Penetration X-227A J Program 214 Relief Valve Flange Gasket E-D E5.20 VT-3 ------CISI-001 No Examinations Required, In Appendix E2100F032B Penetration X-227A J Program 215 Relief Valve Flange Gasket E-D E5.20 VT-3 ------CISI-001 No Examinations Required, In Appendix E2100F011A Penetration X-227B J Program Monday, July 13, 2009 Page 14 of 23 Item Exam Area Identification 216 Relief Valve Flange Gasket E2100F012A Penetration X-227B 217 Relief Valve Flange Gasket E2100F032A Penetration X-227B E5.30 218 Drywell Moisture Seal (Drywell concrete floor to metal liner)Cat.E-D E-D Component Examination Schedule Period 1I Period 2 Period 3 Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 E5.20 VT-3 E5.20 VT-3 I ISI-NDE Program Rev.6; Change 0 Appendix F4.7Relief Request Remarks CISI-001 No Examinations Required, In Appendix J Program CISI-001 No Examinations Required, In Appendix J Program N/A E-D E5.30 VT-3 34%Complete 67%Complete 100%Complete E8.10 219 Drywell Head Flange Bolting X-001A 220 South Equipment Hatch Bolting X-001 B221 North Equipment Hatch Bolting X-001C 222 Drywell Personnel Airlock Bolting X-001D 223 Reactor Vessel Stablization Manhole Bolting X-001E 224 Reactor Vessel Stablization Manhole Bolting X-001 F 225 Reactor Vessel Stablization Manhole Bolting X-001G 226 Reactor Vessel Stablization Manhole Bolting X-001 H 227 Reactor Vessel Stablization Manhole Bolting X-001J 228 Reactor Vessel Stablization Manhole Bolting X-001K 229 Reactor Vessel Stablization Manhole Bolting X-001 L 230 Reactor Vessel Stablization Manhole Bolting X-001 M 231 CRD Hatch Bolting XK-006 232 Penetration Flange Rupture Disk Bolting X-018 233 Penetration Flange Rupture Disk Bolting X-019 234 Spectacle Flange Bolting X-020 235 TIP Penetration Bolting X-035A 236 TIP Penetration Bolting X-035B 237 TIP Penetration Bolting X-035C 238 TIP Penetration Bolting X-035D 239 TIP Penetration Bolting X-035E Monday, July 13, 2009 E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-i1 E8.10 VT-1 E8.10 VT-i E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-1 E8.10 VT-I1 E8.10 VT-1 VTC VTC VTC VTC VTC VTC VTC VTC VTC VTC VTC VTC N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A VTC VTC VTC VTC'VTC VTC VTC VTC V-rC VTC VTC V'TC VTC VTC VTC Page 15 of 23 Item Exam Area Identification 240 TIP Penetration Bolting X-035F 241 Penetration Flange Bolting X-039A 242 Penetration Flange Bolting X-039B 243 Electrical Penetration Bolting X-100A (X-100A) 244 Electrical Penetration Bolting X-100B (X-102A)245 Electrical Penetration Bolting (X-100c)246 Electrical Penetration Bolting (X-100E)247 Electrical Penetration Bolting X-1OOF (X-103B)248 Electrical Penetration Bolting X-1OOG (X-100G)249 Electrical Penetration Bolting X-101A (X-101A)250 Electrical Penetration Bolting X-101B (X-101B)251 Electrical Penetration Bolting X-101C (X-101C) 252 Electrical Penetration Bolting X-101D (X-101D)253 Electrical Penetration Bolting X-101E (X-101E)254 Electrical Penetration Bolting X-101F (X-101F)255 Electrical Penetration Bolting X-102A (X-105B)256 Electrical Penetration Bolting X-102B (X-102B)257 Electrical Penetration Bolting X-102C (X-1OOB)258 Electrical Penetration Bolting X-1020 (X-105C)259 Electrical Penetration Bolting X-103A (X-103A)260 Electrical Penetration Bolting X-103B (X-107B) 261 Electrical Penetration Bolting X-104A (X-104A)262 Electrical Penetration Bolting X-104B (X-104B) 263 Electrical Penetration Bolting X-104C (X-1 04C)Monday, July 13, 2009 Cat.E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G Component Examination Schedule Period 1 Period 2 Period 3 Code NDE Method RF07 RF08 RF09 RF10 RFll RF12 E8.10 VT-1 VTC -v-c E8.10 VT-1 VTC ---E8.10 VT-1 VTC ---E8.10 VT-1 VTC ---E8.10 VT-1 VTC ---E8.10 VT-1 VTC ---E8.10 VT-1 VTC --E8.10 VT-1 VTC E8.10 VT-1 VTC E8.10 VT-1 VTC E8.10 VT-1 VTC E8.10 VT-1 VTC E8.10 VT-1 VTC E8.10 VT-1 VTC E8.10 VT-1 V-'JC E8.10 VT-1 VI'JC E8.10 VT-1 VTC E8.10 VT-1 VTC -E8.10 VT-1 -VTC E8.10 VT-1 -VTC E8.10 VT-1 -VTC -E8.10 VT-1 -V-E8.10 VT-1 -V-E8.10 VT-1 -V-I I ISI-NDE Program Rev.6; Change 0 Appendix F4.7 Relief Request Remarks N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Page 16 of 23 Item Exam Area Identification 264 Electrical Penetration Bolting X-104D (X-104D)265 Electrical Penetration Bolting X-104E (X-104E)266 Electrical Penetration Bolting X-104F (X-104F)267 Electrical Penetration Bolting X-105A (X-105A)268 Electrical Penetration Bolting X-105D (X-105D)269 Electrical Penetration Bolting X-106A (X-100D) 270 Electrical Penetration Bolting X-106B (X-106B)271 South Torus Hatch Bolting Penetration X-200A 272 NorthTorus Hatch Bolting Penetration X-200B 273 Butterfly Valve Flange Bolting Penet. X-205C 274 Butterfly Valve Flange Bolting Penet. X-205D 275 Electrical Penetration Bolting X-209A 276 Electrical Penetration Bolting X-209C 277 RHR Test Line Orifice D008B Bolting Penetration X-210A 278 RHR Test Line Orifice D009B Bolting Penetration X-210A 279 Relief Valve Flange Bolting E 110F001B Penetration X-210A 280 Relief Valve Flange Bolting E110OF025B Penetration X-21OA281 RHR Blind Flange Bolting Penetration X-210A 282 RHR Test Line Orifice D008A Bolting Penetration X-210B 283 RHR Test Line Orifice D009A Bolting Penetration X-210B 284 Relief Valve Flange Bolting Ell0OF001A Penetration X-210B 285 Relief Valve Flange Bolting E110OF025A Penetration X-210B 286 Relief Valve Flange Bolting E1I0OF029 Penetration X-210B Monday, July 13, 2009 Cat.E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G Component Examination Schedule Period 1I Period 2 Period 3 Code NDE Method RF07 RF08 RF09 RF1O RF11 RF12 E8.10 VT-i VTC E8.10 VT-1 VTC E8.10 VT-1 VTC E8.10 VT-1 VTC E8.10 VT-i VTC E8.10 VT-1 VTC E8.10 VT-1 VTC E8.10 VT-i VTC E8.10 VT-i VTC E8.10 VT-1 VTC E8.10 VT-1 --E8.10 VT-i --VTC -E8.10 VT-i --VTC -E8.10 VT- --VTC -E8.10 VT-1 --VTC -E8.10 VT-i --VTC E8.10 VT-i -VTC -E8.10 VT-i -VTC E8.10 VT-i -VTC -E8.10 VT-i -VTC -E8.10 VT-i -VTC -E8.10 VT-i -VTC -E8.10 VT-I -1VTC ISI-NDE Program Rev.6; Change 0 Appendix F4.7Relief Request Remarks N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Page 17 of 23 Item Exam Area Identification 287 RHR Blind Flange Bolting Penetration X-210B 288 TWMS Spool Bolting 4055-1 Penetration X-213A 289 TWMS Spool Bolting 4055-2 Penetration X-213A 290 TWMS Spool Bolting 4056-1 Penetration X-213B 291 TWMS Spool Bolting 4056-2 Penetration X-213B 292 Relief Valve Flange Bolting T4804F016A Penetration X-218 293 Relief Valve Flange Bolting T4804F016B Penetration X-218 294 Relief Valve Flange Bolting E1100F030D Penetration X-223A 295 Relief Valve Flange Bolting E1100F030B Penetration X-223B 296 Relief Valve Flange Bolting E1100F030C Penetration X-223C 297 Relief Valve Flange Bolting E110OF030A Penetration X-223D 298 Relief Valve Flange Bolting E2100FO11B Penetration X-227A 299 Relief Valve Flange Bolting E2100F012B Penetration X-227A 300 Relief Valve Flange Bolting E2100F032B Penetration X-227A 301 Relief Valve Flange Bolting E2100FO11A Penetration X-227B 302 Relief Valve Flange Bolting E2100F012A Penetration X-227B 303 Relief Valve Flange Bolting E2100F032A Penetration X-227B 304 Vacuum Breaker-Electrical Penetration Bolting X-228A 305 Vacuum Breaker-Electrical Penetration Bolting X-228B 306 Vacuum Breaker-Electrical Penetration Bolting X-228C 307 Vacuum Breaker-Electrical Penetration Bolting X-228D E8.20 308 Drywell Head Flange Bolting X-001A Cat.E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G Component Examination Schedule Period 1 Period 2 Period 3 Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 E8.10V-1 -VTC E8.10 VT-I 1 VTC E8.10 VT-I 1 VTC E8.10 VT-1 VTC E8.10 VT-i VTC E8.10 VT-i -VTC -E8.10 VT-1 -VTC -E8.10 VT-i --VTC E8.10 VT- --VTC -E8.10 VT-1 --VTC -E8.10 VT-1 -VTC --E8.10 VT-I --VTC E8.10 VT-i .- VTC E8.10 VT-1 -VTC E8.10 VT-1 VTC VTC E8.10 VT-1 VTC E8.10 VT-1 VTC VTC E8.10 VT-I 1 -VTC -E8.10 VT-I -1VTC -E8.10 VT-i -VTC -E8.10 VT-1 -VTC -ISI-NDE Program Rev.6; Change 0 Appendix F4.7 I Relief Request Remarks N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A E-G E8.20 Torque/Tension CISI-007 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 Page 18 of 23Monday, July 13, 2009 Component Examination Schedule I Period 1 I Period 2 1 Period 3 ISI-NDE Program Rev.6; Change 0 Appendix F4.7 I Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 Relief Request Remarks 309 South Equioment Hatch Bolting X-001B 310 North Equioment Hatch Bolting X-001C 311 Drywell Personnel Airlock Bolting X-001 D 312 Reactor Vessel Stablization Manhole Bolting X-001E 313 Reactor Vessel Stablization Manhole Bolting X-001F314 Reactor Vessel Stablization Manhole Bolting X-001G 315 Reactor Vessel Stablization Manhole Bolting X-001H 316 Reactor Vessel Stablization Manhole Bolting X-001J 317 Reactor Vessel Stablization Manhole Bolting X-001K 318 Reactor Vessel Stablization Manhole Bolting X-001 L 319 Reactor Vessel Stablization Manhole Bolting X-001M 320 CRD Hatch Bolting X-006 321 Penetration Flange Rupture Disk Bolting X-018 322 Penetration Flange Rupture Disk Bolting X-019 323 Spectacle Flange Bolting X-020 324 TIP Penetration Bolting X-035A 325 TIP Penetration Bolting X-035B 326 TIP Penetration Bolting X-035C 327 TIP Penetration Bolting X-035D 328 TIP Penetration Bolting X-035E 329 TIP Penetration Bolting X-035F 330 Penetration Flange Bolting X-039A 331 Penetration Flange Bolting X-039B Monday, July 13, 2009 E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI1-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40 Page 19 of 23 Component Examination Schedule I Period 11 Period 2 1 Period 3 ISI-NDE Program Rev.6; Change 0 Appendix F4.7 I Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 Relief Request Remarks 332 Electrical Penetration Bolting X-100A (X-100A)333 Electrical Penetration Bolting X-100B (X-102A) 334 Electrical Penetration Bolting (100C 335 Electrical Penetration Bolting (X-100E)336 Electrical Penetration Bolting X-10OF (X-103B)337 Electrical Penetration Bolting X-10OG (X-100G)338 Electrical Penetration Bolting X-101A (X-101A)339 Electrical Penetration Bolting X-101B (X-101B) 340 Electrical Penetration Bolting X-101C (X-1 01 C)341 Electrical Penetration Bolting X-101D (X-101D)342 Electrical Penetration Bolting X-101E (X-101E)343 Electrical Penetration Bolting X-101F (X-101F)344 Electrical Penetration Bolting X-102A (X-105B)345 Electrical Penetration Bolting X-102B (X-102B)346 Electrical Penetration Bolting X-102C (X-100B)347 Electrical Penetration Bolting X-102D (X-105C)348 Electrical Penetration Bolting X-103A (X-103A)349 Electrical Penetration Bolting X-103B (X-107B)350 Electrical Penetration Bolting X-104A (X-104A)351 Electrical Penetration Bolting X-104B (X-104B)352 Electrical Penetration Bolting X-104C (X-104C)353 Electrical Penetration Bolting X-104D (X-104D)354 Electrical Penetration Bolting X-104E (X-104E)Monday, July 13, 2009 E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40 Page 20 of 23 Component Examination Schedule j Period 11 Period 2 1 Period 3 ISI-NDE Program Rev.6; Change 0 Appendix F4.7 I Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RFll RF12 Relief Request Remarks 355 Electrical Penetration Bolting X-104F (X-104F)356 Electrical Penetration Bolting X-105A (X-1 05A)357 Electrical Penetration Bolting X-105D (X-105D)358 Electrical Penetration Bolting X-106A (X-100D)359 Electrical Penetration Bolting X-106B (X-106B)360 South Torus Hatch Bolting Penetration X-200A 361 NorthTorus Hatch Bolting Penetration X-200B 362 Butterfly Valve Flange Bolting Penet. X-205C 363 Butterfly Valve Flange Bolting Penet. X-205D 364 Electrical Penetration Bolting X-209A 365 Electrical Penetration Bolting X-209C 366 RHR Test Line Orifice D008B Bolting Penetration X-210A 367 RHR Test Line Orifice D009B Bolting Penetration X-210A 368 Relief Valve Flange Bolting E1100F001B Penetration X-210A 369 Relief Valve Flange Bolting E1100F025B Penetration X-210A 370 RHR Blind Flange Bolting Penetration X-210A371 RHR Test Line Orifice D008A Bolting Penetration X-210B 372 RHR Test Line Orifice D009A Bolting Penetration X-210B 373 Relief Valve Flange Bolting E1100FOOlA Penetration X-210B 374 Relief Valve Flange Bolting E1100F025A Penetration X-210B 375 Relief Valve Flange Bolting E1100F029 Penetration X-210B 376 RHR Blind Flange Bolting Penetration X-21 GB 377 TWMS Spool Bolting 4055-1 Penetration X-213AMonday, July 13, 2009 E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8&20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CLSI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007 CISI-007To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested.Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance With E8.10 and Tested Per E9.40 Page 21 of 23 Component Examination Schedule I Period 11 Period 2 1 Period 3 ISI-NDE Program Rev.6; Change 0 Appendix F4.7 I Item Exam Area Identification Cat. Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 Relief Request Remarks 378 TWMS Spool Bolting 4055-2 Penetration X-213A 379 TWMS Spool Bolting 4056-1 Penetration X-213B 380 TWMS Spool Bolting 4056-2 Penetration X-213B 381 Relief Valve Flange Bolting T4804F016A Penetration X-218 382 Relief Valve Flange Bolting T4804F016B Penetration X-218383 Relief Valve Flange Bolting E11 00F030D Penetration X-223A384 Relief Valve Flange Bolting E1100F030B Penetration X-223B385 Relief Valve Flange Bolting E1100F030C Penetration X-223C 386 Relief Valve Flange Bolting E1100F030A Penetration X-223D 387 Relief Valve Flange Bolting E2100FO11B Penetration X-227A 388 Relief Valve Flange Bolting E2100F012B Penetration X-227A 389 Relief Valve Flange Bolting E2100F032B Penetration X-227A 390 Relief Valve Flange Bolting E2100FO11A Penetration X-227B 391 Relief Valve Flange Bolting E2100F012A Penetration X-227B 392 Relief Valve Flange Bolting E2100F032A Penetration X-227B 393 Vacuum Breaker-Electrical Penetration Bolting X-228A 394 Vacuum Breaker-Electrical Penetration Bolting X-228B 395 Vacuum Breaker-Electrical Penetration Bolting X-228C 396 Vacuum Breaker-Electrical Penetration Bolting X-228D E9.10 397 Pressure Retaining Boundary E9.20 398 Containment Penetration Bellows E9.30 399 AirlockMonday, July 13, 2009 E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E-G E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/TensionE8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/TensionE8.20 Torque/Tension E8.20 Torque/Tension E8.20 Torque/TensionE8.20 Torque/TensionE8.20 Torque/Tension

--- -- CISI-007--- -- CISI-007--- -- CISI-007--- -- CISI-007--CISI-007---- -CISI-007---- -CISI-007---- -CISI-007--CISI-007---- -CISI-007---- -CISI-007---- -CISI-007--CISI-007---- -CISI-007---- -CISI-007---- -CISI-007--CISI-007---- -CISI-007---- -CISI-007To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance With E8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 To Be Inspected In Accordance WithE8.10 and Tested Per E9.40 E-P E9.10 VT-2 E-P E9.20 App. J E-P E9.30 App. J After repair, modification or replacement.

10CFR50.AppendixJ 10CFR50.AppendixJ Page 22 of 23 Component Examination Schedule Period 11 Period 2 1 Period 3 Cat. Code NDE Method RF07 RF08 RF09 RF10 RF11 RF12 Relief Request RemarksISI-NDE Program Rev.6; Change 0 Appendix F4.7 Item Exam Area Identification E9.40 400 Seals and Gaskets E-P E9.40 App. J 10CFR50.AppendixJ GS = General Inspection Scheduled GC = General Inspection Complete VTS = VT Inspection Scheduled VTC = VT Inspection Complete VTPC = VT Inspection Partical Complete Monday, July 13, 2009 Page 23 of 23 LA' I 99Igt' IN 'lpod-aA.

S-H a~x~a K OOt' 'juvidiJamod vaP'nK Z lwiag~XH9CZNU INno 'Z!OJP lmalZIwId ,dmva Ix "OJUOSp3IO$s 6 NIOIJ3:S 9.0 NIS-2 DATA REPORT INDEX LOG No.07-005 08-002 08-003 08-004 08-006 08-007 08-008 08-009 WORK PKG.No.25549789 1131070100 1129040100 VARIOUS VARIOUS 25998832 25975196 26004968 VARIOUS 25975209 25996656 VARIOUS COMPONENT No.Cl 102DXXX R3001C007 R3001Co05 C1 102DXXX B2103F013@

B2103F013@

VARIOUS VARIOUS C LSME DESCRIPTION LASS 1 Rebuild (15) CRDM's for installation in RF13 3 Install Replacement Pump DGSW #13 3 Install Replacement Pump DGSW #11 1 Replace CRDM's during RF13 1 Replace Main Steam Safety Relief Valves during RF 13 1 Refurbish Main Steam Safety ReliefValve Main Bodies and Pilot Assemblies for installation in RF 13 N/A Refurbish Mechanical Snubbers for installation in RF 13 N/A Refurbish Hydraulic Snubbers for installation in RF 13Replace Stem/Disc assembly N/A Replace Hydraulic Snubber 3 Modify NIAS Piping (Division 1)3 Modify NIAS Piping (Division 2), 3 Install replacement bolting material on Pump DGSW #11 3 Install replacement check valve 1 Perform base metal repair of heat exchanger channel due to pitting 2 Replace leaking valves on ResidualHeat Removal System 2/3 Replace Heat Exchanger Service Water side flange bolting 1 Install Replacement Bolting 08-011 28982441 08-012A 28171173 28171257 08-012B 28171199 28171267 08-013 1129040100 08-014 E5689703 09-001 29188651 09-003 25984079 09-004 B134060100 09-005 B203090100 E21-3147-G27 P5000F440 P5000F441 R3001Co05 R3000F015A R3001B027 El100F071B E1100F072B E1101BO01A B210OF010A Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)148 LOG No. WORK PKG.No.COMPONENT No. ASME CLASS DESCRIPTION 09-006 09-007 09-008 09-009 09-010 09-011 09-012 09-013 09-014 09-016 26320349 T250090100 G428090100 25980121 G428090100 29205488 29649872 25981894 25981870 291010808 B2103F022B B2100F032B C4100F007 E4101CO01 C4100F007 El100FO12B P4400F972A C4100F029A C4100F029B R3001B025 1 Replace valve cover bolting and replace in-body seat ring by welding and machining 1 Replace Stuffing Box 1 Replace Check Valve Bolting None Replace Turbine Casing Bolting 1 Replace Check Valve Disc 3 Replace Valve Bonnet Bolting 3 Replace Check Valve 3 Prep and install Replacement Relief Valve 3 Prep and install Replacement Relief Valve N/A Perform base metal repair of channel heads due to internal pitting Detroit Edison Co., One Energy Plaza, Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NB No. 21085 (RPV)149 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 07-005 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Date Sheet Unit May 20, 2009 1 of 6 Address 2. Plant Fermi 2 Nuclear Power Plant Name 6400 North Dixie Highway, Newport Ml 48166 Address 2 Deco Maintenance

3. Work Performed by Detroit Edison Company Name Type Code Sy Stamp Authorization Expiration Dat No.e Repair Organization P.O. No., Job No., etc.mbol N/A N/A N/A 6400 North Dixie Highway, Newport, MI 48166 Address 4. Identification of System (N5-J120-N5-1)

Control Dod Drive System

5. (a) Applicable Construction Code ASME Ill, Winter Class 1 19 71 Edition 1971 Addenda, (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or 1992- W" 92 Replacements Addenda 6. Identification of Components Repaired or Replaced and Replacement Components N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)Control Rod Drive General Various N/A C1102D@ Various Replacement Yes Mechanisms Electric Description

7. of Work Refurbish Control Rod Drive Mechanisms for installation in RF13.8. Tests Conducted:

Hydrostatic

[I Pneumatic

[ Nominal Operating Pressure [ X ]Other [X ] Pressure _ psi Test Temp._VT-2 After Installation OF Seal Leak Test Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets isrecorded at the top of this form.(10194)

Form NIS-2 (Back)9. Remarks Refurbished Control Rod Drive Mechanisms for Installation in RF-13. Copies of available Code Data Reports are attached.

Replacement Piston Tubes were procured per Purchase Orders #4700204568 and 423758 and data reports are attached.

Cylinder Tube and Flange Assemblieswere procured per PO #266433 with no data reports.Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of theASME Code, Section Xl.Type Code Symbol Stamp Original Code Data Reports for each Control Rod Drive will be supplemented by OwnersSection XI Program Plan # 07-005 and work order # 25549789 as listed on attached Sheet 2. For tracking purposes CRDM information will be maintained in N5-J120-N5-1.

Certificate of Authorization No.N/Aq, I Expiration Date.N/A Signed R.M. Hambleton Lead ISI Engineer INNýD1ate Owner or Owner's Designee, Title NUM W 2009 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid.commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected thecomponents described in this Owner's Report during the period9- 2-1--to 6 -Z.3- 0 :, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

A Commissions Inspector's Signature National Board, State, Province, and Endorsements Date , Z J, 2009 (10/94)Far additional detail see work order # 25549789.

Serial No. Rebuild WR (1) Cylinder Tube/ Piston Tube Other ASME Parts Flange (480-8571) 3176 25549789 None 3998 25549789 None 4575 25549789 None 4282 25549789 None 5349 25549789 None 3321 25549789 None 4525 25549789 None 6523 25549789 5458 1167 None-3156 25549789 6415 1162 None 3962 25549789 6494 None 4541 25549789 6379 None 4331 25549789 6233 1151 None 4209 25549789 5467 1157 None 4595 25549789 6320 None 6369 25549789 6013 None 3349 25549789 None 1) Replacement Cylinder Tube/Flange assemblies were utilized from Shoreham Nuclear Station Control Rod Drive Mechanisms that were procured per P.O. 266443. Product Quality Certifications were supplied with the parts, however, manufacturers data reports were not supplied with these items. The CRDM's obtained were disassembled and inspected.and the usable parts were put into the Fermi stock system.

0'7--00 FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES*

As required by the Provision of the ASME Code Rules,Section III, Division I 1. Manufactured and certified by GE Hitachi Nuclear Energy 3901 Castle Hayne Road, Wilmington, North Carolina 28401 (Name and address of NPT Certificate Holder)(b) Manufactured for FERMI 2 6 2. Identification

-Certificate Holder's S/N of Part (a) Constructed According to Drawing No.(b) Description of Part Inspected 400,N. DIXIE HWY.NEWPORT, MI 48166 (Name and address of N Certificate Holder for completed nuclear component)'

1151 798D228G012, Rev. 39 PISTON TUBE ASSEMBL Nat'l Bd. No. N/A Drawing Prepared by P. PANSOY.Y te W' 75 , Case No. 1361-2 , Class I (c) A pplicable ASME Code:

Section III, Edition 1974 , Addenda Da 3. Remarks: STANDARD PART FOR USE WITH REACTOR.

HYDROSTATICALLY TESTED AT 1820 PSI. MIN.(Brief description of service for which component was designed)* We certify that the statements in this report are correct and this vessel part or appurtenance as defined in the code conforms to the rules of construction of the ASME Code Section 11. (The applicable Designed Specification and Stress Report are not the responsibility of the NPT Certificate Holder for parts. An NPT Certification Holder for appurtenances is responsible for furnishing a separate Design Specification and Stress Report if the appurtenances is not included in the component Design Specification and Stress Report).Date Certificate of Authorization Expires Signed GEH 'By (NPT Certificate Holder) (SCQ Representative)

, NPT N-1151//.06/16/2011 Certificate of Authorization No.CERTIFICATION OF DESIGN FOR APPURTENANCE Design information on file at GE COMPANY, SAN JOSE, CALIFORNIA Stress analysis report on file at GE COMPANY, SAN JOSE, CALIFORNIA DC22A6253, Rev. 02 Design specification certified by B.N. SRIDHAR Prof. Eng. State CALIF. Reg. No. 18345 DC22A6254, Rev. 01 Stress analysis report certified by E.Y. GIBO Prof Eng. State CALIF. Reg. No. M18646 CERTIFICATION OF SHOP INSPECTION 1, the undersigned, holding a valid commission by the National Board of Boiler and Pressure Inspectors and/or the State or Province of North Carolina and employed by Department of Labor of State of North Carolina have inspected the part of a pressure vessel described in this Partial Data Report. on 9Z29_ /-and state that to the best of my knowledge and belief, the NPT Certificate Holder has constructed this part in accordance with the ASME Code Section III.By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the part described in the Partial Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damages or a loss of any kind arising from or connected with this inspection.

!~ __ýDatd/11Z Inspector's Signature NB8214 IBNA National Board, State, Province and No.*Supplemental sheets in form of lists, sketches or drawing may be used provided (1) size is 8 Y2 "x 11", (2) information in 1-2 on the Data Report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded in item 3 "Remarks".

o1-oxLk cr- a FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES*

As required by the Provision of the ASME Code Rules,Section III, Division I 1. Manufactured and certified by General Electric Company Nuclear Energy (GE-NE)3901 Castle Hayne Road, Wilmington, North Carolina 28401 (Name and address of NPT Certificate Holder)(b) Manufactured for FERMI 2 6400 N. DIXIE HWY. NEWPORT, MI 48166 (Name and address of N Certificate Holder for completed nuclear component)

2. Identification

-Certificate Holder's S/N of Part 1157 (a) Constructed According to Drawing No. 798D228G012, Rev. 39 Nat'l Bd. No. N/A Drawing Prepared by P. PANSOY (b) Description of Part Inspected PISTON TUBE ASSEMBLY (c) Applicable ASME Code:

Section III, Edition 1974 .Addenda Date W' 75 Case No.

1361-2 Class I 3. Remarks: STANDARD PART FOR USE WITH REACTOR. HYDROSTATICALLY TESTED AT 1820 PSL MNN.(Brief description of service for which component was designed)We certify that the statements in this report are correct and this vessel part or appurtenance as defined in the code conforms to the rules of construction of the ASME Code Section III. (The applicable Designed Specification and Stress Report are not the responsibility of the NPT Certificate Holder for parts. An NPT Certification Holder for appurtenances is responsible for furnishing a separate Design Specification and Stress Report if the appurtenances is not included in the component Design Specification and Stress Report).Date 02/15/07 Certificate of Authorization Expires Signed GE-NE (NPT Certificate Holder)By (SCQ RepWesentative) 06/16/2008 Certificate of Authorization No. NPT N-1151 CERTIFICATION OF DESIGN FOR APPURTENANCEDesign information on file at GE COMPANY, SAN JOSE, CALIFORNIA Stress analysis report on file at. GE COMPANY, SAN JOSE, CALIFORNIA DC22A6253, Rev. 02 Design specification certified by B.N. SRIDHAR Prof. Eng. State CALIF. Reg. No. 18345 DC22A6254, Rev. 01 Stress analysis report certified by E.Y. GIBO Prof. Eng. State CALIF. Reg. No. M18646 CERTIFICATION OF SHOP INSPECTION 1, the undersigned.

holding a valid commission by the National Board of Boiler and Pressure Inspectors and/or the State or Province of North Carolina and oyed by Department of Labor of State of North Carolina have inspected the part of a pressure vessel described in this Partial Data Report on)2/V ~d: and state that to the best of my knowledge and belief, the NPT Certificate Holder has constructed this part in accordance with the AiSME Code Section III.By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the part described in the Partial Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damages or a loss of any kind arising from or connected with this inspection.

-\,/ 5-~'DW6 NB8214 INBA NC1231 rýInspp orcs Sign-atre National Board. State, Province and No.*Supplemental sheets in form of lists, sketches or drawing may be used provided (1) size is 8 V2 " x !1". .(2) information in 1-2 on the Data Report is-included on each sheet, and (3) each sheet is numbered and number of sheets is recorded in item 3 "Remarks".

FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES*

As required by the Provision of the ASME Code Rules,Section III, Division I I. Manufactured and certified by GE Hitachi Nuclear Energy 3901 Castle Havne Road, Wilmington, North Carolina 28401 (Name and address of NPT Certificate Holder)(b) Manufactured for FERMI 2 6 2. Identification

-Certificate Holder's S/N of Part (a) Constructed According to Drawing No.400 N. DIXIE HWY.NEWPORT, MI 48166 (Name and address of N Certificate Holder for completed nuclear component) 1162 /798D228G012, Rev. 39 Nat'l Bd. No. N/A Drawing Prepared by P. PANSOY (b) Description of Part Inspected PISTON TUBE ASSEMBLY I (c) Applicable ASME Code: Section III, Edition 1974 , Addenda Date W' 75 I Case No. 1361-2 , Class 1 3. Remarks: STANDARD PART FOR USE WITH REACTOR. HYDROSTATICALLY TESTED AT 1820 PSI. MIN.(Brief description of service for which component was designed)-

We certify that the statements in this report are correct and this vessel part or appurtenance as defined in the code conforms to the rules of construction of the ASME Code Section III. (Theapplicable Designed Specification and Stress Report are not the responsibility of the NPT Certificate Holder for..parts. An NPT Certification Holder for appurtenances is responsible for furnishing a separate Design Specification and Stress Report jfthe,--..

appurtenances is not included in the component Design Specification and Stress Report).Date Signed GEH By Y4. ,'(NPT Certificate Holder) 6SC Reresentative)

-1 CertifLicated of Athuorization Expires UO/1o/IJ/l I C..ertilicate OI Authorizanon No.INP IN-1I 15 1 CERTIFICATION OF DESIGN FOR APPURTENANCE Design information on file at GE COMPANY, SAN JOSE, CALIFORNIA Stress analysis report on file at GE COMPANY, SAN JOSE, CALIFORNIA DC22A6253, Rev. 02 Design specification certified by B.N. SRIDHAR Prof. Eng. State CALIF. Reg. No. 18345 DC22A6254, Rev. 01 Stress analysis report certified by E.Y. GIBO Prof. Eng. State CALIF. Reg. No. M18646 CERTIFICATION OF SHOP INSPECTION I, the undersigned, holding a valid commission.by the National Board of Boiler and Pressure Inspectors and/or the State or Province of North Carolina and emp loyed by Department of Labor of State of North Carolina have inspected the part of a pressure vessel described in this Partial Data Report on-'I _, _ ' and state that to the best of my knowledge and belief, the NPT Certificate Holder has constructed this part in accordance with the KSME Code Section III.By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the part described in the Partial Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damages or a.loss of any kind arising from or connected with this inspection.

Date *NB8214 IBNA Inspector's Signature National Board, State, Province and No.*Supplemental sheets in form of lists, sketches or drawing may be used provided (1) size is 8 Y2 " x 11", (2) information in 1-2 on the Data Report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded in item 3 "Remarks".

FORM N-2 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PART AND APPURTENANCES*

As required by the Provision of the ASME Code Rules,Section III, Division I 1. Manufactured and certified by GE Hitachi Nuclear Energy 3901 Castle Hayne Road, Wilmington, North Carolina 28401 (Name and address of NPT Certificate Holder)(b) Manufactured for FERMI 2 6 2. Identification

-Certificate Holder's S/N of Part 400 N. DIXIE HWY.NEWPORT, MI 48166 (Name and address of N Certificate Holder for completed nuclear component) 1167 Nat'l Bd. No. N/A (a) Constructed According to Drawing No.(b) Description of Part Inspected 798D228G012, Rev. 39 Drawing Prepared by P. PANSOY PISTON TUBE ASSEMBLY (c) Applicable ASME Code: Section III, Edition , 1974 , Addenda Date W' 75 , Case No. 1361-2 , Class I.3. Remarks: STANDARD PART FOR USE WITH REACTOR. HYDROSTATICALLY TESTED AT 1820 PSI. MIN.(Brief description of service for which componentviwas designed)We certify that the statements in this report are correct and this vessel part or appurtenance as defined in the code conforms to the rules of construction of the ASME Code Section I1l. (The applicable Designed Specification and Stress Report are not the responsibility of the NPT Certificate Holder for parts. An NPT Certification Holder for appurtenances is responsible for furnishing a separate Design Specification and Stress Reppirtt-

.appurtenances is not included in the component Design Specification and Stress Report). .

" "--Date Certificate of Authorization Expires By Signed GEH (NPT Certificate Holder),, (SCQ Representative) 06/16/2011 Certificate of Authorization No.

NPT N-1151 CERTIFICATION OF DESIGN FOR APPURTENANCE Design information on file at GE COMPANY, SAN JOSE, CALIFORNIA Stress analysis report on file at GE COMPANY, SAN JOSE, CALIFORNIA DC22A6253, Rev. 02 Design specification certified by B.N. SRIDHAR Prof. Eng. State CALIF. Reg. No. 18345 DC22A6254, Rev. 01 Stress analysis report certified by E.Y. GIBO Prof. Eng. State CALIF. Reg. No. M18646 CERTIFICATION OF SHOP INSPECTION I, the undersigned, holding a valid commission by the National Board of Boiler and Pressure Inspectors and/or the State or Province of North Carolina and er. loyed by Department of Labor of State of North Carolina have inspected the part of a pressure vessel described in this Partial Data Report on/A21, AQ9; and state that to the best of my knowledge and belief, the NPT Certificate Holder has constructed this part in accordance with the ASME Code Section III.By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the part described in the Partial Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damages or a loss of any kind arising from or connected with this inspection.

Date&eA.Jtl NB8214 IBNA 67 Inspector's Signature National Board, State, Province and No.*Supplemental sheets in form of lists, sketches or drawing may be used provided (1) size is 8 'A" x I1", (2) information in 1-2 on the Data Report is included on each sheet, and (3) each sheet is numbered and number of sheets is recorded in item 3 "Remarks".

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 08-002 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Address 2. Plant Fermi 2 Nuclear Power Plant Date Sheet Unit January 15, 2009 1lof 2 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance Repair Organization P.O. No., Job No., etc.3. Work Performed by Address Detroit Edison CompanyType Code Symbol.Stamp Authorization No.Expiration.Date N/A Name 6400 North Dixie Highway, Newport, MI 48166 Address N/A N/A 4. Identification of SystemT & B N5 -.20 (Emergency Diesel Generator (EDG) Number #13 Service Water Pump)

5. (a) Applicable Construction Code ASME Ill, Class 3 19 71 Edition (b) Applicable Edition/Addenda of Section Xl Utilized for Repairs or Replacements 19 6. Identification of Components Repaired or Replaced and Replacement Components "71 Addenda 92-92 Addenda N/A Code Case Name of Name of Manufacturer Serial National Other Year.

Repaired, ASME Component Manufacturer No .Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)R3001C007 Goulds Pumps TCN N0007-3 N/A N/A 1977 Replaced Y R3001C007 Enertech 11575 N/A N/A 2008 Replacement Y Description

7. of Work Installed Replacement Pump and bolting material.8. Tests Conducted:

Hydrostatic

[I Other [ I Pressure Pneumatic

[] Nominal Operating Pressure [ X ]e psi Test Temp.Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each'sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)9. Remarks: Replacement Pump procured per Purchase order # 4700013487.

Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules ofthe ASME Code,Section XI.Type Code Symbol Stamp Original Code data report T&B N5-20 to be supplemented by OwnersSection XI Program 08-002.Certificate of Authorization No. N/A Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer .Date I .20 Owner or Owner's Designee, Title " CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected thecomponents described in this Owner's Report during the period ."-,- ,ao /Z-125--09

' and state that to the best of myknowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

/_____________________J---

Commissions A.-. Q .' -4,__*Inspector's Signature National Board, State, Province, and Endorsements Date ./-i/?.-<

/" 5 20 C/((10/94)For complete work package, see Work Order # 1131070100.

FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES*As Required by the Provisions of the ASME Code, Section iII, Division 1 Pg. l of 1. Manufactured and certified by Enertech, Div.. of Curtiss-Wright Flow Control Corp. ; 2950 Birch St.; Brea, CA 92821(name and address of N Certificate Holder)2. Manufactured for Detroit Edison; 2000 2nd Avenue; Detroit, Ml 48226-1279(name and address of Purchaser)

3. Location of installation Detroit Edison; Fermi EF2; 6400 Dixie Hwy.; Newport, M[48166 (name and address)VlT8'x2" MC ra MD21 144 J 1A____4. Model No., Series No., or Type VIT-8"X12" JMC Drawing Rev. _ CRN N/A S. ASME Code,Section III, Division 1: 1974 No 3 none (edition) (addenda date) (class) (Code Case no.)*6. Pump or valve Pump Nominal inlet size 12 Outiet size 8.in.) N (lin.)7. Material:

Body Bonnet NADisk ..A Bolting N/(a)Cert.'Holder's Serial No.11575 (b)Nat'l Board No.N/A (c)Body Serial No..**, , (d)Bonnet...Serial No.N/A le)Disk Serial No.N/A Supplemental information in form of lists, sketches, or drawings may be used provided (1) size is 8 Yz x 11, (2) Information in items 1 through 4 on this Data Report is inciuded on each sheet. (3) each sheetis numbered and the number of sheets is recorded at the top of this form.(12/88) This form (E00037) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300.

REPRINT 6/93 fI (. : r ,. ". / '

-' '

FORM NPV-1 (Back Pg. 2 of 2 Certificate Holder's Serial No. 11575 8. Design conditions 75 -psi ._ 100 '....OF or valve pressure class N/A Jpressure) (temperature)

9. Cold working pressure N/A psi at IO0pF 10. Hydrostatic test 125 psi. Disk differential test pressure N/Apsi 11. Remarks: Qty. 1, Enertech Project Number 840110 (Serial No. 1.1575)Stuffing Box: (S/N 24145) SA479 Tp. 410 Top Bowl, Interm. Bowl: (S/N 23615, 23613) SA216 Gr. WCB Top Column (S/N 23311, 23338), Interm. Column (S/N 23314, 23341,23342, 23343, 23346), Bott. Column (S/N 23316) SAI06 Gr. B/SA516 Gr. 70.CERTIFICATION OF DESIGN Design Specification certified by Michael S. Williams P.E. State Ml Reg. no 3.1168.6 Design Report certified by N/A PýE. State N/A Reg. no. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code,Section III, Division 1.

N Certificate of Authorization No N-2826 Fxires 10/11/08 Enertech Date 5Name Signed. zdepeetaie IN Certificate Holder) Snuthorizedrepresentatve)

CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of California and employed by HSEB, CT of /_ _ Connecticut have inspected the pump, or valve, described in this Data Report on , and state that to the best of my knowledge and'belief, the' Certificate Holder has con-structed this pump, or valve, in accordance with the ASME Code, Section IlI, Division 1.By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component described in this Data Report. or , neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage o a s o ny kind arising from or connected with this inspection.

De LS-ged. [Nat'). Bd. finc-. endorsements) and state or prv. and no.](1) For manually operated valves only.

' 08 003 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI I i i 08-013 1. 'Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Address 2. Plant Fermi 2 Nuclear Power Plant Date Sheet Unit January 7, 2009 I of, 2 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance Address Detroit Edison Company Repair Organization P.O. No., Job No., etc.3. Work Performed by Name 6400 North Dixie Highway, Newport, MI 48166 Type Code Symbol Stamp Authorization No.Expiration Date N/A N/A N/A AddressT & B N5 -5 (Emergency Diesel Generator (EDG) Number #11 Service Water Pump)4. Identification of System 5. (a) Applicable Construction Code ASME III, Class 3 19 71 Edition (b) Applicable Edition/Addenda of Section Xl Utilized for Repairs or Replacements 19 6. Identification of Components Repaired or Replaced and Replacemeht Components 71 Addenda 92-92,Addenda N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No, ' or Replacement Stamped (Yes or No)R3001C005 Goulds Pumps TCN N0007-1 N/A N/A 1977 Replaced Y R3001C005 Enertech 11574 N/A .N/A 2008. Replacement Y Description

7. of Work Installed Replacement Pump and bolting material, including stuffing box holddown bolts..8. Tests Conducted:

Hydrostatic

[ ]Other [ ) Pressur Pneumatic

[I Nominal Operating Pressure [ X ]e psi Test Temp. _ OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)9. Remarks: Replacement Pump procured per Purchase order # 4700013.487 and 4700130672 and replacement stuffing box bolts procured per Purchase Order #362535,Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code,Section XI.Type Code Symbol Stamp Original Code data report T&B N5-5 to be supplemented by OwnersSection XI Program 08-003 and 08-013.Certificate of Authorization No. N/A Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer Date 2V "" , Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I,.the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period .,'7,/0' to /'/2. 5 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correcti e measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section X1.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners.Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

__,____ '________

"______-____-

_______ Commissions

,-'.. /Inspector's Signature National Board, State, Province, and Endorsements Date ,//,&-.,,/

Z 20 0 (10194)For complete work package, see Work Order# 1129040100.

FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES*As Required by the Provisions of the ASME Code, Section 111, Division 1 Pg. 1 of 2 1. Manufactured and certified by Enertech, A Div. of Curtiss-Wright Flow Control Corp.; 2950 Birch St.; Brea, CA 92821 (name and address of N Certificate Holder)2. Manufactured for Detroit Edison; 2000 2nd Avenue; Detroit, MI 48226-1279 (name and address of Purchaser)

3. Location of installation Detroit Edison; Fermi EF2; 6400 Dixie Hwy.; Newport, MI 48166 (name and address)4. Model No., Series No.,or Type VIT 8"X12" JMC Drawing MD21144 Rev. _ CRN N/A 5. ASME Code,Section III, Division 1: 1974 No' 3 none (edition) (addenda date) (class) (Code Case no.)6. Pump or valve Pump Nominal inlet size 12 Outlet size 8 (in.) (in.)7. Material:

Body Bonnet N/A Disk N/A Bolting N/A (a)Cert.Holder's Serial No.11574 Ib)Nat'l Board No.N/A (c)Body Serial No.(dl Bonnet Serial No.N/A (e)Disk Serial No.N/A*Supplemental information in form of lists, sketches, or drawings may be used provided (1) size is 8'A x 11, (2) information in items 1 through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets Is recorded at the top of this form.(12/88) This form (E00037) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300.

REPRINT 6/93-I.

FORM NPV-1 (Back -Pg. 2 of 2 Certificate Holder's Serial No. 115748. Design conditions psi 100 0 F or valve pressure class N/A (1)(pressure) (temperature)

9. Cold working pressure N/A psi at 1000 F 10. Hydrostatic test 125 psi. Disk differential test pressure N/A psi 11. Remarks: Qty. 1, Enertech Project Number 840110 (Serial No. 11574)Stuffing Box: (SIN 24144) SA479 Tp. 410 Top Bowl, Interm. Bowl: (S/N 23614, 23612) SA216 Gr. WCB Top Column Assy (S/N 23312, 23337), Interm. Column (S/N 23313, 23339, 23340, 23344, 23345),Bott.

Column Assy (S/N 23315), SA1 06 Gr., B / SA516 Gr. 70 CERTIFICATION

ýOF DESIGN Design Specification certified by Michael S. Williams P.E. State Ml Reg. no. 31686 Design Report certified by N/A P.E. State N/A Reg. no. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code,Section III, Division 1.N Certificate of Authorization No. N-2826 Expires 10/11/08 Enertech, A Div. of Curtiss-Wright Flow Date -Name Control Corp. Signed (N Certificate Holder) (authorized representativeY CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of California

.and employed by HSB, CT of Connecticut have inspected the pump, or valve, described in this Data Report on-/ 1* 1/0 -, and state that to the best of my knowledge and belief, the Certificate Holder has con-structed this pump, or valve, in accordance with the ASME Codeý,Section III,.Division 1.By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component described in this Data Report.

Furthernr , ,ther the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a lo i arising from or connected with this inspection..Date Signed ./ Commissions

(.A Z I (Authorized [Nat'. Bd. (incl. endorsements) and state or prov. end no.)(1,LF-61 ma'tl¥ operated valves only.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 08-004 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Date Sheet Unit May 14, 2009 1 of 2 Address 2. Plant Fermi 2 Nuclear Power Plant 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance

3. Work Performed by AddressDetroit Edison Company Repa Type Code Symbol Stamp Authorization No.Expiration Date ir Organization P.O. No., Job No., etc.N/A Name 6400 North Dixie Highway, Newport, MI 48166 Address N/A N/A 4. Identification of System (N5-J120-N5-1)

Control Rod Drive System 5. (a) Applicable Construction Code ASME Ill, Class 1 19 71 .Edition (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or Replacements 19 6. Identification of Components Repaired or Replaced and Replacement Components W'71 Addenda 92-92 Addenda N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)CRD Housing Bolting RCI N5-J120-N5-1 N/A See Matrix 1975 Replacement NControl Rod Drive General See Matrix N/A See Matrix 1975 Replacement Y Mechanisms Electric Description

7. of Work Replaced Control Rod Drive Mechanisms at various locations and installed replacement Cap Screws on each mechanism to facilitate drive installation durinq RF13. All removed boltinq will be inspected and stored forfuture installation.

8. Tests Conducted:

Hydrostatic

[]Other[X] Pressure Pneumatic

[] Nominal Operating Pressure [ X ]e_ psiTest Temp.

_F Performed VT-1 of Bolts Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)9.Replacement bolting was bolting that was procured per PO# 389120 and #4700038655. Cap Screws are ASME I1l, Class 1, 1"- 8 UNC2A x 5.5", SA193 Grade B7, and all were VT-1 inspected prior to installation.

Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report-are correct and this Replacement conforms to the rules of the ASME Code, Section X1.Type Code Symbol Stamp Original Code data report N5-J120-,N5-1 to be supplemented by OwnersSection XI Program 08-004 Certificate of Authorization No. N/A_ Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer A0/. -Date MA&.A ,2009 Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected thecomponents described in this Owner's Report during the period.1-)/ t'-o -to8 -

/ 8 -a , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_Commissions-Inspector's Signature National Board, State, Province, and Endorsements Date 1 i,,y , 2000 (10/94)For complete work packages, see Work Requests listed on attached matrix.

NIS-2 08-004 Sheet 2 of 2 Nis-2 Attsachment for Section XI Pro2ram No.08-004 -RF13 CRDM Exchange Replacement bolting (Cap Screws) were installed on each drive mechanism installed (8 per drive).Bolting material utilized was all brand new material procured per PO# 389120 and

4700038665.

New CRDM Serial numbers are based on the locations requested prior to the outage and were verified during installation.

Replacement CRDM's were previously refurbished per Section XI Program 07-011.CRDM PIS No. Old Serial New Serial Exchange WR Flange Cap No. No. Screws PO#_/Heat Code#22-59 C1102D007 4574 4282 26959931 (3) #389120 -#H947 (5) #4700038665

0W67 02-39 C1102D052 4542 5467 26959589 #389120 -#H947 18-43 C1102D037 5673 3998 26959811 #389120 -#H947 26-03 C1102D022 4551 4575 26959950 #389120 -#H947 06-15 C1102D019 4528 3321 26959703 #389120 -#H947 50-27 C1102D100 4548 6233 26960375 #389120 -#H947 10-23 C1102D063 4476 6494 26959707 #389120 -#H947 38-55 C1102Dl13 4155 3349 26960256 #389120 -#H947 54-47 C1102D103 4165 6415 26960388 #389120

-#H947 30-35 C1102D154 3516 3176 26960131 #4700038665

0W67 46-31 C1102D165 4164 6379 26960346 #4700038665

0W6742-19 C1102D145 4342 6320 26960318 #4700038665

0W67 46-43 C1102D157 4518 6013 26960170 #4700038665

0W6746-15 C1102D181 4546 4525 26960333 #4700038665

0W67 58-31 C1102D168 4303 5458 26960407 #4700038665

0W67 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI 08-006 1.. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Address 2. Plant Fermi 2.Nuclear Power Plant Date Sheet Unit May 7, 2009 1 of 2 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance

3. Work Performed by Address Detroit Edison Company Name Repair Organization P.O. No., Job No., etc.Type Code Symbol Stamp Authorization No.Expiration Date N/A N/A 6400 North Dixie Highway, Newport, MI 48166 N/A 4. Identification of System Address B21 Nuclear Boiler, Main Steam Safety Relief Valve Pilot and Base Assemblies

-Various N-5 Reports 5. (a) Applicable Construction Code ASME Ill, Class 1 19 71 Edition W'71 Addenda (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or Replacements 1992-92 Addenda 6. Identification of Components Repaired or Replaced and Replacement Components None Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)SRV Pilot Assemblies-Target Rock Various (See N/A B2103F013-N/A Replacement Y attached listing) A thru R SRV Main Body Target Rock Various (See N/A B2103F013-N/A Replacement Y Assemblies attached listing) A thru R Description

7. of Work Durina RF13 reolace all 15 SRV Pilot valve Assemblies as well as the Main Bodies for SRV's B2103F013G.

H and P.8. Tests Conducted:

Hydrostatic

[ ]Pneumatic [ ] Nominal Operating Pressure [ X I Other [X] Pressure, psi Test Temp._ OF Operability test per 24.137.11 Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items I through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10194)

Form NIS-2 (Back)

9. Remarks All 15 SRV Pilots, and 4 Main Bodies were replaced using Work Requests listed on attached sheet.

See attached listing for SRV exchange matrix. SRV Pilots and Main Bodies were refurbished per Section XI Program 08-007 and Work Request B273070100.

Discharge flange bolting material (1 stud and 2 nuts)were changed out on SRV B2103F013Pprocured per PO# 4700062335, Inlet flange bolting material (1 stud and 2 nuts) were changed out on SRV B2103F013Hprocured per PO# 686576 and #806420. All material is ASME Class 1 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the'ASME Code, Section Xl.Type Code Symbol Stamp Original Code data reports to be supplemented by OwnersSection XI Program #08-006 Certificate of Authorization No. Expiration Date N/A Signed R.MK Hambleton Lead ISI Engineer Date 7 ,2009 Owner or Owner's Designee, Tide CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT ý! of One State Street, Hartford, CT 06102 have inspected thecomponents described in this Owners Report during the period-5-e,-'9 to--2/- 0 9 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section XA.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_____________________

Commissions ,C _,/ : Inspectors Signature National Board, State, Province, and Endorsements Date /'-Y / " '1 2009 (10/94)For complete work packages, see listing on attached matrix.* -

2009 Refueling Outage SRV Replacement Matrix RF13 -Section Xl Program #08-006 REMOVE INSTALL" All the "Main Body" SN#s listed and installed have had the Main Disc/Piston Modification SRV Pilots & Main Bodies listed SRV Pilots & Main Bodies listed below Performed.

below were Removed during were Installed During RF13 Refuel* New Solenoid valves were installed on each SRV RF13. (Shaded Areas) Outage. (Shaded Areas)during RF13. Note that 4 Main Bodies listed below are complete Valve assemblies with Pilots already installed.

Steam Work N-5 Code Required PIS Number Valve/Body Pilot Solenoid Valve/Body Pilot Solenoid Line Order Data Set Point S/N S/N S/N S/N S/N S/N report Psig- B2104F013 Position D 25981452 N5-0265 1135 A 337 331 310 337 -142, 442 C 25981406 N5-0301 1135 B 392 311 392 1197 441 B 25981373 N5-0291 1135 C 328 317 328 375-439 B 25981352 N5-0278 1145 D 389 3 1 l318 389 327.435 C 25981328 N5-0309 1155 E 373 !3334ý , 312 373 -3U6. 440 B 25981303 N5-0290 1145 F 332 :338 -319 332 339 -433 B 25981193 N5-0321 1135 G 341338{41, 326 2 1200 443 C 25981264 N5-0266 1155 H -336..ii,1176<

313 -I- 1199g 430 C 25981168 N5-0308 1155 J 321 i-182-,. 314 321 -3289 438 B 25981121 N5-0311 1135 K 342 -:373 321 342 332 431 A 25981099 N5-0313 1145 L 319 3888 320 -330i 3,19. 434 A 25981009 N5-0268 1145 M 339 1178'. 325 339 321 445 A 25980981 N5-0310 1145 N 371 ---337 324 371 330 444 D 25980926 N5-0322 1155 P '31. -390. 315 341:i, 7, 318 -432 C 25980898 N5-0288 1155 R 340 J33:335ý.

316 340 1180 -- 436 C)('p FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI ,08-007 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Date Sheet Address 2. Plant Fermi 2 Nuclear Power Plant 07/08/2009 1 of' 2 2 Repair: Target Rock Corp, P.O. 4700163746 Testing: NWS Technologies, P.O.4700163746 Unit Name 6400 North Dixie Highway, Newport MI 48166 Address 3. Work Performed by Detroit Edison Company Name 6400 North Dixie Highway, Newport, MI 48166 Repair Organization P.O. No., Job No., etc.Type Code Symbol Stamp Authorization No.Expiration Date N/A NIA N/A Address 4. Identification of System B21 Nuclear Boiler, Main Steam Safety Relief Valve Pilot Assemblies, and Main Bodies..5. (a) Applicable Construction Code ASME Ill Class 1 19 71 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements Edition S'1970 1992, 92 Addenda Addenda, NA Code Case 6. Identification of Components Repaired or Replaced and Replacement Components National ASME Name of Component Name of Manufacturer Board Other Year Repaired, Replaced, Code Manufacturer Serial No No. Identification Built of Replacement Stamped (Yes or No)SRV Pilot Assemblies Target Rock Various, See N/A B2104F013A-R N/A Replacement Yes attached list SRV Main Body Target Rock Various, See N/A B2104F013A-R N/A Replacement .Yes Assemblies attached list 7. Description of Work 8. Tests Conducted:

Rebuild & Test 15 SRV Pilot Assemblies, and4 SRV Main Bodies as required.Hydrostatic El Pneumatic E] Nominal Operating Pressure []Other M] Pressure psi Test Temp. OF)Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)Form NIS-2 (Back)

9. Remarks Applicable Manufacturer's Data Reports to be attached where required.All 15 SRV Pilot Assemblies, and 4 main Bodies were rebuilt and tested as necessary under NWS P.O. 4700163746, and Target Rock was subcontracted for making the actual repairs. All Parts used arerecorded in Work Request 25998832, as well as the Target Rock final document package from refurbishment activities.

See Sheet 2 of 2 for a list of SRV Main Body Serial Numbers that Pressure Retaining Parts were replaced on. No welding repairs were performed.

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this replacement conforms to the rules of the ASME Code,Section XI. repair or replacement Type Code Symbol Stamp Original Code Data Reports to be supplemented by Section XI Program 08-007 Certificat Authori.ation No. N/A Expiration Date N/A Signed O o ,, LDate ' ." .2009' Owner o-' 'r's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by H. S. B. /CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period. / 0 -OY- zc,&918 -to e ;7'-,-,/--7_.0 2 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_________________________

Commissions

,,Ltd> /Q Inspector's Signature National Board, State, Province, and Endorsements Date , 7 a't.y' ,' 7,

2009 L/(10194)For complete work package see Work Orders 25998832 Attachment (1) NIS-2 Repair Replacement Program 08-007 Sheet 2 of 2 Pressure Retainin2 Parts Installed in SRV Main Bodies Main Valve Pilot Base to'body Nut P.O.#, Lot#, orHT#Body SIN# 1-1/8-12 unf. Stock#252-0565 MM#100014364 330 9ea. P.O.-#402217 330 3ea- P.O.-#4700120991 341 2ea. P.O. -#424169 341 lOea. P.O.-#4700120991 391 l2ea. P.O.-#4700120991 372 12ea. P.O. -#424169 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 08-008 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport Ml 48166 Date Sheet Unit July 8, 2009 Address 2. Plant Fermi 2 Nuclear Power Plant Name 6400 North Dixie Highway, Newport MI 48166 1 of 6 2 Deco Maintenance Address Detroit Edison Company Repair Organization P.O. No., Job No., etc.3. Work Performed by Name 6400 North Dixie Highway, Newport, MI 48166 Address Type Code Symbol Stamp Authorization No.Expiration Date N/A N/A N/A 4. Identification of System Various Component Supports (Mechanical Snubbers)5. (a) Applicable Construction Code 'ASME III 19 71 W" 71 Addenda ASME Il 19 74 Edition No Addenda*(b) Applicable Edition/Addenda of Section Xl Utilized for Repairs or Replacements 1992-92 Addenda (Piping)1644-5 Code Case 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)PLANT MECHANICAL PACIFIC Various N/A *None Various Replacements Y SNUBBERS SCIENTIFIC Description

7. of Work Refurbish mechanical snubbers for installation and install replacement snubbers in RF13.8. Tests Conducted:

Hydrostatic [ ] Pneumatic

[] Nominal Operating Pressure [ ]Other [X] Pressure

_ psi Test Temp._

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

Subsection NF (10/94)

Form NIS-2 (Back)

9. Remarks: Attached are listings of Mechanical Snubbers that were refurbished and changed out during RF13.

The listing of the Mechanical Snubbers that were refurbished prior to and during RF13 includes a listing of load bearing parts installed.

Documentation satisifies the reguirements of Code Case N-508-1 as allowed by relief reQuest RR-C4.Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code, Section Xl.Type Code Symbol Stamp Original Code data report to be supplemented by OwnersSection XI Program 08-008.Certificate of Authorization No. N/A '- Expiration Date N/A Signed R. M. Hambleton, Lead ISI Engineer " Date .-"'--C" ) 2009Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period -.-.-U-081 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

________________

Commissions / Q lnspector's Signature National Board, State, Province, and Endorsements Date , / 2009 (10/94)For complete work package, see Work Orders 26004968 and 25975196 as well as the installation work orders that are detailed on sheets 4. 5, and 6.

Mechanical Snubbers Rebuilt with New Load Bearing Parts NIS-2 for:08-008 Sheet .' of Serial Snubber Size Description PO Work Order 1 Location I 19911 Spare 1/4 Capstan Spring Resv 100077 26004968 22380 T23-12837-51-G141 1/4 Torque Carrier and Shaft Assembly Resv 100077 26004968 8470 C41-2340-G-17 1/2 Torque Carrier and Shaft Assembly Resv 100077 26004968 8482 B21-2174-G25B 1/2 Capstan Spring, Torque Carrier and Resv 72579, 26004968 Shaft Assembly 100077 .8497 Spare 1/2 Capstan Spring Resv 100077 26004968 13117 T23-12837-40-G09A 1/2 Torque Carrier and Shaft Assembly Resv 100077 26004968 16225 T23-12837-46-G100 1/2 Torque Carrier and Shaft Assembly Resv 100077 26004968 9855 Spare 1 Thrust Bearing Kit Resv 100077 26004968 18654 Spare 1 Thrust Bearing Kit Resv 72579 26004968 23168 Spare 1 Thrust Bearing Kit Resv 72579 26004968 20980 E11-3151 -G17 3 Thrust Bearing Kit Resv 100077 26004968 6174 Spare 10 End Plug Assembly, Telescoping Parts taken from 25975196 Cylinder, Serial No. 8963 6190 E11-3154-G13 10 Thrust Bearing Kit Resv 137320 26004968 8963 B21-2297-G 1 10 Telescoping Cylinder Part taken from 26004968 Serial No. 9007 8965 N21-3536-G31 10 Thrust Bearing Kit Resv 137320 26004968 8981 N21-3536-G38A 10 Thrust Bearing Kit, Capstan Spring Resv 100077, PO 26004968 4700161690 8982 N21-3131 -G38 10 Thrust Bearing Kit Resv 137320 26004968 8983 E41-3172-G19 10 Thrust Bearing Kit Resv 137320 26004968 8994 N21-3131 -G33 10 Thrust Bearing Kit Resv 137320 26004968, 8999 B21-4096-G08 10 Thrust Bearing Kit Resv 100077 26004968 Thrust Bearing Kit, Clutch Spring, Ball Resv 100077, 25975196 Bearing Screw Assembly, Support Batch No. 412030-Cylinder 01, Resv 177899, Part taken from Serial No. 10334 9007 N21-3537-G38A 10 Telescoping Cylinder Part taken from 26004968 Serial No. 12771 10347 Spare 10 Thrust Bearing Kit Resv 137320 26004968 10348 B21-2590-G07 10, Thrust Bearing Kit Resv 137320 26004968 12771 N21-3537-G37 10 Telescoping Cylinder, End Plug Parts taken from 26004968 Assembly Serial No. 10334 12772 N21-3536-G38B 10 Thrust Bearing Kit Resv 137320 26004968 12812 N21-3537-G28 10 End Plug Assembly and Telescoping Parts taken from 26004968 Cylinder, Thrust Bearing Kit, Bearing Serial No. 8956, Retainer Nut Resv 137320, Resv 100077 12815 B21-4096-G 1 10 Bearing Retainer Nut Resv 100077 26004968 4709 Spare 35 Thrust Bearing Kit, Capstan, Balls, PO 4700062678, 26004968 Balls Part taken from Serial No. 7736, Resv 177874 Mechanical Snubbers Rebuilt with New Load Bearing Parts*NIS-2 for 08-008 Sheet Z of 6 Serial ' Snubber Sizer Description PO- WorkOrder Location ___ __9887 N21-3537-G39 35 Telescoping Cylinder, Capstan Spring Part taken from 26004968 Serial No. 8739, Resv 100077 11286 E11-2299-G 19 35 Telescoping.Cylinder Part taken from 26004968-Serial No. 9887 12793 B21-2592-G02 35 Thrust Bearing Kit, Balls, Balls Batch No. 26004968 416477/03, Resv 1778741583 N30-3259-G75B 100 Thrust Bearing. Kit Resv 72759 26007968 1590 N30-3259-G32 100 Thrust Bearing Kit, Balls, Balls Resv 181761, PO 25975196 4700225215Note that these parts are ASME parts. Listing does not include non-load bearing parts (retaining rings, washers).

Mechanical Snubbers Replaced with Rebuilt Spares in RF13 NIS-2 for 087008 Sheetj of HHanger NPumber Old Serial Number Work Order Final Serial Number B21-2174-G25B 13183 26977578 8482 B21-2187-G81 22443 26978201 12718 B21-2297-G08 8978 29686317 8340 B21-2297-G 11 1 8960 29652025 " 8963 B21-2586-G06 9016 29686257 6182 B21-2590-G07 8967 26975914" 10348 B21252G28-7-22,-

2-697,5914 12793 B21-2592-G 10 6182 29686257 i12820 B21-2593-G 13 1 8357 26975914 10354 B21-4093-G 13 6185 29652025i 9021 B21-4094-G05i 9026 29652025 12809 B21-4096-G08 10352 29652025 1 8999 B21-4096-G11i 9012 29686257 1 12815 B21-E213-SSB1 8993 26975914 8970 B21 -E213-SSB6

-11275 26975914 11272 B31-5065-G39B 22337. 26977761 22343 B31 -E215-SSA4 9879 26977761 6771 B31-E215-SSB10 9880 26977799 -9868 C41-2340-G17, 13171 .i 26976616 8470 E 11-2299-G 19 11277 26976797 11286 E11-3146-G23 9018 26976110 8363 E11-3146-G37B 8996 26976241 8968 E11-3151-G17 20978 26976146 1 20980 E11-3154-G 13 8953 1 26976897 6190 El1-3184-G24 20989 26976277 12450 E11-3185-G32B 8325 26976241 12799 E11-3519-G14 20969 i 26977008 ___ 20983 E11-4004-G22 12992 26976110 12727 E21-3053-G04 6179 26976745 12816 E41-3162-G24 12777 -29686317 8967 E41-3162-G26 8331 26976409 6175 E41-3172-G19 8345 29686317 _ _ 8983 E41-5256-G20SA

.19923 26976409 12753 E51-3174-G09 8709 26976487 11268 G33-3245-G49-18649 926976525 21948 G51-4055-G20

_ 20979 29686342 20958 G51-4056-G20 15282 26976605 15284 N21-3131-G33 6178 26975877 8994 N29-3031030^900026"'9-7-5 8 77 _8982 N21-3536-G31 8339 29654378 8965 N21-3536-G35 8340 29654378 10350 N21-3536-G38A 8992 26977705 8981 N21-3536-G38B 6174 26977705 -12772 Mechanical Snubbers Replaced with Rebuilt Spares in RF13 NIS-2 forO8-008 Sheet 5'o Hanger Number Old N21 -3537-G28'8 N21 -3537-G31 N21-3537-G37 N21 -3537-G38A N21-3537-G38B N21-3537-G39 N30-2186-G09 N30-2186-G13_

N30-2186-G17 N30-3259-G32 N30-3259-G33 N30-3259-G37 N30-3259-G48

_N30-3259-G58 N30-3259-G75B N30-3526-G48 N30-3526-G57 N30-3526-G57 P34-7405-GO5 T23-12837-36-G56 T2ý3-42 --8"3-7"-4-0" -G08--'T23-12837-40-G09A T23-12837-41 -GO5A T23-12837-42-G22 T23-12837-42-G36 T23-12837-43-G49 T23-12837-45-G17 T23-12837-45-G 11 A Tý3 -i2837 -4'6 -G1 0-0 _T23-12837-51 -G141 T23-12837-51-G142 T23-12837-51-G 144 _T23-12837-51 -G 19T23-12837-51 -G28T23-12837-51 -G29 T23-12837-51 -G33T23-12837-51 -G43 T23-12837-51 -G61T23-12837-51 -G62 T2-3092-G05 T48-4062-GO1 SerialNum...... 8 32,9i ..........

12792 8358 9011 11223 13142 9859 12988 40236 4711 8717 8742 9845 1586.12750 13195 13194 6827 11975 12722 21954 13187 8465 19921 22387 12760 18645 13131 22417 22451 8484 _12733 212363 12745 22365 22420 22434 13200 27917 12811 12683 ber Work Order Final 29654378 26977705 26977705 26977705 26977705 26977578.26977578 26977578 29681008 26977080 26977080 26977080 26977080 ..26977080 26977302 26977302 26977302 26977058 26978013 26978110 26978110 26978013 26978106 26978106.26978013 26978013 26978013 26978110~26978110_ 26978106" 26978110 26978110-26978110 26978110 26978110 26978110 26978201 26978110 26978110 29686344 26977396 Serial Number 8357 12771 9007 9010 9887 8499 21947 12708 1590 8734 9897 8724 1583 22423 13158 13198 13184 ... .. .12690 12764 9857 13117 13153 22335 12725 19910 21951 16230 16225 22386 -- .-22380.13191 12720 19924 19916 22403 12729 13179 12734 8991 22352 Mechanical Snubbers Replaced with Rebuilt Spares in RF13 NIS-2.for 08-008 Sheet ,,of Hanger Number j Old Serial Number Work Order A Final Serial Number T48-5314-GO5 22388 i26977396 12751 T71-12837-62-G35 22353 26977200 22437 T71-12837-62-G57 12692 26977844 22339 T71-12837-63-G32 13133 26977844 8467 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 08-009 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport, MI 48166 Address 2. Plant Fermi 2 Nuclear Power Plant Date Sheet Unit July 8, 2009 I of 4 2 Name 6400 North Dixie Highway, Newport, MI 48166 3. Work Performed by Address Detroit Edison Company Deco Maintenance Repair Organization P.O. No., Job No., etc.Type Code Symbol N/A Stamp Name 6400 North Dixie Hiqhway, Newport, MI 48166 Authorization No.Expiration Date N/A.N/A AddressVarious Component Supports (Hydraulic Snubbers)

4. Identification of System 5. (a) Applicable Construction Code ANSI B31.7 19 69 Articles 1-720 & 1-721 ANSI B31.1 19 67 Articles 121 (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or Replacements 1992-92 AddendaIdentification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)PLANT HYDRAULIC POWER Various N/A None Various Replacements N SNUBBERS PIPING Description

7. of Work Refurbish hydraulic snubbers for installation and install replacement snubbers in RF13 8. Tests Conducted:

Hydrostatic

[] Pneumatic

[] Nominal Operating Pressure []Other [ X] Pressure psi Test Temp.Functional test and visual inspections Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.* Subsection NF (10/94)

Form NIS-2 (Back)9. Remarks: Attached are listings of Hydraulic Snubbers that were refurbished and changed out during RF13. The listing of the Hydraulic Snubbers that were refurbished prior to and during RF13 includes a listing of load bearing parts installed.

Documentation satisfies the requirements of Code Case N-508-1 as allowed by relief request RR-C4.Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of theASME Code, Section Xl.Type Code Symbol Stamp Original Code data report to be supplemented by OwnersSection XI Program 08-009.Certificate of Authorization No. N/A Expiration Date N/A Signed R. M. Hambleton, Lead ISI Engineer A QC. Date e) 2009Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan nd employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period 16 -)--'-o to 7- "ý/- 0 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section X1.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_____________________________

Commissions

-'_"-' S Inspector's Signature National Board, State, Province, and Endorsements Date -, j'J.5" 2009 Dt/(10/94)For complete work package, see Work Orders 25975209 and 25996656 as well as installation work orders that are detailed on sheets 3, and 4.

Hydraulic Snubbers Rebuilt with New Load Bearing Parts N IS-2 for 08-009 ,, ~Sheet I-_of!Serial Snubber Location Size Description Reservation Work Order 810102 El 1-3184-G31 1 1/2 x.5 (Tie Rod) Locknuts 171741 25996656 820129 Spare 1 1/22 x 5 Cylinder 93441 25996656 810083 E21-3147-G09 2 x 5 Cylinder 157699 25996656 830053 El 1-3160-G15B 2 x 5 Cylinder 157699 25996656 810091 El 1-3158-G20 4 x 5 Cylinder 177356. 25996656 810129 Spare 4 x 5 Tie Rod 183878 25975209 Note that these parts are non-ASME as all Power Piping snubbers were not fabricated to ASME requirements.

This list does not include non-load bearing parts (o-rings, piston rings, seal kits, reservoir brackets, sightglasses, poppets, tubing).

Hydraulic Snubbers Replaced with Rebuilt Spares in RF13 NIS-2 for 08-009 Sheet of Hanger Number Old Serial Number Work Order Final Serial Number E11-3151-G13

810146 26976146 810160 E 1 1 9 830055 E11-3152-G29B~

830041 26976797 8305 E11-3157-G08 810134 -26976241 810217 E11-3158-G20 820194 26976146 _ 810091 E11-3159-GO2

.810010 26976110 810043 E11-3160-G11 810181 26976241 820161 E11-3160-G15A 820006 -26976241 820226E11-3160-G15B 810073 26976241 830053E11-3160-G17 830055 , 26976241 810159 E11-3164-G26~

81020? j26976921 810148 E11-3177-G20 820060 26976277 820225 E11-3184-G31 830016 26976146 810102 E11-3185-G38 820216 26976110 1 820093 E11-4612-GO4A 810173 29714474 .810104 E21-3145-G17 810050 26976678 820165E21-3147-G08 810230 26976745 830052 E21-3147-G09 810080 269767451 810083 E41-3162-G20 8101364 26976409 810054 E41-3172-G11

_ 810131 26976409 810027 E51-3174-G17 J 820070 26976487 820080 E51-3175-G02.

830051 26976487 810198 E51-3175-G21

-820252 26976487 820185 G33-3244-G36A 820083 26976525 810014 G33-3244-G36B 820078 26976525 810178 N21-3109-G62 , 810129 29671315 830029 N21 -31 09-G63B 820196 29652024 820194 N21-3109-G66A r 830029 29652023 830032 N21-3109-G71B i 830032 29647144 820060T48-2366-G26B 820172 26977396 810036 Hydraulic Snubbers Rebuilt and Re-installed in RF13 NIS-2sfor 08-009___ __ __ __ _ __ __ heet of LHanger Number Old Serial Number Work Order Final Serial Number E21-3147-G37 820154 26976745 same N21-3103-G20A 820014 26975877 same N21-3103-G2oB F 820133 29658435 same N21 -31 09-G64A 830044 29658597 -same N21-3109-G64B 830045 29671401 same N21-3109-G68 810207 29681007 1 same N21-3109-G7OA 820058 29680940 sameN213109-G70B 820096 29647105 same N21-3109-G72A 810092 26975877 same N21-3109-G77B 1 810090 26975877 same FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xi 08-011 1. Owner Detroit Edison Company Date January 7,2009 Name 6400 North Dixie Highway, Newport MI 48166 Address 2. Plant Fermi 2 Nuclear Power Plant Name 6400 North Dixie Highway, Newport MI 48166 Sheet Unit 1 of 1 2 Deco Maintenance

3. Work Performed by Address Detroit Edison Company Name Repai Type Code Symbol Stamp Authorization No.Expiration Date r Organization P.O.

No., Job No., etc.N/A N/A 6400 North Dixie Highway, Newport, Ml 48166 N/A 4. Identification of System Address Core Spray System Division 2 Discharge Piping Pipe Supports (Hydraulic Snubber E21-3147-G27)

5. (a) Applicable Construction Code ANSI-B31.1 19 67 ASME Il1 19 71 (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or Replacements Article 121 Edition W' 71 (Hangers)Addenda (Piping) N/A Code Case1992-92 Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)E21-3147-G27 Power Piping 810049 N/A E2147G027 1981 Replaced N E21-3147-G27 Power Piping 810213 N/A E2147G027 1981 Replacement N Description

7. of Work Installed Replacement Snubber due to leakage from a cylinder end seal.

In addition, the rod paddle was exchanged due to bearing configuration.

The Snubber was not inoperable but was changed to minimize maintenance activity.

The reolacement snubber was functionally tested and visually inspected.

8. Tests Conducted:

Hydrostatic

[] Pneumatic

[] Nominal Operating Pressure Other [X] Pressure

_ psi Test Temp._ _ F Visual per 43.000.003 Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 81/2 in. X 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)

9. Remarks: Replacement Snubber was previously installed in the plant and was previously refurbished (seal replacement) per work order #A497060100.

No load bearinq parts were replaced at the time of seal replacement., Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify~that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code, Section Xl.Type Code Symbol Stamp Original Construction records for the snubber to be supplemented by OwnersSection XI Program 08-011.Certificate of Authorization No. Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer -Date .---i -k 1 .2009 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period,/ 4- to 9 7 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section X1.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions_________________

Inspector's Signature National Board, State, Province, and Endorsements Date ,A ./ 2009 (10/94).For complete work package, see Work Request # 28982441, FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 08-012A 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Date Sheet Unit June 5,2009 1 of 2 Address 2. Plant Fermi 2 Nuclear Power Plant 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance Repair Organization P.O.

No., Job No., etc.3. Work Performed by Address Detroit Edison Company Type Code Symbol Stamp Authorization No.Expiration Date N/A Name 6400 North Dixie Highway, Newport, MI 48166 N/A N/A 4. Identification of System Address N5-0047 and N5-0716 -P50 Station and Control Air System from the Air Header to the North and South Air Compressors NIAS Division 1 and Division 2 5. (a) Applicable Construction Code ASME Ill, Class 3 19 71 Edition W' 71 Addenda (b) Applicable Edition/Addenda of Section Xl Utilized for Repairs or Replacements 1992-92 Addenda 6. Identification of Components Repaired or Replaced and Replacement Components N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)P5000F2246A Velan 011013-1 N/A V30-1830 2001 Replacement Y P5000F2247A Velan 011013-4 N/A V30-1832 2001 Replacement Y P5000F2248A.

Velan 011013-6 N/A V30-1839 2001 Replacement Y P5000F2249A Velan 011013-8 N/A V30-1841 2001 Replacement Y 7 Description of Work Modify the air supply source to provide dry air from the Interruptible Control Air Receiver P5002A005 via valve P5000F313P with a new line. The piping will be cleaned and new filters will be added upstream of isolation valve P5000F440 (EDP-34625)

8. Tests Conducted:

Hydrostatic

[ ] Pneumatic

[] Nominal Operating Pressure [ X Other [X] Pressure psi Test Temp.Code Case N-416-2 Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)9. Remarks: Replaced Valves were obtained per Purchase Order #4700162372 All other ASME Code material was verified to meet ASME Class 3 requirements and is detailed in work order and EDP-34625.

Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of theASME Code,Section XI.Type Code Symbol Stamp Original Code data report N5-0047 and N5-0716 to be supplemented by OwnersSection XI Program 08-012A.Certificate of Authorization No. I Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer Y,, Date -" ,2009Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owners Report during the periodA- -z>9 to 6, -,9 -ý" ,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_Commissions Inspectors Signature National Board, State, Province, and Endorsements Date , .*,,2009 (10/94)For complete work package, see Work Request 28171173 and 28171257

.9-z o2-.~ c~C\Z DATA PACKAGE NO. 011013 FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES As Required by the Provisions of the ASNE Code, Section 111, Division 1*Pg. 1.of *2 1. Manufactured and certified by VELAN INC. 2125 WARD AVE,MONTREAL.OUEBEC CANADA H4MIT6 (name and address of N Certificate Holder)2. Manufactured for FRAMATOME TECHNOLOGIES 3315-A OLD FOREST RDLYNCBURGVA.USA 24501(name and address of purchaser)

3. Location of installion N/A (name and address)'4. Model No., Series No., or Type: GATE Drawing Pl-76800-N21 Rev HIT CRN N/A 5. ASME Code,Section III, Division 1: 1989 NONE 1 N/A (edition) (addenda date) (class) (Code Case no.)6. PUmp or valve VALVE Nominal inlet size 2 Outlet size' 2 7. Material:

Body, SA-182,F316 BonnetSA-182, F316 Disk SA-351,CFSM Bolting SA-194.8M SA-564, 630H1100 (a)Cert.Holder's Serial No.Cb)Nat'Board No.(c)Body Serial No.(d)Bonnet Serial.No.011013-1 011013-2 011013-3 011013-4 011013-5 011013-6 011013-7 011013-12 011013-9 011013-10 011013-11 011013-12 011013-13 011013-14 011013--15 N/A H/C: CCE CCE CCE CCE CCE CCE CCE CCE CCE CCE CCE CCE CCE CCE CCE H/C: BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT (e)Disk Serial No.H/C: 62H 62H 62H 62H 622H 62H 62H' 62H 62H 62H 62H 62H 62H 62H 6S2H Supplemental information In form of lists, sketches, or drawings may bd used provided (1) size is S In x 11, (2) information in items I through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the.top of this form.(12/88) This form (E00037) may be obtained from the Order Dept, ASME, 22 LAW DR!V'E< BOX 23P.0 Fn hifield, NJ 07007-2300.

f LPAGE OF 2/

FORM NPV- 1 (Back -Pg. 2 of 2 Certificate Holder's Serial No. 011013 8. Design conditions 1920 psi 100 @F or valve pressure class (pressure) (tamperat-are)

9. Cold Working pressure 1920 psi at 100*F 10. Hydrostatic test 3000 psi. Disk differential test pressure 220 80o0 (p )0 psi 11. Remarks: MATERIALS MEET ASME SECTION II EDITION: 1989 ADDENDA: NONE CERTIFICATE OF DESIGN Design Specification certified by M.LAVIGNE P.E. State QOUl Reg. no. 40052 Design report certified by S. tSBITSKY P.E. State QU9 Reg. no. 22115 CERTIFICATE OF COMLI"ANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASHE Code, Section 1II, Division 1.N Certificate of Authorization No. IT-2797i IE APRIL 20,2004 Date JUN 0 5 '0 Name VELAN INC. Signed (N Certificite fHolder) (authorized rqe'.etadve)

CERTIFICATE OF INSPECTI0N 1, the undersigned, holding a valid cozmission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of -QUEBEC and employed by REGIE DU BATIX9NT of oUEBEC have inspected the pump, or valve, described in this Data Report on C/--pC-- S -, and state that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, in accordance with the AS~dE Code, Section I1, Division 1.By signing this certificate, neither the inspector nor his employer makes any warrenty, expressed or implied, concerning the component described in this 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 an kind ising from or connected with this inspection, R.LAUZON QC # 872 Datel- O~ S -signed -OsUEBEC A riedln (Nz$t't. Bd. (C-or arMT DJ QuaB)-State or Pr0Y. :and fib.) --(1) For manually operated valves only.iLPAGE ~OF 32- --~--

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 08-012B 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Date Sheet Unit June 5,2009 1 of 2 Address 2. Plant Fermi 2 Nuclear Power Plant 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance

3. Work Performed by Address Detroit Edison Company Repair Organization P.O. No., Job No., etc.Type Code Symbol Stamp Authorization No.Expiration Date N/A Name 6400 North Dixie Highway, Newport, MI 48166 N/A N/A Address N5-0047 and N5-0716 -P50 Station and Control Air System from the Air Header to the North and 4. Identification of System South Air Compressors NIAS Division 1 and Division 2 5. (a) Applicable Construction Code ASME Ill, Class 3 19 71 Edition W' 71 Addenda (b) Applicable Edition/Addenda of Section XA Utilized for Repairs or Replacements 1992-92 Addenda N/A Code Case6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)P5000F2246B Velan 011013-3 N/A V30-1831 2001 Replacement Y P5000F2247B Velan 011013-5 N/A V30-1833 2001 Replacement Y P5000F2248B Velan 011013-7 N/A V30-18409 2001 Replacement Y P5000F2249B Velan 011013-9 N/A V30-1842 2001 Replacement Y 7. Description of Work Modify the air supply source to provide dry air from the Interruptible Control Air Receiver P5002A005 via valve P5000F313P with a new line. The oioing will be cleaned and new filters will be added upstream of isolation valve P5000F441 (EDP-34625)

8. Tests Conducted:

Hydrostatic

[I] Pneumatic I] Nominal Operating Pressure [ X I Other [ X] Pressure psi Test Temp._Code Case N-416-2 Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)9. Remarks: Replaced Valves were obtained per Purchase Order #4700162372 All other ASME Code material was verified to meet ASME Class 3 requirements and is detailed in work order and EDP-34625.

Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of theASME Code, Section Xl.Type Code Symbol Stamp Original Code data report N5-0047 and N5-0716 to be supplemented by OwnersSection XI Program 08-012B.Certificate of Authorization No. N/A \. Expiration Date N/A Signed R.M. Hambleton Lead ISI Enaineer Date LA- Vc.; ,2009 Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period to 6- -,,,0 2 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this' Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_ _ _ _ _._ _Commissions_

__ _ _ _ _ _ ___'1____Inspector's Signature National Board, State, Province, and Endorsements Date , 2009 (10/94)For complete work package, see Work Request 28171199 and 28171267 FORM NPV-1 (Back -Pg. 2 of 2 Certificate Holder's Serial No. 011013 8. Design conditions 1920 psi 100 'r or valve pressure class 800 (1)(pressure) (temperature)

9. Cold Working pressure 1920 psi at 100*F 10. Hydrostatic test 3000 psi. Disk differential test pressure 2200 psi II. Remarks: MATERIALS MEET ASME SECTION I1 EDITION: 1989 ADDENDA: NONE CERTIFICATE OF DESIGN Design Specification certified by M.LAVIGNX P.E. State 013 Reg. no. 40052 Design report certified by S. ISBITSTY P.E. State Qf9UR Reg. no. 22115 CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for constr-uction of the ASME Code, Section I1I, Division 1.N Certificate of Authorization No. N-2797-1 E APRIL 20,2004 Date JUN ' 5 Name VELAN INC. Signed (N Certificate Holder) (authorized r.eesentative)

CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of QUEBEC and employed by REGIE DU BATIMENT of QUEBEC have inspected the pump, or valve, describedin this Data Report on ____C-- S-- , , and state that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, in accordance with the ASME Code,Section II, Division 1.By signing this certificate, neither the inspector nor his employer makes any warrenty, expressed or implied, concerning the component described in this Data Report. Furthermore, neither the imspector nor, his employer shall be liable in any manner for any personal injury or property damage or a loss" of any kind ising from or connected with this inspection.

FR AUZON 00C#872 Date(-O(i

' -signed ----ommissions QUEBEC ., trjid4ized Ins,$e, (Nrtro. Bd. (ncl nMt1iM41T --

OUtBEC state or proy. aad fi6.)(1) For manually operated valves only.PAGE .OF

~oS..-ck\z=-DATA PACKAGE NO. 011013 -FORP1 NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES *As Required by the Provisions of the ASdE Code,Section III, Division 1 Pg. 1.of 2 1. Manufactured and certified by VELAN INC. 2125 WARD AVEMONTRRAL.QUEBEC CANADA H4MIT6(name and address of N Certificate Holder)2. Manufactured for F AMATOME TECHNOLOGIES 3315-A OLD FOREST RD.LYNCHBURGVA.UJSA 24501(name and address of purchaser)

3. Location of installion N/A'(name and address)'4. Model NO., Series No., or Type: GATE Drawing Pl-76800-121 Rev H CRN N/A 5. ASME Code,Section III, Division 1: 1989 NONE 1N/A(edition) (addenda date) (class) (Code C2ase no.)6. Pump or valve VALVE Nominal inlet size 2 Outlet size' 2 7(in) 3,B.)7. Material:

Body, SA-182,F316 BonnetSA-182, F316 Disk SA-351,CF8M Bolting SA-194.8M (a)Cert.Holder's Serial No.Cb)Nat' 1 Board No.(c)Body Serial No.(d)Bonnet Serial No.011013-1 011013-2-011013-3 011013-4 011013-5 011013-6 011013-7 011013-18 011013-9 011613-10 011013-11 011013-12 011013-13 011013-14 011013-15 H/C: CCE CCE CCE CCE CCE CCE CCE CCE CCE CCX CCX cCE CCE CCE CCE H/C: BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT BVT SA-564, 630H1100 Ce)Disk Serial Nqo H/C: 62E 62H 62H 62H 62H 62H 62H* 62E 62H 62H 62H 62H 62H 62H 62E Supplemental information In form of lists, sketches, or dr2wings m2y be used provided (I) size is 8 2 x 11, (2) information in items I through 4 on this. Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the.top of this form.(12/88) This form (E00037) may be obtained from the Order Dept, ASMF, 22 LAW DRJV'< BOX.-23.p Fai-fie 7" eid, NJ 07007-2300.

= PGE z~OF 32-J

.K-FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl 08-014 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Address 2. Plant Fermi 2 Nuclear Power Plant Date Sheet Unit January 8, 2009 1 of 2 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance Address Detroit Edison Company Repair Organization P.O.

No., Job No., etc.3. Work Performed by Type Code Symbol Stamp Authorization No.Expiration Date N/A N/A N/A 6400 North Dixie Highway, Newport, MI 48166 4. Identification of System Address Emergency Diesel Generator (EDG) Number #11, R3001 S001 Manufacturer

-Colt Quality Records 5. (a) Applicable Construction Code ASME III, .71 S. '73 (Valve)Class 3 19 71 Edition W"71 Addenda (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or Replacements 1992-92 Addenda

6. Identification of Components Repaired or Replaced and Replacement Components N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)R3000F015A TRW Mission 157562 N/A None 1975 Replaced Y R3000F015A C&S Valve Co. 91-1550-01N-2 N/A V30-3053 2008 Replacement Y Description

7. of Work Installed Reolacement Check Valve 8. Tests Conducted:

Hydrostatic [ ] Pneumatic

[] Nominal Operating Pressure [ X ]Other [ ] Pressure _ psi Test Temp._ OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is *recorded at the top of this form.(10/94)

Form NIS-2 (Back)9. Remarks: Replacement Check Valve procured per Purchase Order # 249442. There is no N5 ASME Code data report that contains this specific component.

Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code,Section XI.Type Code Symbol Stamp Original Code Records for R3001 S001 to be supplemented by Owners Section Xl Program 08-014.Certificate of Authorization No. N/A Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer A ciJ,-Date

-, -.20C)!D Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected thecomponents described in this Owner's Report during the period//-/8_oS to o,//- /- 09 , and state that to the best of myknowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XA.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_____________________

Commissions__________

Inspector's Signature National Board, State, Province, and Endorsements Date A/, / 2002 (10/94)For complete work package, see Work Order # E568970307.

CORRECTED COPY FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES*As Required by the Provisions of the ASME Code,Section III, Division 1 Pg. 1 of 2 1. Manufactured and certified by C&S Valve Carpany, Tricentric Division; 40 Chestnut Ave.; Wesb'rnt, IL 60559 (name and address of N Certificate Holder)2. Manufactured for Detroit Edison, 2000 Second Ave.; Detroit, Michigan 48226 (name and address of Purchaser)

3. Location of installation Detroit Edison, EF2-Site; 6400 Dixie Highway; Newrt, Michigan 48166-.(name and address)4. Model No., Series No., or Type Check Drawing 91-1550-01 (N) Rev. A CRN N/A 5. ASME Code,Section III, Division 1: 1971 Suimer 1973 3 N/A (edition) (addenda date) (class) (Code Case no.)6. Pump or valve Valve Nominal inlet size 511 Outlet size 5"* .Mea CFByA 1, 4 tN (in.) 3(in.)*7. Material:

Body SA 351 GR.:9P-onnet " NZA -Disk SA 351 GR. CF34 BoltjngSee Backside of Page (a)Cert.Holder's Serial No.91-1550-01 (N)-02 (b)Nat'l Board No.NA (c)Body Serial No.Heat: 91175 S/N: A353 (d)Bonnet Serial No.N/A (e)Disk Serial No.Heat: 91168 S/N'S: A357 & A358 Supplemental information in form of lists, sketches, or drawings may be used provided (1) size is 81/2 x 11, (2) information in items 1 through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

(121881 This form 1E00037) may be obtained from the Order Dept., ASME, 22 Law Drive, Box 2300, Fairfield, NJ 07007-2300.

corrected material gr. typo FORM NPV-1 (Back -Pg. 2 of 2_ )Certificate Holder's Serial No. 91-1550-01(N)-

02 8. Design conditions 275 psi 100 -F or valve pressure class 150 01)(pressure) (temperature)

9. Cold working pressure 275 psi at 100)F 10. Hydrostatic test 425 psi. Disk differential test pressure 305 psi 11. Remarks: Servce: Check Backflcw S-tqp Pin Retair= -M~aterial SA 1IEZ Ut FT6 ,b Heat Uxde: ML Him-- Pin Retainer-htgtrial SA 182 GR. F316 Heat Ccxie: K1 CERTIFICATION OF DESIGN Design Specification certified by Ronald J. Adler P.E. State Michigan Reg. no. 28412Design Report certified by N/R P.E. State Reg. no.CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code,Section III, Division 1.N Certificate of Authorization No. N-2724 Expires 2 -,-r -Q Date 1kLLc b 4 Name C&S Valve .Ccpany, Tricentric Div. Signed. _(N Certificate Holder).--4authorized representative)

CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by* Allendale M.tual Ins. Co.of Norwoxd, Massachusetts have inspected the pump, or valve, described in this Data Report on t/e /,"- 9'/ , and state that to the best of my knowledge and belief, the Certificate Holder has con-structed this pump, or valve, in accordance with the ASME Code,Section III, Division 1.* Factory Mitual System By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component described in this Data Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any,kind arising from or connected with this inspection.

Date/' /- 9/Signed / -V o siAns Z/a/-'1 .0_2; , At , AJ-3 (Authorized Ifspector)

[Nat'l. Bd. lincl. endorsements) and state or prov. and no.1 (1) For manually operated valves only.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 09-001 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Date Sheet Unit May 18,2009 1 of I Address 2. Plant Fermi 2 Nuclear Power Plant Name 6400 North Dixie Highway, Newport MI 48166 2 Deco Maintenance

3. Work Performed by Address Detroit Edison Company Repai Type Code Symbol Stamp Authorization No.Expiration Date r Organization P.O. No., Job No., etc.N/A Name 6400 North Dixie Highway, Newport, MI 48166 Address N/A N/A 4. Identification of System N5-012 (T&B) Emergencv Diesel Generator#

12 5. (a) Applicable Construction Code ASME Ill, Class 3 19 71 Edition (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or Replacements 19 6. Identification of Components Repaired or Replaced and Replacement Components

'71 Addenda 92-92 Addenda N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)R3001 B027 American Stnd.

5-20002-02-1 26204 Air Coolant 1974 Repair Y Ht. Ex.R3001BOO1 American Stnd. 5-20002-03-1 26210 Lube Oil 1974 Repair YHt. Ex.Description

7. of Work Perform welded repairs to Heat Exchanger Channels caused by pitting erosion. Repairs were performed on the inside surfaces of the channels and reinforcement was made on the shell exterior at several locations.

8. Tests Conducted:

Hydrostatic

[ ] Pneumatic

[] Nominal Operating Pressure [X ]Other [ ] Pressure psi Test Temp._Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)9.Remarks: None Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report arecorrect and this Reoair conforms to the rules of theASME Code,Section XI.Type Code Symbol Stamp Original Code data report N5-012 to be supplemented by OwnersSection XI Program 09-001 Certificate of Authorization No. NLAr, Expiration Date N/A Signed R.M. Hambleton Lead ISI Enqineer .Date .20 7A Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period 2-Z-r-D to 7- 1& --c5 ,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions

/,-,2 _Inspector's Signature National Board, State, Province, and Endorsements Date 20 (10/94)For complete work package, see Work Request 29188615 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI I 09-003 1. Owner Detroit Edison Company Name 6400 North Dixie Hiahway, Newport MI 48166 Date Sheet April 29, 2009 1 of*2 Address 2. Plant Fermi 2 Nuclear Power Plant Unit 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance Address Detroit Edison Company 3. Work Performed by Repair Organization P.O. No., Job No., etc.Type Code Symbol N/A Stamp Authorization No. 'N/A Expiration Date N/A Name 6400 North Dixie Highway, Newport, Ml 48166 Address (N5-0307)

Residual Heat Removal (Division 2)4. Identification of System 5. (a) Applicable Construction Code ASME Ill, Class 2 19 71 Edition W` 71 (b) Applicable Edition/Addenda of Section XA Utilized for Repairs or Replacements 1992-92 Addenda 6. Identification of Components Repaired or Replaced and Replacement Components Addenda N-154 Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)El 1 00F071 B William Powell 64662-23 N/A V8-2112 1977 Replaced Y E1100F071B Flowserve BH-145 N/A V30-1826 2009 Replacement Y Corporation E1100F072B William Powell 64662-27 N/A V8-2116 1977 Replaced Y E1100F072B Flowserve BH-146 N/A V30-1827 2009 Replacement Y Corporation Description

7. of Work Replaced the existing valves with replacement valves obtained from stock. The installed valve bodiesexhibited corrosion and erosion as a result of identified seat bypass leakage. The need for valve replacement was identified during RF12 disassembly, and a replacement disc was temporarily installed to improve the Eli 00F071 B valve condition per Section Xl Proqram 07-029. Valve body material is identical and acceptability of new valves is documented in ERE-35681 8. Tests Conducted:

Hydrostatic [ ] Pneumatic [ ] Nominal Operating Pressure [ X]Other [ I Pressure psi Test Temp.____Code Case N-416-2 OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10194)

I Form NIS-2 (Back)9. Remarks Replacement Valves were procured per PO# 4700147110.

ASME III Class 2, Grade CA-15,, Serial No.BH-145 for E1100F071B (V30-1826), and Serial No.BH-146 for E1100F072B (V30-1827), and ASME Code Data reports are attached.Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code, Section Xl.Type Code Symbol Stamp Oriqinal Code data report (N5-0307) to be supplemented by OwnersSection XI Proqram #09-003 Certificate of Authorization No. NIA- t Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer Date .2009Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected thecomponents described in this Owner's Report during the period .-16 -0" to _-.- o 9 .and state that to the best of my knowledge and belief, the Owner has performed examinations a'lnd taken corrective measures described in this Owner's Report in accordance with the requirements of the.ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions

'J Inspector's Signature National Board, State, Province, and Endorsements Date- / 2009 (10/94)For complete work packages, see Work Orders 25984301 and 25984079.

r~-f L FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES*As Required by the Provisions of the ASME Code,Section III, Division 1 2 Pg. 1 of _1. Manufactured and certified by Rowserve Corporation, 1900 South Saunders St. Raleigh, NC 27603 (name and address of N Certificate Holder)2. Manufactured for Detroit Edison Company PO Box 1659 Detroit, MI 48231 1659 (name and address of Purchaser)

3. Location of installation Enrico Fermi Unit 2 6400 Dixie Highway Newport, MI 48166 (name a d address)4. Model No., Series No., or Type 300 FW Drawing 0 8" 50294-01 Rev. A CRN N/A 5. ASME Code,Section III, Division 1: 1971 NO N154 (edition) (addenda date) (class) (Code Case no.)6. Pump or valve Valve Nominal inlet size 4 Outlet size 4 (in.) (in.)7. Material: (a) valve Body SA216WCB BonnetS9-1 6 WCB DiskSA216WCB Bolting SAI 93-137 (b) pump Casing Cover Bolting (a)Cert.Holder's Serial No.BHI145 BH146 /(b)Nat'l Board No.N/A N/A (c)Body/Casing Serial No.DFGF-1 DFGF-2.(d)Bonnet/Cover Serial No.HWAA-09X0050-1 HWAA-09X0050-2 (e)Disk Serial No.DFWP-2 DFWP-3* Supplemental information in the form of lists, sketches, or drawings may be used provided (1) size is 02/2 x 11, (2) information in items I through 4 on this Data Report is included on each sheet, (3) each sheet is numbered and the number of sheets is recorded at the top of this form."-7, FORM NPV-1 (Back -Pg. 2 of 2 .)BH14S thru BH146 Certificate Holder's Serial No.8. Design conditions 480 psi 335 °F or valve pressure class 300 (pressure) (temperature)

9. Cold working pressure 720 psi at 100'F I 10. Hydrostatic test 1100psi. Disk differential test pressure psi 11. Remarks: Bolting is as follows: Stud, SA1 93-B7, Ht. Code 880: Nut. SA 194-2H. Ht. Code 600 SO 50294, ITEM 1, SIZE 4, 300# FLEX WEDGE GATE VALVE; TAG #'s V30-1826 & V30-1827 CERTIFICATION OF DESIGN Lawrence D. Burr MI 33999 Design Specification certified by .RE. State Reg. no.Design Report certified by N/A P.E. State N/A Reg. no. N/A CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code,Section III, Division 1.

N Certificate of Authorization No. N-1562 Expires 11-2p-09 Date 9 Name Flowserve Corporation Signed ( .(N Certificate Holder.) (aut ized representative)

CERTIFICATE OF INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NC and employed by HSB CT of Hartford, CT have inspected the pump, or valve, described in this Data Report on-/ , and state that to the best of my knowledge and belief, the Certificate Holder has constructed this pump, or valve, in accordance with the ASME Code,Section III, Division 1.By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component described in this Data Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date I /11 Signed Commissions

_ _ _ _ _ __S SAuthorized Nuclear peco) j[Nat'l. Bd. (incl. endorsements) and state or prov. and no.)A 'lei t'-'

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI 09-004 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Address 2. Plant Fermi 2 Nuclear Power Plant Date Sheet'June 30, 2009 1 of 1 Unit 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance Address Detroit Edison Company Repair Organization P.O. No., Job No., etc.3. Work Performed by Name 6400 North Dixie Highway, Newport, Ml 48166 Type Code Symbol Stamp Authorization No.Expiration Date N/A N/A N/A Address (N5-0261 and N5-0307) Residual Heat Removal (Division

1) RHR Heat Exchanger 4. Identification of System 5. (a) Applicable Construction Code ASME III, Class 2/3 19 71 Edition (b) Applicable Edition/Addenda of Section Xl Utilized for Repairs or Replacements 19 6. Identification of Components Repaired or Replaced and Replacement Components W' 71 Addenda 192-92 Addenda N-154 Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)E1101BO01A Fromson Heat 70756B 2 N/A 1971 Replacement Y Transfer Description

7. of Work Install a complete replacement set of bottom flange bolting (studs and nuts) to facilitate component reassembly during RF13 after inspection and testing activities.

8. Tests Conducted:

Hydrostatic

[ ]Other[ ] Pressur Pneumatic

[ ] Nominal Operating Pressure [ X I Code Case N/A e psi Test Temp. _ _ F Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number. of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)

9. Remarks Replacement bolting material Stud Material, SA1 93, Grade B7, (21) procured per P0 # 988676, Trace Code 405C, and (33) procurred per P0 # 4700074915, Trace Code 1D43. Replacement Nuts, SA-1 94, Grade 7, (40) procured per PO# 4700074915, Trace Code 1D38, (12) were procured per P0 # 903580, Trace Code A200.Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code, Section XA.Type Code Symbol Stamp Original Code data report (N5-0261 and N5-0307) to be supplemented by Owners Section Xl Program #09-004 Certificate of Authorization No. NjA Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer Date .--..p- -2009 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected thecomponents described in this Owner's Report during the periodV.__..-

to '2 -.,'s'- oc , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions -" Inspector's Signature National Board, State, Province, and Endorsements Date '-' / 2009 (10/94)For complete work packages, see Work Orders B 134060100.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 09-005 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Date Sheet Unit, June 3,2009 1 of 1 Address 2. Plant Fermi 2 Nuclear Power Plant 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance Address Detroit Edison Company Repair Organization P.O. No., Job No., etc.3. Work Performed by Type Code Symbol Stamp Authorization No.Expiration Date N/A Name 6400 North Dixie Highway, Newport, MI 48166 N/A N/A 4. Identification of System Address N5-0245 and N5-0187 -Feedwater Line "A" (Inboard Isolation Check Valve)5. (a) Applicable Construction Code ASME Ill, Class 1 19 71 Edition (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or Replacements 19 6. Identification of Components Repaired or Replaced and Replacement Components W'71 Addenda92-92 Addenda N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)B2100F010A Atwood Morrill 2-763 N/A V12-2008 1974 Replacement Y Description

7. of Work Install replacement bonnet bolting material (Stud and nut) that was damaged duringq valve disassembly.

8. Tests Conducted:

Hydrostatic [ ] .Pneumatic

[]Other [X] .Pressure Nominal Operating Pressure [ X ]psi Test Temp._Appendix J Leak Test Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)9. Remarks:Replaced bonnet bolting damaged during valve disassembly.

Replace ment material is ASME Ill, Class 1, 1" Stud is SA-193, Grade B7, Heat #1 B17, 1" Nut is SA-194, Grade 2H, Heat # 1 B14. Both items procured per PO# 4700062335..

Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of theASME Code, Section Xl.Type Code Symbol Stamp Original Code data report N5-0245 and N5-0187 to be supplemented by OwnersSection XI Program 09-005.

Certificate of Authorization No. N/A t Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer .Date )t." ? ,2009 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period,/-/-5'-O to e, -P-e,2 ,and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.d:;z --C -"Commissions

__ _ __ _ _ _ _ _Inspector's Signature National Board, State, Province, and Endorsements Date 2009 (10/94)For complete work package, see Work Request B203090100 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI V 09-006 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Address 2. Plant Fermi 2 Nuclear Power Plant Name 6400 North Dixie Highway, Newport MI 48166 Address Date Sheet May 5, 2009 1 of 1 Unit 2 Deco Maintenance Repair Organization P.O. No., Job No., etc.3. Work Performed by Detroit Edison Company Name 6400 North Dixie Highway, Newport, MI 48166 Address Type CodeSymbol Stamp Authorization No.Expiration Date N/A N/A N/A 4. Identification of System (N5-0245)

Main Steam SuoolV)5. (a) Applicable Construction Code ASME Ill, Class 1 19 68 (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or Replacements N-240,.N32-4 N316 N237, N274, N275 Code Case Edition Draft Addenda 1992-92 Addenda 6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)V17-2001 Atwood-Morril 6-682 N/A B2103F022B 1971 Replacement Y 7.Description of WorkRemoved and replaced the existing inbody satellite seat which had cracks in the satellite material.

The existing seat was machined down to the carbon steel base material.

A carbon steel weld overlay was then applied, followed by the application of satellite hardfacing.

The satellite was then machined to final manufacturing tolerances and to match the poppet. In addition, several studs and nuts that were damaged during the disassembly process were replaced, the valve stem was replaced, and the gasketed seal surface was machined to provide a good seal and to meet manufacturing tolerances.

8. Tests Conducted:

Hydrostatic [ ]Pneumatic

[.] Nominal Operating Pressure [ X ]Other [ X]I Pressure psi Test Temp. -'F (Appendix J Seat Leakage Test)Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11. in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10194)

Form NIS-2 (Back)

9. Remarks Replacement bolting material procured Der the followino PO#'s (4) 2" studs -SA1 93 Gr B7 Heat Code #89712PO# 686582, and (6) 2" Nuts -SA1 94, Gr. 7, Heat Code #8960108, Trace #R800, PO#912130.

A replacement stemwas also installed that was procured pe PO# 4700222688 A564 Gr. S17400 (630), HT. #:47068, S/N: H7774-6 Applicable Manufacturer's Data Reports to be attached-CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair/Replacement conforms to the rules of the ASME Code, Section XA.Type Code Symbol Stamp Oriqinal Code data report (N5-0245) to be supplemented by OwnersSection XI Program #09-006 Certificate of Authorization No. N/A Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer -Date 2009 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigqan and employed by HSB CT ofOne State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period" to 5ý-2 /- 6ý'9 , and state that to the best of myknowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_______-.

________-_________

Commissions__'

____--'________

Inspector's Signature National Board, State, Province, and Endorsements Date .t y t/'2009 (10/94)For complete work packages, see Work Orders 26320349 and 29684245.-I FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 09-007 1. Owner Detroit Edison Company Name 6400 North Dixie Hiahwav, Newport M1 48166 Date Sheet Unit June 3,2009 1 of 1 Address 2. Plant Fermi 2 Nuclear Power Plant 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance Address Detroit Edison Company 3. Work Performed by Repair Organization P.O. No., Job No., etc.Type Code Symbol N/A Stamp Authorization No. N/A Expiration Date N/A Name 6400 North Dixie Highway, Newport, MI 48166 Address 4. Identification of System N5-0214 -Feedwater Line "B" (Outboard Isolation Check Valve)5. (a) Applicable Construction Code ASME Ill, Class 1 19 71 Edition W'71 (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or Replacements 1992-92 Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Addenda N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)B2100F032B Anchor Darling IN-081 N/A V12-2003 1974 Replacement Y Description

7. of Work Install reolacement stuffino box in valve durino RF1 3 due to normal wear identified on this valve oart durina routine inspections.

This valve is disassembled for inspection every 3 refueling outages 8. Tests Conducted:

Hydrostatic [ ] Pneumatic

[I Nominal Operating Pressure [ X ]Other [ ] Pressure _ psi Test Temp._Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 1I in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10194)

Form NlS-2 (Back)9. Remarks: Replacement stuffing box that was procured per PO# 394616, ASME III -Class 1, SA-105, Heat Code #21211.Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE-We certify that the statements made in the report are correct and this Replacement conforms to the rules of theASME Code, Section Xl.Type Code Symbol Stamp Original Code data report N5-0214 to be supplemented by Owners Section XA Program 09-007.Certificate of Authorization No. ULA I Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer Date 2009 S Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period .o & -A--9 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,'Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Repoft. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

______________________

Commissions_,,_,________,___

Inspector's Signature National Board, State, Province, and Endorsements Date 2009 (10/94)For complete work package, see Work Request T251090100 09-008 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI 09-010 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport Ml 48166 Date Sheet Unit May 5, 2009 1 of 2 Address 2. Plant Fermi 2 Nuclear Power Plant Name 6400 North Dixie Highway, Newport MI 48166 2 Deco Maintenance

3. Work Performned by Address Detroit Edison Company Repair Organization P.O. No., Job No., etc, Type Code Symbol N/A Stamp Authorization No. N/A Expiration Date N/A Name 6400 North Dixie Highway, Newport, Ml 48166 Address 4. Identification of System (N5-0356)

Standby Liguid Control Pump Discharge 5. (a) Applicable Construction.Code ASME Ill, Class 1 19 71 Edition W' 71 Addenda (b) Applicable Edition/Addenda of Section Xl Utilized for Repairs or Replacements 1992-92 Addenda 6. Identification of Components Repaired or Replaced and Replacement Components N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)C4100F007 Anchor Darling E2062-1-2 N/A VR4-2037 1983 Replacement*

Y Description 7 of Work Obtained and installed only a replacement disc with an integral soft seat since valve was disassembled forscheduled maintenance. Replacement of iust the soft seat was not an option, due to the small size of the disc (1-1/2").

Also replaced all 4 side cover nuts since 2 different sizes had been used in the past ,aswell as pressure seal bonnet studs and nuts which aren't considered pressure retaining parts.8. Tests Conducted:

Hydrostatic

[ ] Pneumatic

[]Other[X] Pressure Nominal Operating Pressure [ X ]psi Test Temp. OF Seat leakage (Appendix J)Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)

9. Remarks Replacement Disc procured per PO# 283778. ASME III Class 1, SA479-S34700, Trace Code: A906, SN-5.

ASME Code Data report is attached. Replaced 4 side cover nuts, SA194 Grade 2H procured per P.O #4700205458, HeatCode# 8868448

/ 2P08 Applicable Manufacturer's Data Reports to be attachedCERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code, Section Xl.Type Code Symbol Stamp Original Code data report (N5-0356) to be supplemented by OwnersSection XI Program #09-008 and #09-010.Certificate of Authorization No. N/A N Expiration Date N/A Signed R.M. Hambleton Lead ISI EngineerQ Date V ,009 Owner or Owner's Designee, TitleCERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected thecomponents described in this Owner's Report during the penod5_<76o0, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XA.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

___Commissions

" Inspector's Signature National Board, State, Province, and Endorsements Date 2009 (10/94).For complete work package, see Work Orders.G428090100.

U..- -W ~ ~ ........wa W<xv..::.Div I -L (a) ,mm-isc.d by Anchor/Darling Valve Co., 701 First St., Williamsport, PA 17701 I mewamMV o T CWU6S84 Holds""w Detroit Edison, P.O. Box 1659, Detroit. MI 48231 I dv E CaUmaue K .be e&~ sw em se w eIk mm L ae u uHodrs 4 & 5 Nac'lB.LNo.

N/A (a) 4 Q C31282 R!- DiPredby Anchor/Darling Valve Company (j Doe pcimm pan jsp'ectad Disc w/WliCr Trace Code: A906 SA479-S34700 (c)

A.WE Secti LL1, Edince 1980 "2dL.... Addend '82 , Case No. JLc C 3. Spare Part(s) for i 1/2"-900#

Swing Check Valve (oftud lewit"Woa ai awwtq. gow wtacb eomps~w waa 406iaqasd)

A/DV S.0. and Item No.: P-W993-1 No Performed We ca.uifT&S tbat the ,tin.s --de in &his report are correit &and this vessel part at appurtenance as detfined in ebe Code coo-f~amas to the mies .4 coasmrctic=

of the AS4L Code Sectioni Ill.(The a99iea~bke D-SeeltIeauol anld Surml Report ame riot the Meponsibiljly al' the NPT Certlflcam Hoider for part. An, NPT Cer~tf.kmw Hoidgr (or' &0VMt~Ce&nuis respoemblie for fiwmsltung a sepamue Dcmgn Spcrificdaton and Stres Repon if the apponeamcc is not Uteald-ed InthUe c.omoet Desam Speoclation amd Suess Report.)~ Anchor/Darling Valve Co.By Cortricaeas of Asidiaoxtiziom Expires 4/59 Certifcate of Authoriatica No.71 F CERTIFICATION OF DE-SIGN FOR APPURTENANCE (when applicable)

DesioWmazatam(Leam a e __ _ _ _ _ _ _ _ _ _Dewisn specj4 cewoas cextifle'd b ______________Prof.

Eag. State Reg. No.Suess mealsicai imp"e celarsfed P Praf. Estg. Sc ame Itg. No.f ~CERTIFICATE OF SHOP INSPECTION

1. tho aweslgmei.

holdia a vahd Comaam aaim i*sued bry Ch*e Natioeam Board of Sailas mavi Ptesmoc* Vessel La spectars.seaw WtheSseaftOXrxooxceof Pcn ns yIva n ia Cnanloe onmmercial Union Insurance Company_B0 8Otonl _'Ma SS -A&w iasoec~d the past of a picaare weasel described in this Peifea Deog 1etow1 an q2 V-ZV-~f~

-IS_ and state 0,11toto Ue begn of my kaowkfedg sa" be"A.. t"e MP? Ce "tHolder has coeMicte hi si parct In aCCOswlance with the ASME Code SOCODflnitl.

by alisaig *his 'Crtificasr, atehe the Iampectot not his einployer makes ay warraerf, exprecss" at immied. coecera-ins thm, part doscribad in this Partial Data Report. fuarthermore, neither the trnapector nor his employer ms"a be li*W* i ma-y Masmar for a"y persoeai tiwly or propemt damage at a lossato any kind maiming from or coanectrd~

Cosmvssazooa Pennsylvania 2392 rilavm' Based. Stage. PrOV04"s (10/771This fotn" 1EVOO4o0In.iy ae oolmoned fromn tri Ortar Oeot.. ASME. 345 E. 47th, St., Now York. P4.Y. 10017 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

!As Required by the Provisions of the ASME Code Section XI 09-009 1. Owner Detroit Edison Company Name 6400 North Dixie Hiqhway, Newport MI 48166.Date Sheet May 6, 2009.1 of 1 Address 2. Plant Fermi 2 Nuclear Power Plant Unit 2 Name 6400 North Dixie Highway, Newport MI 48166 Deco Maintenance Address Detroit Edison Company 3. Work Performed by Repai Type Code Symbol Stamp Authorization No.Expiration Date r Organization P.O. No., Job No., etc.N/A Name 6400 North Dixie Highway, Newport, Ml 48166 N/A N/A Address HPCI Steam Turbine (N5-0325)

Piping System (Steam Supply)4. Identification of System 5. (a) Applicable Construction Code ASME III Cl 2 19 71 Edition W'71 Addenda N/A Code Case (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or 1992-92 Addenda Replacements

6. Identification of Components Repaired or Replaced and Replacement Components, Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes"_ _or No)E41 01 C002 Terry Turbine 4-36688-A N/A HPCI Turbine 1974 Replacement N Description

7. of WorkReplaced casing studs damaged during turbine disassembly.

8. Tests Conducted:

Hydrostatic

[ ] Pneumatic

[] Nominal Operating Pressure [ X Other [ ] Pressure psi Test Temp. 0 F Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 1I in., (2) informa-tion in items .1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10194)

Form NIS-2 (Back)9. Remarks: Replacement bolting material procured per PO# 4700224758 (2) 1-1/4" Double end studs, SA-193 Gr.

B7, Heat Code #2V85.Applicable Manufacturer's Data Reports to be attached.CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code,Section XI.Type Code Symbol Stamp Original Code Data Report N5-0325 and to be supplemented by OwnersSection XI Prog ram 09-009.Certificate of Authorization No. NLA t Expiration Date_ N/A Signed R.M. Hambleton Lead SI Enqineer Date e- 2009 Owner or Owner's Designee, Tide CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michiqan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected thecomponents described in this Owner's Report during the period: ý,5i., 5to 5 .-o 2 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personalinjury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions

__________________

Inspector's Signature National Board, State, Province, and Endorsements Date , 2, -2009 (10/94)For complete work package, see Work Request # 25980121.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI i K-09-011 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Date Sheet Unit May 18, 2009 1 of 1 Address 2. Plant Fermi 2 Nuclear Power Plant Name 6400 North Dixie Highway, Newport MI 48166 2 Deco Maintenance

3. Work Performed by Address Detroit Edison Company Repa Type Code Symbol Stamp Authorization No.Expiration Date ir Organization P.O. No., Job No., etc.N/A N/A Name 6400 North Dixie Highway, Newport, MI 48166 Address N/A 4. Identification of SystemT & B N5-22 & Wismer Becker N5-0284 (RHR Service Water (RHRSW)5. (a) Applicable Construction Code ASME Ill, Class 3 19 71 Edition (b) Applicable Edition/Addenda of Section XA Utilized for Repairs or Replacements 19 6. Identification of Components Repaired or Replaced and Replacement Components "71 Addenda92-92 Addenda NIA Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)E1100F012B William Powell 64162-2 N/A V15-2005 1975 Replacement Y______________________

_____________

L L L ____________

A. ________Description

7. of Work Installed Replacement Boltinq for valve body/bonnet connection.

8. Tests Conducted:

Hydrostatic

[ I Other[ ] Pressur Pneumatic

[I Nominal Operating Pressure [ X I e_ psi Test Temp._ _F Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10194)

Form NIS-2 (Back)9. Remarks: Replacement bolting material (16)- -4" studs, SA193, Grade B7, Heat Code #642A, PO# 986829. (32) -YW" Nuts SA-194, Grade 2H, Heat Code #1 54C, PO# 985892 and Heat Code #1 B48, PO# 4700057923.

Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code, Section XA.Type Code Symbol Stamp Original Code data reports to be supplemented by OwnersSection XI Program 09-011.Certificate of Authorization No. NExpiration Date N/A Signed R.M. Hambleton Lead ISI Engineer Date v2009 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period_/-c,5 to "' -/ o , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

______________________________

Commissions , : Inspector's Signature National Board, State, Province, and Endorsements Date 2009 (10/94)For complete work package, see Work Request 29205488.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl 09-012 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Date Sheet Unit May 19,2009 1 of 2 Address 2. Plant Fermi 2 Nuclear Power Plant Name 6400 North Dixie Highway, Newport MI 48166 2 Deco Maintenance Address Detroit Edison Company 3. Work Performed by Repai Type Code Symbol Stamp Authorization No.Expiration Date r Organization P.O. No., Job No., etc.N/A Name 6400 North Dixie Highway, Newport, MI 48166 Address N/A N/A 4. Identification of System P44 -Emergency Eqyipmenrt Cooling Water (N5-0013 and N5-0352)5.- (a) Applicable Construction Code ASME Ill, Class 3 19 71 Edition W'71 Addenda (b) Applicable Edition/Addenda of Section Xl Utilized for Repairs or Replacements 1992-92 Addenda 6. Identification of Components Repaired or Replaced and Replacement Components N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)P4400F972A C & S Valve 92-1953-01(N)-01 N/A V30-6064 1992 Replaced Y P4400F972A C & S Valve 91-1551-01 (N)-01 N/A V300050 1992 Replacement Y Description

7. of Work Install replacement check valve dur RF1 3 due to internal binding and seat leakage problems with originally installed valve. Valve is seat leakaoe tested as oart of an inteorated system leakaae test.

8. Tests Conducted:

Hydrostatic

[ ] Pneumatic

[] Nominal Operating Pressure [ X ]Other [ I Pressure _ psi Test Temp.Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10194)

Form NIS-2 (Back)9. Remarks: Replacement valve procured per PO# # 249441.Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of theASME Code,Section XI.Type Code Symbol Stamp Original Code data report N5-0013 and N5-0352 to be supplemented by OwnersSection XI Program 09-012.Certificate of Authorization No. I Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer Date e, 2009 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected the components described in this Owner's Report during the period q- 7 0 -c to --2-4 -0 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taker corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions Inspector's Signature National Board, State, Province, and Endorsements Date 2-O 2009 (10/94)For complete work package, see Work Request 29649872 FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVES*As Required by the Provisions of the ASME Code,Section III, Division 1 Pg. 1 of2c 1. Manufactured and certified by C&S Valve Carpany, Tricentric Division; 40 Chestnut Ave.; IL 60559 (name and address of N Certificate Holder)2. Manufactured for Detroit Edison, 2000 Second Ave.; Detroit, Michigan 48226 (name and address of Purchaser)

3. Location of installation Detroit Edison, EF2-Site; 6400 Dixie Highway; Newport, Michigan 48166 (name and address)Check K 91-1551-01(N)

A_____ WA___4. Model No., Series No., or Type Drawing Rev. A CRN_ N/A 5. ASME Code,Section III, Division 1: 1971 Surmnr 1973 3 N/A (edition) (addenda date) (class) (Code Case no.)________4" 4"______6. Pump or valve Valve Nominal inlet size_ _ Outlet size 4" (in.) (in.)7. Material:

Body M 351 G. CFEM Bonnet WA .Disk SA 351 GR. CFP BotingSee Backside of Page (a)Cert.Holder's Serial No.91-1551-01(N)-

01 (b)Nat'l Board No.NA (c)Body Serial No.Hea. 15691 S/N: A60 (d)Bonnet Serial No.N/A (e)Disk Serial No.Heaet 16581 SIN'S: A380 & A381*Supplemental information in form of lists, sketches, or drawings may be used provided (1) size is 81/ x 11, (2) information in items 1 through 4on this Data Report is included on each sheet. (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(12/88) This form (E00037) may be obtained from the Order Dept., ASME, 22 Law Drive. Box 2300. Fairfield, NJ 07007-2300.

FORM NPV-1 (Back -Pg. 2 of 2. )Certificate Holder's Serial No. 91-1551-01(N)-

c"1 8. Design conditions 275 psi 100 -IF or valve pressure class 150 (pressure) (temperature)

9. Cold working pressure 275 psi at 100F" 10. Hydrostatic test 425 psi. Disk differentia.1 test pressure 305 psi 11. Remarks: CteCk BaCkflow stop Pin Retainer -tFhtea-ai SA 182 (A. P3 16 Het lc1e: ML Hinge Pin Retainer -m~'aterial SA 162~ CR. F3 l6 Hmit (..cE=71i CERTIFICATION OF DESIGN Design Specification certified by Ronald I. Adler P.E. State Michigan Reg. no. 28412 Design Report certified by N/R P.E. State --- Reg. no. ---CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this pump or valve conforms to the rules for construction of the ASME Code,Section III, Division 1.N Certificate of Authorization No. N-2724 Expires 9 tU -! -4 .Date t) Ir\ f. -Name C&S Valve Carpany, Tricentric Div. Signed IN Certificate Holder)ck~) o~<r.-athorized representative)

CERTIFICATE OF INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of I-linoiS and employed by Allendale Mial Ins. Co.of Norwood, Massachusetts have inspected the pump, or valve, described in this Data Report on/10 /-i-- 5;/ , and state that to the best of my knowledge and belief, the Certificate Holder has con-structed this pump, or valve, inaccordance with the ASME Code,Section III, Division 1.* Factory Mitual Systen By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or implied, concerning the component described in this Data Report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date Signed Commissions Al/ vý6/,R' L, / 4'f g, ;A- iz .C (Au/Iorized Inspector) (Nat'l. Bd. (incl. endorsements) and state or prov. and no.)(1) For manually operated valves only.X.09-013 09-014 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the Provisions of the ASME Code Section XI 1. Owner Detroit Edison Company Name, 6400 North Dixie Highway, Newport MI 48166 Date Sheet Unit May 5, 2009 1 of 3 Address 2. Plant Fermi 2 Nuclear Power Plant Name 6400 North Dixie Highway, Newport MI 48166 2Deco Maintenance Address Detroit Edison Company 3. Work Performed by Repair Organization P.O. No., Job No., etc.Type Code Symbol N/A Stamp Authorization No. N/A Name 6400 North Dixie Highway, Newport, M1 48166 Address Expiration Date N/A 4. Identification of System (N5-0356)

Standby Liauid Control PumD Discharae 5. (a) Applicable Construction Code ASME Ill, Class 1 & 3 19 71 Edition W' 71 Addenda (b) Applicable Edition/Addenda of Section XI Utilized for Repairs or Replacements 1992-92 Addenda6. Identification of Components Repaired or Replaced and Replacement Components N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped (Yes or No)C4100F029A Crosby N56803-00-0004 N/A V22-2029 1975 Replaced Y C4100F029A Anderson N56803-00-0007 N/A V30-2050 2008 Replacement y Greenwood-V30-2051 Crosby C4100F029B Crosby N56803-00-0002 N/A V22-2030 1975 Replaced Y C4100F029B Anderson N56803-00-0008 N/A V30-2050 2008 Replacement Y Greenwood-V30-2051 Crosby Description

7. of Work Obtained replacement relief valves from stock and modified inlet and outlet connections by the installation of piping and flanges to allow for installation in system and performed setpoint teating.8. Tests Conducted:

Hydrostatic

[ ]Other[X] Pressur Pneumatic

[ ] Nominal Operating Pressure [ X ]e Code Case N-416-2(Setpoint Testing)

_ psi Test Temp._ _F Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.(10/94)

Form NIS-2 (Back)9. Remarks Replacement Valves were procured per PO# 4700037578.

ASME III Class 3, Serial No.N56803-0007 and N56803-0008. ASME Code Data reports are attached.

1" SW 600# RF Piping Flanges were procured per PO#

4700214099, SA-182 Gr. F316,. 2" SW 150# RF Piping Flanges were procured per PO# 4700214099, SA-182 Gr.F316. 1" Pipe was also procured per PO# 4700214099, SA312 Type 304, Schedule 80, Heat #514040 2" Pipe was also procured per PO# 4700214099, SA312 Type 304, Schedule 80, Heat #2P639 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code, Section XA.Type Code Symbol Stamp Original Code data report (N5-0356) to be supplemented by OwnersSection XI Program #09-013 and #09-014.Certificate of Authorization No. N/A Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer 'LUA 3?j ) Date 2009 Owner or Owners Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Street, Hartford, CT 06102 have inspected thecomponents described in this Owner's Report during the period Y-Z7-09 to .'-/?-z-V , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinationsand corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

/A ..Commissions________________________.Inspector's Signature National Board, State, Province, and Endorsements Date -z, , /,. 2009 (10/94)For complete work packages, see Work Orders 29430317 and 29430987 for shop work and 25981870 and25981894 for field installations.

FORM NV-1 FOR SAFETY AND SAFETY RELIEF VALVES As required by the Provisions of the ASME Code Rules DATA REPORT Q.C.-44C-1 Sheet 1 of 2#315-7 Foe-M 52M,03 3T 1. Manufactured By Anderson Greenwood Crosby, 43 Kendrick St., Wrentham, MA 02093 Name and Address Model No. JMB-45-WR-S Order No. G157420000 Contract Date 8/8/2007 National Board No. ---TYPE B 2. Manufactured For DETROIT EDISON CO. Order No. 4700037578 Name and Address 3. Owner DETROIT EDISON CO.Name and Address 4. Location of Plant FERMI POWER PLANT 2 -MI 5. Valve Identification V30-0250, V30-0251 Serial No. N56803-00-0007 Drawing No. DS-C-56803 REV.- C Type SAFETY RELIEF Orifice Size .296 Pipe Size --- Inlet 1 Outlet 2 Safety, Safety Relief, Pilot, Power Actuated Inch Inch Inch 6. Set Pressure (PSIG) 1370 150 0 F Rated Temperature Stamped Capacity 40 GPM WTR-@ 70 DEG.F @ 10 % Over'pressure Blowdown (psig) 10% OF S.P..Hydrostatic Test (PSIG) Inlet 2100 Complete Valve 100 7. The material, design, construction and workmanship comply with ASME Code,Section III.Class 3 Edition 1971 Addenda Date SUMMER 1972 Case No. N/A Pressure Containing or Pressure Retaining Components

a. Castings Body Bonnetb. Bar Stock and Forgings Support Rods Nozzle Disc Spring Washers Adjusting Bolt Spindle Serial No.Identification N90152-09-0265 N88830-80-1118 N88830-80-1128 N88829-43-0128 N89494-54-0057 Material Specification Including Type or Grade STELLITE'~1 ASTM A 479 TYPE 316 ASTM A 479 TYPE 316 ASTM A 479 TYPE 316/.!

Q.C.-44C-1 N56803-00-0007 Sheet 2 of 2 Form NV-1 (Back)Certificate Holder's Serial No.c. Spring d. Bolting e. Other Parts such as Pilot Components Serial No.Identification, NX2799-0057Material Specification.

Including Type or Grade ASTM A313 TYPE 316 Base N90596-36-00.12 ASTM A479 TYPE 316 Cylinder N90597-34-0008 ASTMl A351 GR. CF8M We certify that the statements made in this report are correct.Anderson Greenwood Crosby ___ _ _ _, _Date ,4 I. 20 o a Signed Wrentham, MA B Manufacturer Certificate of Authorization No. N-1878 Expires 30-Sep-10 Date CERTIFICATE OF SHOP INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MA and employed by HSB -CT have inspected the equipment described in this Data Report on/ -200 D and state that to the best of my-knowledge and belief, the Manufacturer has constructed this equipment in accordance with the applicable Subsections of ASME Section III.By signing this certificate, neither the Inspector nor his employer makes any warranty , expressed or implied, concerning the equipment described in this Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection..

Date )S-," 200 8 Commissions MA-1420 A, N, I Ntu naA.J -Ja tt. 1), "-A ... Nd",.-F'r.I'.4-FORM NV-1 FOR SAFETY AND SAFETY RELIEF VALVES As required by the Provisions of the ASME Code Rules DATA REPORT Q.C.-44C-1 Sheet 1 of 2 t, s-LPP 1. Manufactured By Anderson Greenwood Crosby, 43 Kendrick St., Wrentham, MA 02093 Name and Address Model No. JMB-45-WR-S Order No. G157420000 Contract Date 8/8/2007 National Board No. _ __TYPE B 2. Manufactured For DETROIT EDISON CO. Order No. 4700037578 Name and Address 3. Owner DETROIT EDISON CO.Name and Address 4. Location of Plant FERMI POWER PLANT 2 -MI 5. Valve Identification V30-0250, V30-0251 Serial No. N56803-00-0008 Drawing No. DS-C-56803 REV. C Type SAFETY RELIEF Orifice Size .296 Pipe Size --- Inlet I Outlet 2Safety, Safety Relief, Pilot, Power Actuated Inch Inch Inch 6. Set Pressure (PSIG) 1370 150 0-F Rated Temperature Stamped Capacity 40 GPM WTR @ 70 DEG.F @ 10 % Overpressure

-- Blowdown (psig) 10% OF S.P.Hydrostatic Test (PSIG) Inlet 2100 Complete Valve 100 7. The material,, design, construction and workmanship comply with ASME Code,Section III.Class -3 Edition 1971 Addenda Date SUMMER 1972 Case No. N/A Pressure Containing or Pressure Retaining Components

a. Castings Body Bonnet b. Bar Stock and Forgings Support Rods Nozzle DiscSpring Washers Adjusting Bolt Spindle Serial No.Identification N90152-09-0264

/N88830-80-1115

-N88830-80-1126 J N88829-43-0127 J N89494-54-0058

.Material Specification Including Type or Grade till'STELLITE ASTM A 479 TYPE 316 ASTM A 479 TYPE 316 ASTM A 479 TYPE 316//I Q.C.-44C-1 N56803-00-0008 Sheet 2 of 2 Form NV-1 (Back)Certificate Holder's Serial No.c. Spring d. Bolting e. Other Parts such as Pilot Components Serial No.Identification NX2799-0056

.." Material Specification Including Type or Grade ASTM A313 TYPE 316 Base N90596-36-001 1 ASTM A479 TYPE 316 Cylinder N90597-34-0007 ASTM A351 GR. CF8M We certify that the statements made in this report are correct.Date 0~~Jq~)20 ~ Sined Anderson Greenwood Crosby Date ,25-7,,q1V 20 o Signed Wrentham, MA By _ManufacturerCertificate of Authorization No. N-1878 Expires 30-Sep-10 Date CFRTTFT ATF FqT-1 P 11VSP CTTONT I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MA and employed by HSB -CT have inspected the equipment described in this Data Report on20 0 and state that to the best of my knowledge and belief, the Manufacturer has constructed this equipment in accordance with the applicable Subsections of ASME Section III.By signing this certificate, neither the Inspector nor his employer makes any warranty , expressed or implied, concerning the equipment described in this Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date J T 200 8 Commissions MA-1420 A, N, I /r 4tisfector)(National Board, State, Province and No.) ',

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 09-016 1. Owner Detroit Edison Company Name 6400 North Dixie Highway, Newport MI 48166 Date Sheet July 9, 2009/1 of 1.2 Address 2. Plant Fermi 2 Nuclear Power Plant Name 6400 North Dixie Highway, Newport MI 48166 Unit Deco Maintenance

3. Work Performed by Address Detroit Edison Company Repair Organization P.O.

No., Job No., etc.Type Code Symbol N/A Stamp Name 6400 North Dixie Hiqhway, Newport, Ml 48166 Authorization No.Expiration Date N/A N/A, Address 4. Identification of System N5-01 3 (T&B) Emergency Diesel Generator # 11 5. (a) Applicable Construction Code ASME Il1, Class 3 19 71 Edition (b) Applicable Edition/Addenda of Section Xl Utilized for Repairs or Replacements 19 6. Identification of Components Repaired or Replaced and Replacement Components "71 Addenda 92-92 Addenda N/A Code Case Name of Name of Manufacturer Serial National Other Year Repaired, .. ASME Component Manufacturer No Board Identification Built Replaced, .Code No. or Replacement Stamped (Yes or No)R3001B025 American Stnd.

5-20002-02-4 26207 Air Coolant 1974 Repair Y Ht. Ex.R30011B002 American Stnd. 5-20002-03-4 26213 Lube Oil 1974 Repair Y Ht. Ex.R3001B017 American Stnd. 5-20002-04-4 26217 Jacket Cooling 1974 Repair Y Ht. Ex.Description

7. of Work Perform welded repairs to Heat Exchaneer Channels caused bh eittino erosion. Reoairs were rerformed on the inside surfaces of the channels at both ends of the heat exchangers at several locations.

8. Tests Conducted:

Hydrostatic [ ] Pneumatic

[] Nominal Operating Pressure [ X ]Other [ I Pressure _ psi Test Temp.__Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 8 1/2 in. X 11 in., (2)information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

(10/94)

Form NIS-2 (Back)9. Remarks: None Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of theASME Code,Section XI.Type Code Symbol Stamp Original Code data report N5-013 to be supplemented by Owners Section Xl Program 09-016 Certificate of Authorization No. .N/A Expiration Date N/A Signed R.M. Hambleton Lead S] Engineer Q!jk. Date 9Ak5)' q ,20 09, Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State. Street, Hartford, CT 06102 have inspectedthe components described in this Owner's.Report during the period-52,/-, -5 to '7- / (' -0 9 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl." By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

________________

Commissions 26.. '/Inspector's Signature National Board, State, Province, and Endorsements Date 20., --y 7 7/D (10/94)For complete work~package, see WorkOrder 29101808

NRC-09-0038, Fermi 2 - Summary Report of the 2009 Inservice Inspection Activities

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1.0 INTRODUCTION

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NRC-09-0038, Fermi 2 - Summary Report of the 2009 Inservice Inspection Activities

Text

Reference:

Subject:

SUMMARY

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SUMMARY

1.0 INTRODUCTION

SUMMARY

SUMMARY

SUMMARY

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SUMMARY

SUMMARY

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