NRC-03-0061, Inservice Inspection Summary Report

Inservice Inspection Summary Report

ML032340342
Person / Time
Site:	Fermi
Issue date:	08/08/2003
From:	Cobb D Detroit Edison
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-03-0061
Download: ML032340342 (282)

Text

- -T - I Fermi 2 6400 North Dixe Hwy., Newport, MI 48166 Detroit Edison 10CFR50.55a August 8, 2003 NRC-03-0061 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001

Reference:

Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

Subject:

Inservice Inspection Summary Report Enclosed is the Summary Report of the 2003 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 Ninth Refueling Outage, which was completed on May 10, 2003.

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 1992 Edition, including the 1992 Addenda, for IWE inspections.

Should you have any questions or require additional information, please contact Mr.

Norman K. Peterson, Manager - Nuclear Licensing, at (734) 586-4258.

Sincerely, Donald K. Cobb Director - Nuclear Production Enclosure cc: H. K. Chernoff M. A. Ring NRC Resident Office Regional Administrator, Region III M. Wilson - ANII {l -7 R. Aben Chief Inspector, Michigan Dept. of Labor Bureau of Construction, Codes/Boiler Division ADTE Energy Company

Sheet 1 of 1 FORM NIS-1 OWNERS' DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner Detroit Edison Co.. 2000 2nd Ave.. 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 Summnar 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 NIANIA Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided(l) 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 i of I FORM NIS-1 (back)

8. Examination Dates 3/28/03 to 5/10/03

9. Inspection Interval from 02/17/00 to 02/17/10

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 2, Refuel Outage Nine (RF-09), is included in the ISI Summary Report of the 2003 Inservice Inspection, Section 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 and corrective measures taken conform to the rules of the ASME Code,Section XI.

Date ao lsA2003 Signed Detroit Edison Co. By.

Owner Lead ISI Engineer Certificate of Authorization No. (if applicable) N/A Expiration Date N/A CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province Michigan of 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 2/27/02 to 5/10103 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners' Data Report. 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 " ge - ZZ 2003 Signedi g ComrCissions C; c(Z Inspector's Signature" State, Province

ISI

SUMMARY

REPORT OF THE 2003 INSERVICE INSPECIION at Fermi 2 Nuclear Power Plant 6400 N. Dixie Highway Newport, MI 48166 Detroit Edison Company 2000 2nd Avenue Detroit, MI 48226 Commercial Service Date: January 23, 1988 NB# 21085 (RPV)

Michigan Boiler Serial Number M345962M To:

U. S. Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Prepared by:.

Marc A. Brooks Lead ISI Engineer, NDE Program Level El[

Reviewed by: &A 19103 Richard M. Hambleton Lead ISI Engineer, RVIM Program Level m Reviewed by:

James Aorson Supervisor, ISI Approved by:

Tom Dong Manager, Performance Engineering-Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48166 - - -

Fermn-2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NB# 21085 (RPV) - ' .

TABLE OF CONTENTS I Section I Description I Page(s) l 1 MTRODUCMION 1-7 2

SUMMARY

OF ASME CLASS 1 & 2 AND AUGMENTED EXAMINATIONS 8-33 3

SUMMARY

OF REACTOR INTERNAL EXAMINATIONS 34 -40 4

SUMMARY

OF COMPONENT SUPPORT EXAMINATIONS 41 -43 5 ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE ACTIONS TAKEN 44 - 56 5.1 REFUEL-09 5.2 REFUEL-08 5.3 REFUEL-07 5A REFUEL-06 5.5 REFUEL-O5 5.6 REFUEL-04 5.7 REFUEL-03 5.8 REFUEL-02 5.9 REFUEL-01 6 PROGRAM STATUS, ASME SECTION XI CREDIT - IWB, IWC, & IWF 57 - 85 7 UPDATED PROGRAM TABLES 86 - 98 ENCLOSED PROGRAM TABLES TABLE A - (32 pages)

TABLE B - (9 pages) 8

SUMMARY

OF CONTAINMENT INSPECTIONS (IWE)99-105 9 SECTION XI REPAIR/REPLACEMENT NIS-2 FORMS INDEX 106 - 109 (Fonns Attached - Note NIS-2 forms are double sided)

SECTION 1 INTRODUCTION Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48166 Ferml-2 Nuclear Power Plant, 6400 N. Dixie Hlighway, Newport, Ml 48166 Comnmercial Service Date: 1-23-88 NBNo. 21085 (RPV)

I

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.

Fermi 2 - Program B (ASME Section XI, IWA-2420):

First Inspection Interval (1980-W'81 addenda) (01/23/88 - 02J16100)*

1. First Inspection Period (01/23/88 - 06/10/91)

a. First Refueling Outage (09/03/89 - 12/16/89)

b. Second Refueling Outage (03/30/91 - 06/10/91)

2. Second Inspection Period (06/11/91 - 01/03/95)

a. Third Refueling Outage (09/12/92- 11/07/92)

b. Fourth Refueling Outage (04/12/94 - 01/03/95)*

3. Third Inspection Period (01/03/95 - 12/31/98)*

a. Fifth Refueling Outage (09/27/96 - 01/03/97)

b. Sixth Refueling Outage (09/07/98 - 10/29/98)

Second Inspection Interval (1989 Edition) (02/17/00 - 02/17/10)*

1. First Inspection Period (02/17/00 - 03/27/03)

a. Seventh Refueling Outage (04/01/00 - 05/23/00)

b. Eighth Refueling Outage (10/22/01 - 11/30/01)

2. Second Inspection Period (03/28/03 - Prior to RF-1 1, Fall 2006)

a. Ninth Refueling Outage (03/28/03 - 05/10/03)

• 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 rWA-2430. The second inspection interval may be shortened by one year to maintain the interval pattern as required in IWA-2430(d).

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48166 Fennl-2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, Ml 48166 Connercial Service Date: 1.23-88 NBNo. 2108S (RPV) 2

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

• American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XL 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 Guidelinqs 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, 5.1 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., 2000 2nd Ave., Detroit, AG 48166 Fermi-2 Nuclear Power Plant, 6400 N. Dbde Highway, Newport, Ml 48166 Connmercial Service Date: 1-23-88 NBNo. 21085 (RPV) 3

TABLE A REQUIREMENT DESCRIPTION EXAM METHOD l VESSELS Sect. XI, 1989 Edition Pressure Vessel (B-A, B-D, B-H, C-A, C-B) Surface and/Automated Volumetric Appendix VM, 1995 or Manual Volumetric Edition, 1996 Addenda for UT as applicable Reactor Vessel Interior and welded attachments Visual Examination or core support structures (B-N-1, B-N-2)

Integral attachments for vessels (B-H, C-C) Surface and/or Volumetric Pressure retaining bolting >2" diameter Surface and/or Volumetric (B-G-1, C-D)

Pressure retaining welds in CRD housing Surface and/or Volumetric (B-O)

Sec. XI, 1992 Edition, Containment Inspection (IWE) Visual 92 Addenda PIPING Sect. XL 1989 Edition Pressure retaining Piping Welds Surface and/or Manual Volumetric Appendix VIIL 1995 (B-F, B-J, C-F) or Automated Volumetric Edition, 1996 Addenda for UT as applicable Integral attachment for piping pumps and Surface and/or Volumetric valves (B-K-1, C-C, Code Case N-509)

OTHER 1989 Edition Pressure retaining partial penetration Visual Examination welds (B-E)

Pressure retaining bolting <2" diameter Visual Examination (B-G-2)

Pressure retaining bolting >2" diameter Visual Examination (B-G-1) and /or Volumetric Pressure boundary component supports Visual Examination (F-A, Code Case N491-1)

Pump and Valve Internal Surfaces Visual Examination (B-L-2, B-M-2)

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48166 Fermi-2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MfI 48166 Conunercial Service Date: 1-23-S8 NBNo. 21085 (RPV) 4

TABLE A (continued)

REQUIREMENT DESCRIPTION EXAM METHOD PRESSURE TEST 1989 Edition Interval 2 Pressure Testing (B-P, C-H, Visual Examination and D-B, Code Case N-416-1, Code Case N-498-1)

AUGMENTED NUREG-0313, Pressure retaining piping welds (B-F, B-J) Manual Volumetric and/or Rev. 2 and BWRVIP- Automated Volumetric 75 Pressure retaining piping welds (Nonclassed) Manual Volumetric BWROG NUREG-0619 Feedwater Nozzle Inner Blend Radii Manual or Automated Volumetric -

Alternative Feedwater (GE-NE-523-A71-594) from outside surface Nozzle Inspections Fermi 2 Technical Safety Related Snubbers Visual Examination Requirements Manual 5.1 Sampling of Safety Related Snubbers Functional Testing 1E Notice 93-079 Core Shroud Visual Examination Generic Ltr. 94-03 Core Shroud Welds Visual Examination IEB 80-13 Core Spray and Spargers Visual Examination Vendor Recommendations SIL No. 459 Byron Jackson Recirculation Pump Shaft Visual Examination Cracking SIL No. 409 Incore Dry Tube Cracks Remote Visual Examination RICSIL No. 073 Incore Dry Tube Cracks Remote Visual Examination SIL No. 420 Jet Pump Sensing Lines and Support Brackets Remote Visual Examination SIL No. 433 Shroud Head Bolts Remote Visual Examination Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48166 Ferml-2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 5

TABLE A (continued)

REQUIREMENT DESCRIPTION EXAM METHOD AUGMENTED (continued)

SIL No. 462 Access Hole Cover Cracking Remote Visual Examination SEL No. 465 Jet Pump Inlet Mixer Remote Visual Examination SIL No. 474 Steam Dryer Channel Cracking Remote Visual Examination SIL No. 551 Jet Pump Riser Bracket Remote Visual Examination SL No. 554 Top Guide Beams Remote Visual Examination SIL No. 559 Top Guide Inspections Remote Visual Examinations SIL No. 574 Jet Pump Adjusting Screw Tack Welds Remote Visual Examination SEL No. 588, Rev. 1 Top Guide and Core Plate Cracking Remote Visual Examination SRL No. 629 Inlet Mixer Wedge Damage in BWR Jet Pump Remote Visual Examination Assemblies BWRVIP-Ol/76 BWR Core Shroud Remote Methods as in BWRVIP-03 Core Shroud Inspection and Flaw Evaluation Guidelines BWRVIP-03 Reactor Reactor Vessel Remote Visual Examination, Vessel and Internal Internals Components Ultrasonic and Eddy Current Examination Guidelines BWRVIP-07 Core Shrouds Remote Visual and Ultrasonic Guidelines for Reinspection of BWR Core Shrouds BWRVIP-18 Core Core Spray Internals Piping and Spargers Remote Visual Examination Spray Inspection and Evaluation (I&E)

Guidelines Detroit Edison Co, 2000 2nd Ave., Detroit, Ml 48166 Fermi-2 Nudcear Power Plant, 6400 N. Dixe Highway, Newport, Ml 48166 Commercial Service Date: 1-23-48 NBNo. 21085 (RPV) 6 -

TABLE A (continued)

REQUIREMENT DESCRIPTION EXAM METHOD AUGMENTED (continued)

BWRVIP-25 Core Plate Core Plate Components Remote Visual Examination I&E Guidelines BWRVIP-26 Top Top Guide Components Remote Visual Examination Guide I&E Guidelines BWRVIP-27 BWR Core Differential Pressure and SLC Line Direct Visual Standby Liquid Control Dissimilar Metal Nozzle Welds System / Core Plate Differential Pressure I

& E Guidelines BWRVIP-38 Shroud Shroud Support Components Remote Visual Examination Support I&E Guidelines BWRVIP-41 Jet Pump Jet Pump Components Remote Visual Examination Assembly I&E Guidelines BWRVIP-47 BWR Incore Guide/Dry Tubes Remote Visual Examination Lower Plenum I&E Guidelines BWVRIP-48 Vessel ID Vessel Internal Attachments Remote Visual Examination Attachment Weld I&E Guidelines BWRVIP-49 Instrument Penetrations Remote Visual Examination Instrument Penetration I&E Guidelines Detroit Edison Co, 2000 2nd Ave., Detroit, Ml 48166 Fermd-2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, Ml 48166 Commercial Service Date: 1.23-88 NBNo. 2108S (RPV) 7

SECTION 2

SUMMARY

OF ASME CLASS 1 & 2 AND AUGMENTED EXAMINATIONS Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48166 Fermi-2 Nuclear Power Plant, 6400 N. Dixie Highway, Newport, Ml 48166 Commercial Service Date: 1-2348 NBNo. 21085 (RPV) 8

2.1 Interval 2. Period 2, RF-09 Examinations B-A Reactor Vessel Shell & Head Welds Vol.

1-3061 Bottom Head Meridional 5360-5 UT 6 2667-59 4/6 4/8 4/16 UT-042 thru 045 UT-042 thru RF Blo, 300,604' Manual RPV 045 01 1-319D Closure Head Meridional 5360-5 UT 6 2667-58 3/31 4/2 4/11 UT-016 thru 018 UT-016 thru RF Refuel Fir. Manual RPV 018 02 15-308B Shell Longitudinal Weld 5360-5 UT 7 2667-62 4/4 4/10 4/15 VES.60.IN 186 Pages RF DW,172,620' Auto UT 05 2-307C Shell Longitudinal Weld 5360-5 UT 7 2667-60 4/4 417 4/14 VES.60.IN 76 Pages RF DW,218,610' Auto UT 08 2-308B Shell Longitudinal Weld 5360-5 UT 7 2667-60 4/5 4/9 4/14 VES.60.IN 27 Pages RF DW,180,646' Auto UT 09 4-319 Closure Head Circ Weld 5360-5 UT 6 2667-58 4/9 4/10 4/16 UT-048 thru 050, UT-048 thnu RF Refuel Fir. Manual RPV UT-063 thru 069 050, UT-063 13 thru 069 2-307A Shell Longitudinal Weld 5360-5 UT 7 2667-60 4/8 4/12 4/14 VES.60.IN 137 Pages RF-0 DW,340,610' Length 106 Coverage 99%

B6D Reactor Vessel Nozzle to Vessel Welds Vol.

13-314E Recirc Inlet Nozzle 5361-5 UT 8 2667-60 4/6 4/11 4/14 NOZ.60.IN 34 Pages RF DW,150,615' Auto UT 03 13-314F Recirc Inlet Nozzle 5361-5 UT .8 2667-60 417 4/10 4/14 NOZ.60.IN 50 Pages RF DW,210,615' Auto UT 04 Auto UT 15-315 CRD Return Nozzle 5361-5 UT 6 & 20 2667-60 4/8 4/9 4/14 UT-051 thnu 055 UT-051 thru RF DW,145,638' Manual RPV 055 06 4-316C Feedwater Nozzle 5361 -5 UT 8 2667-60 4/7 4/11 4/14 NOZ.60.IN 33 Pages RF DW,150,642' Auto UT 12 B-D Reactor Vessel Nozzle Inner Bore Region Vol.

13-314D IRS Recirc Inlet Nozzle 5361-5 VT 15 1-milwire *4/16 *4/27 *5/13 N/A N/A N/A Invess,120, *Comp. Under Job 1109030328 13-314E IRS Recirc Inlet Nozzle 5361-5 VT 15 1-mil wire *4/18 *4/27 *5/13 N/A N/A N/A Invess,150 *Comp. Under Job 1109030328 Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 9

Sys/comp 10 Description ISO Exams Procedure Cal Std Comp L IlIl ANII Cal Sheet Daft Sheet Report LodAz/EI Remarks 13-314F IRS Recirc Inlet Nozzle 5361-5 VT 15 1-mil wire *4/18 *4/27 *5/13 N/A N/A N/A Invess,210 *Comp Under Job 1109030328 13-314G IRS Recirc Inlet Nozzle 5361-5 VT 15 1-mil wire *4/16 *4/27 *513 N/A NWA N/A Invess,240 *Comp. Under Job 1109030328 13-314K IRS Recirc Inlet Nozzle 5361-5 VT 15 1-mil wire ^4/16 '4/27 5/13" N/A N/A N/A Invess,330 'Comp. Under Job 1109030328 B-F Class 1-Piping RIISI Welds Vol.

N-9 CRD Return Cap (IGSCC) 5361-5 UT CS-48, 4/8 4/14 4/16 UT-059 thru 062 UT-059 thru RF DW,145,638' RIISI Coverage INC-49 062 47 2-303G RRI Noz to SE (IGSCC) 5356-5 UT SS- 4/2 4/5 4/11 APC-001 thru 006 APD-001 RF DW,240,615' RIISI Coverage 56/CSCL- 07 54 B-J Class 1-Piping RIISI Welds Vol.

FW-RD-2-A16 B31 12 SE-P 5356-5 UT SS-17 4/3 4/5 4/14 APC-008 thru 011 APD-02 RF DW,240,615 RIISI Coverage (IGSCC,CRC) 44 SW-RS-2-A2-W1 B31 28' Pipe-El (IGSCC) 5357-5 UT SS-3 4/4 4/4 4/13 UT-036,UT-037 UT-036,UT- RF-0 DW,0,578' RIISI Coverage 037 69 FW-E11-2299-2WF3 RHR 20' Tee-Pipe 2299-5 UT CS-12 4/5 4/5 4/13 UT-40 UT-040 RF DW,175,597 29 SW-E21-3053-3WN Core Spray 12' El-Pipe 3053-5 UT CS-is 4/8 4/10 4/15 UT-071 UT-071 RF-O9- DW,120,637-57 SW-E21-3053-3WP Core Spray 12' Pipe-El 3053-5 UT CS-15 4/8 4/10 4/15 UT-070 UT-070 RF DW.120,636' 58 FW-ESI-2192-1W2 RCIC 6' El-Pipe 2192-5 UT CS-22 4/8 4/10 4/16 UT-056 thru 058 UT-056 thru RF DW,42,598' 058 40 FW-ES1 -2192-2W3 RCIC 6" Pipe-E. 2192-5 UT CS-22 4/11 4/12 4/15 UT-073 thru 075 UT-073 thru RF DW,355,598' 075 60 SW-N21-2336-1WD RCIC 20" Sweep-Pipe 3536-5 UT CS-12 4/2 4/3 4/16 UT-029,UT-030 UT-029,UT- RF-- Stm.10,686' 030 63 SW-N21-2336-1WU RCIC 20" Pipe-Tee 3536-5 UT CS-12 4/2 4/3 4/6 UT-031 UT-031 RF Stm,10,590' 65 SW-N21-2336-1WL mF (TASCS) 20" Tee-PIpe 3536-5 UT CS-12 4/3 4/3 4/12 UT-025 UT-025 RF-0 StM,10,594- RIISI Coverage 64 SW-N21-2336-3WC RCIC 20' El-Tee 3536-5 UT CS-12 4/5 4/6 4/13 UT-038 UT-038 RF DW,330,608' 66 FW-N21-2336-3W4 RCIC 12' Tee-El 3536-5 UT CS-is 4/5 4/6 4/14 UT-039 UT-039 RF-0 DW,330,608' 43 Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 .

Ferni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 10

Sys/Comp ID Description ISO Exams Procedure Cal Std Comp L III ANII Cal Sheet Data Sheet Report Loc/AV/EI Remarks B-G-1 Bolting Greater Than 2*

326-02 (Closure Nuts) 1/3 of locations (1-22) 5362-5 MT 2 N/A 4/5 4/5 4/13 N/A MT-013,VT- RF Refuel Fir.

029 10 Threads In Flange 1/3 of locations (1-22) 5362-5 UT 9 RPV & 3/31 4/2 4/4 UT-015 UT-0l5 RF RPV Cavity complete prior CSCL-52 70 to flood up 326-03 (Closure 1/S of locations (1-22) 5362-5 VT-1 16 N/A 4/5 4/5 4/14 N/A VT-028 RF Refuel Fir.

Washers) 11 Base Scope B6--2 Bolting 2 and Less FBC-E41-2297-01 2297-5 VT-1 16 N/A 4/5 4/10 4/17 N/A VT-032 RF DW,51,595' Al bolting 25 exams completed under surveillance B31-F023A-VBB 5357-5 VT-1 16 N/A 4/3 4/4 4117 N/A VT-027 RF DW,342,574' 1105030100 17 B31-FO31A-VBB 5357-5 VT-1 16 N/A 4/3 4/4 4/17 N/A VT-026 RF DW,290,578 18.

El 1-F067-VBB 2299-5 VT-1 16 N/A 4/5 4/10 4/17 N/A VT-031 RF DW,163,595' 21 El 1-FO09-VBB 2299-5 VT-1 16 N/A 4/5 4/10 4/17 N/A VT-=3 RF DW,1 63,600' CARD 03-20 16366 E21-FOO5A-VBB 3052-5 VT-1 16 N/A 3129 3/29 4/17 N/A VT-025 RF RB2,C1 3,633 22 E21-FO05B-VBB 3053-5 VT-1 16 N/A 3/29 3129 4/17 N/A VT-024 RF RB2,C1 1,632 23 E51-F007-VBB 2192-5 VT-1 16 N/A 4/9 4/10 4/17 N/A VT-M4 RF DW,360,583' 24 G33-F004-VBB 3096-5 VT-1 16 N/A 4/10 4/11 4/17 N/A VT-049 RF RB2,C13,624 46 B21-F032A-VBB 3537-5 VT-1 16 N/A 4/11 4/12 4/17 N/A N/A RF Stm,350,594' Initial Scope 16 Delete (RF09-209),

Examined as part of sample expansion

- , .. - , Detroit Edison Co., 2000 2nd Ave.. Detroit. Ml .48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 11

Sys/Comp ID Description ISO Exams Procedure Cal Std Comp L III AMI Cal Sheet Data Sheet Report Loc1Az(EI Remarks B21-FOlOB-VBB 3536-5 VT-1 16 N/A 4/14 4/16 4/17 N/A N/A RF DW,10,603' Scope Delete 14 RF09-209 B21-F01 1B-VBB 3536-5 VT-1 16 NWA 4/9 4/10 4/17 N/A VT-047 RF-09 DW,10,594 CARD 03-15 16370 Initial Sample Expansion B4-2 Bolting 2" and Less El`1-F015B-VBB 2327-5 VT-1 16 NA 4/9 4/10 4/17 N/A VT-046 RF All bolting 89 completed under suvelilancer E21-FO06A-VBB 3052-5 VT-1 16 N/A 4/9 4/10 4/17 N/A VT-045 RF-09 1105030100 95 E21-FO06B-VBB 3053-5 VT-1 16 N/A 4/9 4/10 4/17 N/A VT-044 RF-09 96 E21-FO07A-VBB 3052-5 VT-1 16 N/A 4/9 4/10 4/17 N/A VT-043 RF-09 97 E21-F007B-VSB 3053-5 VT-1 16 N/A 4/9 4/10 4/17 N/A VT-042 RF-09 98 E41 -F002-VBB 2297-5 VT-1 16 N/A 4/8 4/10 4/17 N/A VT-039 RF-09 79 E41-F003-VBB 2297-5 VT-1 16 N/A 4/8 4/10 4/17 N/A VT-038 RF-09 78 E41 -F006-VBB 3537-5 VT-1 16 N/A 4/8 4/10 4/17 NtA VT-037 RF-09 77 ESI -F008-VBB 2192-5 VT-1 16 N/A 4/8 4/10 4/17 N/A VT-035 RF 75 E61-F013-VBB 3536-5 VT-t 16 N/A 4/8 4/10 4/17 N/A VT-036 RF 76 G33-FOOI-VBB 3096-5 VT-1 16 NIA 4/9 4/10 4/17 N/A VT-041 RF 99 G33-F1O1 -VBB 3096-5 VT-1 16 N/A 4/9 4/10 4/17 N/A VT-040 RF-09.

101 G33-F121 -VBB 3536-5 VT-1 16 N/A 4/8 4/10 4/17 N/A VT-034 RF409-74 G33-F220-VBB 3536-5 VT-1 16 N/A 4/8 4/10 4/17 N/A VT-033 RF 73

) . L . 4 *v a . _s . I . Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 ... . . . . - J Ferni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commerdal Service Date: 1-23-88 NBNo. 21085 (RPV) 12

Sys/Comp ID Description ISO Exams Procedure Cal Std Comp L II ANII Cal Sheet Data Sheet Report Loc/Az/EI Remarks Second Sample Expansion B-G-2 Bomling 2" and Less B21-FO1OA-VBB 3537-5 VT-i 16 N/A 4/11 4/12 4/17 N/A VT-051 RF Completed 80 under surveillance B21-FO1OB-VBB 3536-5 VT-i 16 N/A 4/14 4/15 4/17 N/A VT-069 RF Job 81 1105030100 B21-FO11A-VBB 3537-5 VT-i 16 N/A 4/11 4112 4/17 NIA VT-052 RF 82 B21-F032A-VBB 3537-5 VT-I 16 N/A 4/11 4/12 4/17 N/A VT-053 RF 83 B21-F032B-VBB 3536-5 VT-I 16 N/A 4/11 4/12 4/17 N/A VT-054 RF 84 B21-F076A-VBB 3537-5 VT-i 16 N/A 4/11 4/12 4/17 N/A VT-055 RF 85 B21-F076B-VBB 3536-5 VT-i 16 N/A 4111 4/12 4/17 N/A VT-056 RF 86 E11-F008-VBB 2299-5 VT-i 16 N/A 4/14 4/15 4/17 N/A VT-068 RF409- CARD 03-87 16372 E11-FO15A-VBB 2298-5 VT-i 16 N/A 4/11 4/12 4/17 N/A VT-057 RF 88 E11-FO5OA-VBB 2298-5 VT-i 16 N/A 4/11 4/12 4/17 N/A VT-058 RF 90 E1t-F050B-VBB 2327-5 VT-1 16 N/A 4/11 4/12 4/17 N/A VT-059 RF-0 91 E11-FO60A-VBB 2298-5 VT-i 16 N/A 4/11 4/12 4/17 N/A VT-060 RF 92 El1-F060B-VBB 2327-5 VT-i 16 N/A 4/11 4/12 4/17 N/A VT-061 RF CARD 03-93 16371 E11-F608-VBB 2299-5 VT-1 16 N/A 4/11 4/12 4/17 N/A VT-062 RF-0 94 G33-F100-VBB 5351-5 VT-i 16 N/A 4/11 4/12 4/17 N/A VT-063 RF 100 G33-F102-VBB 5351-5 VT-i 16 N/A 4/11 4/12 4/17 N/A VT-064 RF-0 102 G33-F106-VBB 5351-5 VT-i 16 N/A 4/11 4/12 4/17 N/A VT-065 RF--

103 G33-F120-VBB 3536-5 VT-i 16 N/A 4/11 4/12 4/17 N/A VT-066 RF-0 104

< ,.... . ...1 . .-........-. EdisonCo.,20002ndAve.,DetroitM 48226

... DeotEinC,202dA.Detroit 4..2.."r, .... ...

Frmi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 13

Sys/Comp ID Description ISO Exams Procedure Cal Std Comp L NiI ANII Cal Sheet Dats Sheet Report Leo/Az/El Remarks B-G-2 Bolting 2' and Less CRD Flange Bolts 4219 (1) 3431 (2) 5363-5 VT-1 16 N/A 4/9 4/12 4/17 N/A VT-050 RF Drywell, 105 Undervessel CRD Bolting New CRD Bolting 1-184 N/A VT-1 16 N/A 3/27 3/28 4/16 N/A VT-001 thru RF VT-023 72 B-P Pressure Retaining M-4536 VT-2 43.000.005 N/A 4/30 4/30 4/30 N/A 0975030430 03-022 Varlous System Boundary Leakage Test D- it Edison Co., 2000 2nd Ave., Deroit, MI 48226..

Dero.... .. I . . .. -- . -

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 14

C-C Vessel Intregal Attachment Vol.

SW-Ell-D2-HXS-13 RHR HX B 5370-5 MT 2 NWA 4/12 4/14 4/15 N/A MT-018 RF RB2,B9,625' Division 2 53 Systemr SW-Eli-D2-HXS-14 RHR HX B 5370-5 MT 2 NWA 4/12 4114 4115 N/A MT-017 RF 54 SW-El 1-D2-HXS-15 RHR HX B 5370-5 MT 2 N/A 4/12 4114 4/16 NIA MT-016 RF409-55 SW-El1t-D2-HXS-16 RHR HX B 5370-5 MT 2 N/A 4/12 4/14 4/16 N/A MT-019 RF 56 C-F-1 Augmented NRC Commitment VoL FW-C41-2979-63S64 SLC weld 2' El -Pipe 2979-5 PT 1 N/A 3/24 3/26 4/4 N/A PT-001 RF-0 RB3, 652,E11 26 FW-{41-2979-64S65 SLC weld 2' Pipe-El 2979-5 PT 1 N/A 3/24 3126 4/4 N/A PT-002 RF RB3, 652,E11 27 FW-C41 -5058-54555 SLC weld 2'Pipe-Reducer 5374-5 PT I N/A 3/24 3126 4/4 N/A PT-03 RF RB3,F1O,661 28 C-F-2 Circumferential Weld Vol.

SW-Ctl-2113-172-A CRD SDV ' Pipe-Tse 5375-5 MT 2 N/A 3/29 4/1 4/6 N/A MT-006 RF RB1,C1O,597' 48 SW-Cl 1-21 13-172-A 5375-5 UT 3 CS-20 3/29 411 4/6 UT-007,UT-008 UT-007,UT- RF 008 48 SW-El 1-3036-7WB RHR 6 El-Pipe 3035-5 MT 2 N/A 3129 3/30 4/4 N/A MT-005 RF-0 Tor,180,578 49 FW-E1 1-3151-3WF2 RHR 24- Tee-El 3151-5 MT 2 N/A 4/12 4/14 4/16 N/A MT-020 RF HxRm,C10,60 Division 2 30 5' System FW-E1 l-3151-3WF2 3151-5 UT 3 CS-43 4/12 4/14 4/16 UT-080,UT-081 UT-080,UT- RF 081 30 SW-El l-3154-4WC RHR 24" El-Tee 3154-5 MT 2 N/A 3/30 3/30 4/6 N/A MT-007 RF Tor,C17,543' 50 SW-El 1-3154-4WC 3154-5 UT 3 PDI-Alt- 3/30 4/2 4/6 UT-009 thru 012 UTv-09 thru RF CS1 012 50 FW-E1 1-3154-13WO RHR 24" Pipe-Pump 3154-5 MT 2 N/A 3/31 4/2 4/13 N/A MT-01a RF RBSB,A15,54 31 1' FW-E1 1-3154-13WO 3154-5 UT 3 PDI-Alt- 4/1 4/2 4/13 UT-019,UT-021, UT-019,UT- RF CS1 UT-022 021, UT-022 31 FW-E1 1-3158-1W2 RHR 24" Pipe-El 3158-5 MT 2 N/A 3/30 3/30 4/6 N/A MT-008 RF HxRm,C17,59 32 3' FW-E1 1-3158-1W2 3158-5 UT 3 CS-43 3/31 3/31 4/6 UT-014 UT-014 RF 32 I- I -1 I . ".. - , - . .1 .1 . I .-

I I 11.1 - .. I ,-

.. I-. ~-.".-Detroit Edison Co., 2000 2nd Ave., Detroit, M .48226, ...

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Fermi 2Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 15

Sys/Comp ID Description ISO Exams Procedure Cal Std Comp L III ANil Cal Sheet Data Sheet Report Loc/A2/EI Remarks FW-El 1-3158-9WF2 RHR 20' Pipe-El 3158-5 MT N/A 3/30 4/1 4/14 N/A MT-009 RF HxRm,B17,63 33 5' FW-E1 1-3158-9WF2 3158-5 UT CS-42 3/31 4/1 4/14 UT-013 UT-013 RF-09 33 SW-El 1-3177-9WE RHR 20'ElPipe 3177-5 MT N/A 4/3 4/4 4/6 N/A MT-012 RF TorB10,570' 52 SW-El1-3177-9WE 3177-5 UT CS-42 4/3 4/4 4/6 UT-035 UT-035 RF-O-52 FW-E21-3148-7W0 Core Spray 12' Red-Pump 3148-5 MT N/A 3/31 4/2 4/14 N/A MT-010 RF RBSB,G17,54 34 1' FW-E21-3148-7W0 3148-5 UT PDI-Ait- 4/1 4/2 4/14 UT-020 UT-020 RF-09 CS1 34 FW-E41-3162-IIWF1 HPCI 16' Pipe-Tee 3162-5 VT-1 N/A 3/25 3/28 4/4 N/A N/A RF Tor,G1 1,564' 35 FW-E41-3162-1 1WF4 HPCI 16' Tee-Reducer 3162-5 VT-1 N/A 3/25 3/28 4/4 N/A N/A RF-09 TorG11,564' 36 FW-E41-3162-1 IWF5 HPCI IO' Reducer- 3162-5 VT-i N/A 3/25 3/28 4/4 N/A N/A RF Tor,G11,564' Reducer 37 FW-E41-3167-OWI HPCI 10' Pump-Pipe 3167-5 MT N/A 3/26 3/28 4/11 N/A MT-001 RF HPCI Skid, 38 546' FW-E41 -3167-OWI 3167-5 UT CS-50 3126 3/28 4/11 UT-002 UT-002 RF 38 FW-E41-3169-2W0 HPCI 10 Pipe-Valve 3169-5 MT N/A 3/26 3/29 4/14 N/A MT-002 RF-{X CRDG1 1,569' 39 FW-E41 -3169-2W0 3169-5 UT CS-36 3/27 3/29 4/14 UT-003,UT-004 UT-003,UT- RF 004 39 SW-E41-5373-GW3 HPCI 12'EI-Pipe 5373-5 MT N/A 3/27 3/30 4/12 N/A MT-003 RF HPCI Skid, 59 546' SW-E41-5373-4W3 5373-5 UT PDI-Alt- 3/27 3/30 4/12 UT-05,UT-06 UT-005,UT- RF CS1 006 59 SW-N30-3258-7WK Main Steam 26' Pipe- 3258-5 MT N/A 4/6 4/10 4/13 N/A MT-014 RF Stm,F12,589' RedEl 67 SW-N30-3258-7WK 3258-5 UT CS-5 4/6 4/10 4/13 UT-046,UT-072 UT-046,UT- RF 072 67 SW-N30-3258-7WKLU Main Steam 26' Long 3258-5 MT N/A 4/6 4/10 4/15 N/A MT-015 RF Stm,F12,589' Seam 68 SW-N30-3258-7WKLU 3258-5 UT CS-5 4/6 4/10 4/15 UT-047 UT-047 RF 68 C-F-2 Branch Connections Vol.

SW-El 1-3160-IWD RHR 18' Weldolet 3160-5 MT 2 NIA 3/29 3/30 4/4 N/A MT-004,PT- RF Tor,B15,578' 005 51

. - I., .- iI--- - .11;-., I--- 111.'..."'. I' .. iDetroit Edison Co,, 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant. 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 16

Description ANSI B31.1 GL 88-01 Category D Vol. UT FW-N20-3105-0W23 201 El-SE Htr 4N, Upper 3105-1 PT/UT 1/13 SSCL-88 4/16 4J18 N/A UT-082 thru 084 UT-082 thnJ 084. RF-9 TB2,P12,62 PT on ID.

Nozz PT-008 41 4' Also PDI-UT-10 DM SW-N20-03-B01 1- 20" Nozz-SE 4N, Upper 3105-1 PT/UT 1/13 SSCL-88 4/16 4/18 N/A UT-085 thru 087 UT-085 thru 088, RF TB2,P12,62 PT on ID.

BWSE Nozz PT006 62 4' Also PDI-UT-10 DM FW-N20-3105-22WO 20' El-SE Htr 4N, Lower 3105-1 PT/UT 1/13 SSCL-88 4/15 4/18 N/A UT-091 thru 093 UT-091 thni 094 RF TB2,P12,61 PDI-UT-10 Nozz 42 5' DM SW-N20-03-BO1 1- 20' Nozz-SE 4N, Lower 3105-1 PT/UT 1/13 SSCL-88 4/15 4/18 N/A UT-088 thna 090 ' UT-88 thmu 091 RF-M TB2,P12,61 PDI-UT-10 AWSE Nozz 61 5' DM

- ..*... . ...... *.. ..,,,, . .. ... .i.DetroitEdison Co., 20002nd Ave., Detroit, MI, 448226.. -- . - I ,- . I " .1-14 .I -, - .1. - !

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport MI 48166 Commercial Service Date: 1-23-88 N8No. 21085 (RPV) 17

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

-.- II., .' ..... .. Detroit Edison Co., 2000 2nd Ave.,.Detroit, Ml 48226 . . .

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MT 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 18

2.2 Interval 2, Period 1,RF-08 Examinations B-A Reactor Vessel Shell Welds Vol.

1-308A 5360-5 UT 8 2667-62-1 15-Nov 17-Nov 19-Nov PDI-254-CO1 PDI-254-CO1 R8-96 DW,52,552 PDI--C25, C26 UT23, UT24, UT25, UT26, 27 1-308B 5360-5 UT 8 2667-62-1 15-Nov 17-Nov 19-Nov PDI-254-CO1 PDI-254-CO1 R8-97 DW,142,552 PDI-6-C27, C28 UT28, UT29, UT30, UT31 15-308C 5360-5 UT 8 2667-62-1 14-Nov 17-Nov 19-Nov PDI-254-CO1 PDI-254-C01 R8-98 DW,262,244 2-307A 5360-5 UT 8 2667-60-1 12-Nov 17-Jan 19-Nov PDI-254-C02 PDI-254-C02 R8-99 DW.339.122 B-A Reactor Vessel Clrc Head Welds Vol.

4-319 2-31 9C to 2-31 9E 40% 5360-5 UT 6 2667-58-1 1-Nov 5-Nov 17-Nov PDi-6-C11, C12 UT09, UT10 R8-47 Refuel Fir.

6-306 180 deg. to 360 deg. 5360-5 UT 6 2667-59-1 5-Nov 7-Nov 15-Nov PDI-6-C13, C14 UT11, UT12 R8-57 Refuel FMr.

..K.Detroit Edison Co., 2000 2nd Ave., Detrit 1 M l 48226 . .... <.. ....J-..

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 19

Sys/Comp ID Description ISO Exams Procedure Cal Std Comp L ilI ANII Cal Sheet Data Sheet Report LodAz/El Remarks B-A Reactor Vessel Meridonal Head Welds Vol.

2-31 9A Top Head 5380-5 UT 6 2667-58-1 31-Oct 6-Nov 17-Nov PDI-C-05. C06 UTO5, UTO6 R8-44 Refuel Fir.

2-319B Top Head 5360-5 UT 6 2667-58-1 31-Oct 6-Nov 17-Nov PDI--007, C08 UT07 R8-45 Refuel Fir.

2-319C Top Head 5360-5 UT 6 2667-58-1 2-Nov 6-Nov 17-Nov PDI-6CO9, C10 UT08 R8-46 Refuel Fir.

1-319B Top Head 5360-5 UT 6 2667-58-1 30-Oct 5-Nov 17-Nov PDI-6-C01, C02 UTO1, UTO2 R8-42 Refuel Rr.

1-319H Top Head 5360-5 UT 6 2667-58-1 30-Oct 5-Nov 17-Nov PDI-6-C03, C04 UTO3, UT04 R8-43 Refuel Fir.

1-306A Bottom Head 5360-5 UT 6 2667-59-1 6-Nov 7-Nov 17-Nov PDI-6-C15, C16 UT13, UT14 R8-60 Blo, Odeg 1-306D Bottom Head 5360-5 UT 6 2667-59-1 6-Nov 7-Nov 18-Nov PDI-6-C17, C18 UTiS, UT16 R8-61 Bio, 120deg 1-306E Bottom Head 5360-5 UT 6 2667-59-1 6-Nov 7-Nov 18-Nov PDI-6-C19, C20 UT17, UT18 R8-62 Bio, 144 deg 1-306G Bottom Head 5360-5 UT 6 2667-59-1 6-Nov 7-Nov 18-Nov PDI-6-C21, C22 UT19, UT20 R8-63 Blo, 225deg 1-306K Bottom Head 5360-5 UT 6 2667-59-1 6-Nov 7-Nov 18-Nov PDI-6C23, C24 UT21, UT22 R8-64 Bio, 335deg B-A Reactor Vessel Shell to Flange Welds Vol.13-308 Partial from shell side 5360-5 UT 7 2667-62-1 13-Nov 16- 16-Nov ISI-210-C46, C47, UT25, UT26 R8-95 DW, 723- 120 degrees Nov C48 13-30 Partial from flange 5360-5 UT 9 CSCI 28-Oct 30- 17-Nov ISI-54-C01 UTO0 R8-12 Vessel Cav. 180 degrees FER Oct B-A Reactor Vessel Head to Flange Vol. /

Surf.

3-319 113 of weld length 5360-5 UT 7 2667-58-1 1-Nov 6-Nov 17-Nov ISI-2104C01, C02, UTO1, UTO2, R8-41 Refuel Fir.

C03 UTO3, UTO4, UT05, UTi1 3-319 1/3 of weld length 5360-5 MT 2 N/A 30-Oct 6-Nov 17-Nov N/A MT-023 R8-41 Refuel Fir.

1- - . .11-6-1111.11.""', .1. 11--.1 ...... .. -.. . - ...' - . . . , ,- ]Detroit Edison Co., 2000 2nd Ave., Detroit, Ml48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Cornmercial Service Date: 1-23-88 NBNo. 21085 (RPV) 20

Sys/Comp 10 Description ISO Exams Procedure Cal Std Comp L lIl ANII Cal Sheet Data Shed Report LodAr/El Remarks B-D Reactor Vessel Nozzle to Vessel Welds Vol.

8-316A Main Steam Nozzle 5361-5 UT 7 2667-62-1 8-Nov 9-Nov 19-Nov ISI-210-C31, C32, UT19 R8-76 DW,71 .655 C33 8-316-B Main Steam Nozzle 5361-5 UT 7 2667-62-1 8-Nov 9-Nov 19-Nov ISI-210-C34, C35, UT20 R8-77 DW,109,655 C36 4-316A Feedwater Nozzle 5361-5 UT 7 2667-62-1 8-Nov 9-Nov 19-Nov ISI-210-C28, C29, UT17, UT18 R8-75 DW,30,642 C30 4-316B Feedwater Nozzle 5361-5 UT 7 2667-62-1 7-Nov 8-Nov 18-Nov ISI-210-C22, C23, UT15 R8-65 DW,90,642 C24 4-316D Feedwater Nozzle 5361-5 UT 7 2667-62-1 8-Nov 10- 18-Nov ISI-210-C37, C38, UT21, UT22 R8-78 DW,210,642 Nov C39 14-316B Core Spray Nozzle 5361-5 UT 7 2667-62-1 7-Nov 8-Nov 18-Nov ISI-210-C25, C26, UT16 R8-66 DW,240,641 C27 13-314A Recrc Inlet Nozzle 5361-5 UT 7 2667-60-1 5-Nov 7-Nov 17-Nov ISI-210-C10, C11, UT09 R8-53 DW,30,615 C12 13-314B Recirc Inlet Nozzle 5361-5 UT 7 2667-61 5-Nov 7-Nov 17-Nov ISI-210-C19, C20, UT14 R8-59 DW,60,615 C21 13-314D Recirc Inlet Nozzle 5361-5 UT 7 2667-61 6-Nov 7-Nov 17-Nov ISI-210-C16, C17, UT13 R8-58 DW,120,615 C18 13-314G Recirc Inlet Nozzle 5361-5 UT 7 2667-60-1 4-Nov 7-Nov 17-Nov ISI-210-CC4, C05, UT06, UT07, R8-51 DW,240,615 C06 UT08 13-314K Recirc Inlet Nozzle 5361-5 UT 7 2667- l1 5-Nov 7-Nov 17-Nov ISI-210-C13, C14, UTi0 R8-54 DW, 330,615 C15 5-314A Recirc Suction Nozzle 5361-5 UT 7 2667-60-1 12-Nov 14- 15-Nov ISI-210043, C44, UT24 R8-93 DW, 0,614 Nov C45 19-3148 JPI Nozzle 5361-5 UT 7 2667- l1 9-Nov 10- 17-Nov ISI-210-C40, C41, UT23 R8-82 DW,280,612 Nov C42 B-D Reactor Vessel Nozzle Inside Radius Vol. Same as Nozzle to vessel above 8-316A 5361-5 UT/VT 13 or 15 N/A IWI 18- 30-Nov N/A Completed 01-034 DW,71,655 Nov under Surv.

43.000.017 8-316-B 5361-5 UT / VT 13 or 15 N/A IWI 18- 30-Nov N/A Completed 01-034 DW,109,655 Nov under Surv.

43.000.017

. .. . . I . ,_.,--..

_ _- . ,.- .-- ...... ... . -Detroit Edison Co.,20002nd Ave., DetitML48226 .. -. . ,.......-

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 21

Sys/Comp 10 Description ISO Exams Procedure Cal Std Comp L IiI ANII Cal Sheet Data Sheet Report L*dAzfEI Remarks B-D Reactor Vessel Nozzle Inside Radius Vol. /

VT 4-316A 5361-5 UT 11 N/A 8-Nov 13- 17-Nov ISI-246-C01 ISI-246-C01 R8-86 DW,30,642 43.000.017 Nov 4-316B 5361-5 UT 11 N/A 8-Nov 13- 17-Nov 151-246-CO1 ISI-246-CO1 R8-87 DW,90,642 Nov 4-316D 5361-5 UT 11 N/A 7-Nov 13- 17-Nov ISI-246-C01 ISI-246-C01 R8-88 DW,210,64 Nov 2 14-316B 5361-5 UT/VT 13 or 15 N/A 1-Nov 13- 30-Nov N/A Completed 01-034 DW,240,64 Nov under Surv. 1 43.000.017 15-315 5361-5 UT/VT 13 or 15 N/A 1-Nov 13- 30-Nov N/A Completed 01-034 DW,150,63 Nov under Surv. 8 43.000.017 13-314A 5361-5 UT/VT 13 or 15 N/A 1-Nov 18- 30-Nov N/A Completed 01-034 DW,30,615 Nov under Sunv.

43.000.017 13-314B 5361-5 UT/VT 13 or 15 N/A 1-Nov 18- 30-Nov N/A Completed 01-034 DW,60,615 Nov under Sun'.

43.000.017 13-314D 5361-5 UT/Vr 13 or 15 N/A N/A N/A N/A N/A N/A N/A DW,120,61 Resheeduled 5

13-314G 5361-5 UT/VT 13 or 15 N/A N/A N/A N/A N/A N/A N/A DW,240,61 Reshceduled 5

13-314K 5361-5 uT/vr 13 or 15 N/A N/A N/A N/A N/A N/A N/A DW, Reshoeduled 330,615 5-314A 5361-5 UT/VT 13 or 15 N/A 1-Nov 18- 30-Nov N/A Completed 01-034 DW, 0,614 Nov under Surv.

43.000.017 19-314B 5361-5 UT/VT 13 or 15 N/A 1-Nov 18- 30-Nov N/A Completed 01-034 DW,280,61 Nov under Surv. 2 43.000.017 B-D Reactor Vessel Nozzle Inner Bore Vol.

Region 4-316A IBR FW Na Inner Bore 5361-5 UT 11 70287 8-Nov 13- 17-Nov ISI-246-COl ISI-246-CO0 R8-86 DW,30,642 Region Nov 4-316B IBR FW Nzz Inner Bore 5361-5 UT 11 70287 8-Nov 13- 17-Nov ISI-246-C01 ISI-246-COI R8-87 DW.90,642 Region Nov 4-316D IBR FW Nzz Inner Bore 5361-5 UT 11 70287 7-Nov 13- 17-Nov ISI-246-CO1 ISI-246-001 R8-88 DW,210,64 Region Nov 2

. , . Detroit Edison Co, 2000 2nd Ave., Detroit, Ml 48226 .. - .. - , -..

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 22

Description ISO Exams Procedure Cal Std Comp L III ANII Cal Sheet Data Sheet Report Loc/Az/EI Remarks B-F &B-J Class 1 RIISI Welds Piping N5B 12" CS SE to Nzz (DM) 3052-5 UT 12 CS-44AN- 6-Nov 16-Nov 19-Nov PDI-2-C14 UT13, UT14 R8-79 DW,240,641 45 UNIXD-C03, C04 UNIXD-C03, C04 SW-E21-3052-4WOX 10" CS Pipe to SE (PM) 3052-5 UT 12 CS-18AN- 7-Nov 16-Nov 19-Nov PDI-2-C13 UNIXD-C01, C02 R8-71 DW,240,641 45 UNIXD-C0O1, C02 FW-RD-2-A9 28" Tee to Cross 5357-5 UT 4 SS-30 3-Nov 5-Nov PDI-2-CO6 UT07 R8-49 DW,270,613 FW-EI1-2298-6WO 24" Pipe to Tee 2298-5 UT 4 SS-8 2-Nov 2-Nov 17-Nov PDI-2-CO2 UT04 R8-39 DW,270,600 SW-El 1-2298-6WC 24 Pipe to Pipe (DM) 2298-5 UT "A CS-7/SS- 2-Nov 2-Nov 16-Nov PDI-1-C18 UT03 R8-38 DW,270,600 8 PDI-2-C04 FW-G33-3096-1 OWF3 4 Sweepolet to Tee 5351-5 UT 4 SS-23 2-Nov 8-Nov 17-Nov PDI-2-C05 UTO5, UT06 R8-40 DW~,140,573 7-316A Main Steam Nzz to SE 5352-5 UT 3 CS-5 8-Nov 8-Nov 19-Nov PDI-1-C34, C35 UT18 R8-74 DW,72,655 SW-PS-2-A1-A 26" Pipe to Elbow 5352-5 UT 3 CS-5 8-Nov 8-Nov 17-Nov PDI-1-C30, C31 UT16 R8-72 DW.72,655 SW-PS-2-A1-B 26" Elbow to Pipe 5352-5 UT 3 CS-5 8-Nov 8-Nov 17-Nov PDI-1-C32, C33 UT17 R8-73 DW.72,653 SW-PS-2-C3-J 8" Sweepolet to Pipe 5354-5 UT 3 CS-20 12-Nov 13-Nov 17-Nov PDI-1-C40 UT23, UT24 R8-91 DW,314,609 SW-PS-2-C3-K 8" Pipe to Flange 5354-5 UT 3 CS-20 12-Nov 13-Nov 17-Nov PDI-1-C41 UT25, UT26 R8-92 DW,314,609 SW-RD-2-B8-W1 12" Pipe to Elbow 5358-5 UT 4 SS-17 1-Nov 2-Nov 16-Nov PDI-2-CO3 UT-02 R8-35 DW,90,613 SW-RD-2-88-W2 12" Elbowto Pipe 5358-1 UT 4 SS-17 30-Oct 2-Nov 16-Nov PDI-2-C01 UT-01, MT-01I R8-15 DW,90,615 FW-E11-2327-OW1 24" Valve to Pipe 2327-5 UT 3 CS-9 3-Nov 4-Nov 17-Nov PDI-1-C19 UT1I R8-48 RB131,B12,594 FW-E41-2297-2W3 10" Pipe to Elbow 2297-5 UT 3 CS-22 2-Nov 3-Nov 16-Nov ISIC-350404 UT09, UT10 R8-37 DW0,0.86 PDI-1 -C17 FW-E41-2297-0W4 10" Fluted head to pipe 2297-5 UT 3 CS-le 2-Nov* 2-Nov 11-Nov PDI-1-C15, C16 UTO8 R8-36 Strn,F12,586

.- I , . I - 11.1  !- 1.11 .. .. Detroit Edison Co., 2000 2nd Ave, Detroit, MI 48226 I.. - . ..... .- . t . I ,I , , ,., .I I I II -

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Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RP 23

Sys/Comp 10 Description ISO Exams Procedure Cal Std Comp L III AMI Cal Sheet Data Sheet Report Loc/Az/EI Remarks B-F & B-J Class I RIISI Welds Piping 3-316A FW 14' SE to Noz 3537-5 UT 3 CS-46 7-Nov 8-Nov 19-Nov PDI-1-C28 UT14 R8-69 DW,30,642 N4A SE Ext. toSE 3537-5 UT 3 CS-46 7-Nov 8-Nov 19-Nov PDI-1-C29 UT15 R8-70 DW,30,642 FW-N21-2336-15W0 12Plpeto SE 3537-5 UT 3 CS-15 7-Nov 8-Nov 17-Nov PDI-1-C27 UT13 R8-68 DW,30,642 SW-N21-2336-15WP 12Z Pipe to Elbow 3537-5 UT 3 CS-15 7-Nov 8-Nov 18-Nov PDI-1-C26 UT12 R8-67 DW,30,641 B-U-1 Boting Greater Than 2" RPV CAosure Nuts 1/3 of locations 5362-5 MT 2 N/A 10- 12-Nov 17-Nov N/A MT-027, MT-028 RB-83 Refuel Fir.

Nov VT-004 RPV Closure Studs 1/3 of locations In place UT 5 RPV Stud 28- 5-Nov 11 -Nov PDI-5-C01, C02 UT-01 R8-10 RPV Cavity 48-51 Oct 17-Nov PDI-5-C03, C04 R8-50 4-Nov.

RPV Closure Studs 48-51 removed MT 2 N/A 10- 12-Nov 17-Nov N/A MT-026 RB-50 Refuel Fir.

Nov Threads in Flange 1/3 of locations UT 10 CSCL-52 29- 30-Oct 16-Nov ISI-55-C01 UT-al1* UT-02 R8-11 RPV Cavity Oct RPV Closure 1/3 of locations VT-1 16 N/A 10- 12-Nov 17-Nov N/A VT-005 R8-84 Refuel Flr.

Washers/Bushings Nov Recirc Pump Studs Pump A 1-16 5365-5 VT-i 16 NJA 10- 17-Nov 27-Nov N/A 01-035AP DW,315,579 Nov Recirc Pump Studs Pump A 1-16 UT 5 i31 Stud 10- 12-Nov 19-Nov PDI-5-COS, C06 R8-85 DW,315,579 Nov Recirc Pump nuts, Pump A 1-16 VT-I 16 N/A 10- 17-Nov 27-Nov NWA 01-035AP DW,315,579 bushings, and washers Nov RPV Spare Flange 0 deg. 5361-5 VT-I 16 N/A 10- 17-Nov 27-Nov N/A 01-035AN Refuel Fir.

Nov RPV Spare Flange 180 deg. VT-i 16 N/A 10- 17-Nov 27-Nov N/A 01 -035Aa Refuel Flr.

Nov B-G-2 Bolting 2" and Less FBC-E51 -2192-01 FE Flange 2192-5 VT-i 16 N/A 1-Nov 17-Nov 27-Nov N/A 01-035A DW,360,594 ^ Completed visual FBC-B21-5352-01 L SRV Flange 5352-5 VT-i 16 NIA 1-Nov 17-Nov 27-Nov N/A 01 -035B DW,360,594 examination of B21-FO13L-VBB SRV Bonnet 5352-5 VT-i 16 NIA 1-Nov 17-Nov 27-Nov N/A 01-035C DW,39,613 bolting per surveillance

.. .DetroitEdison Co.,¢..2000 2nd Ave., Detroit, MI 48226 . -.-. .....-- " - .... . .

Ferni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 24

Systcomp 10 Description ISO Exams Procedure Cal Std Comp L III ANII Cal Sheet Data Sheet Report Loc/Az/EI Remarks B-G-2 Bolting 20 and Less FBC-B21 -5353-01K SRV Flange 5353-5 VT-i 16 N/A 1-Nov 17-Nov 27 Nov N/A 01-035D DW,39,613 43.000.014.

B21 -FO13K-VBB SRV Bonnet 5353-5 VT-1 16 N/A 1-Nov 17-Nov 27-Nov N/A 01-035E DW,70,613 FBC-B21 -5353-01 G SRV Flange 5353-5 VT-i 16 N/A 1-Nov 17-Nov 27-Nov N/A 01-035F DW,70,613 B21-FO13G-VBB SRV Bonnet 5353-5 VT-i 16 N/A 1-Nov 17-Nov 27-Nov N/A 01-035G DW,38,613 B21-F028B-VBB B Une Outboard MSIV 5353-5 VT-i 16 N/A 1-Nov 17-Nov 27-Nov N/A 01- 35H DW,38,613 FBG-B21-5354-01 B SRV Flange 5354-5 VT-i 16 N/A 1-Nov 17-Nov 27-Nov N/A 01-035I DW,298,613 B21-F013B-VBB SRV Bonnet 5354-5 VT-i 16 N/A 1-Nov 17-Nov 27-Nov N/A 01-035 DW,298,613 B21-FO28D-VBB D Une Outboard MSIV 5353-5 VT-i 16 N/A 31- 17-Nov 27-Nov N/A 01-035K Stm,F12,599 Oct E21-F006A-VBB CS Inbd Check 3052-5 VT-I 16 N/A 9-Nov 17-Nov 27-Nov N/A 01-035L DW,210,627 E41-F003-VBB HPCI Otbd ISO Valve 2297-5 VT-1 16 N/A 31- 17-Nov 27-Nov N/A 01-035M Strn,F12,587 Oct G33-F001-VBB RWCU Inbd Iso 3096-5 VT-i 16 N/A 1-Nov 17-Nov 27-Nov N/A 01-035N DW,229,603 G33-F120-VBB RWCU to FW Ck 3536-5 VT-1 16 N/A 1-Nov 17-Nov 27-Nov N/A 01-0350 Strn,F12,587 B21-FO1 A-VBB FW A Manual Iso 3537-5 VT-1 16 N/A 1-Nov 17-Nov 27-Nov N/A 01-035P DW,350,603 B-H RPV Integral Attachment Welds 3-306/4-309 Skirt Weld 10 percent of length 5360-5 MT 2 N/A 4-Nov 6-Nov 19-Nov N/A MT-025 R8-52 Blo Annulus 3-306/4-309 Skirt Weld 10 percent of length 5360-5 UT 7 4-Nov 6-Nov 19-Nov ISI-210-C07, UT12 R8-52 Blo Annulus C08, C09 1-324A Stabilizer 5360-5 MT 2 N/A 13- 14-Nov 16-Nov N/A MT-029 R8-94 DW,0,647 Nov

.. I Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226.

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 25

Sys/Camp ID Description ISO Exams Procedure Cal Std Camp LI" ANII Cal Sheet Data Sheet Report Loe/Az/El Remarks B-H RPV Integral Attachment Welds B"O CRD Housing Welds CRDH-X02-Y27-W1 Peripheral Housing Weld PT 1 N/A 9-Nov 10-Nov 18-Nov N/A PT-004 R8-80 DWUV CRDH-X02-Y27-W2 Peripheral Housing Weld PT 1 N/A 9-Nov 10-Nov 18-Nov W/A PT-005 R8-81 DWUV

-/-

• - 19 + -. - .. . ~. 1I. .11.i . I...

-. I--,...O. . Detroit Edison Co., 2000 2nd Ave., Detroit, MI .48226 . .-

Fermi 2 Nuclear Power Plant 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 26

C-A Vessel Shell Welds Vol.

SW-El1-D2-HX-l1 Shell to Flange 5370-5 UT 14 CS-80 30- 2-Nov 16-Nov ISI-350-C03 UT03, UT04, R8-34 RB1,B9, Oct ISI-215-C02 UT05 C-B Vessel Nozzle to Shell Welds Vol.I Surf.

SW-E11-D2-HX-01 Inlet Nozzle to Head 5370-5 UT 14 CS-80 30- 1-Nov 16-Nov ISI-350-COI UT01, UT02 R8-13 RB1,B9, Oct IS1-215-COI SW-El1-D2-HX-01 Inlet Nozzle to Head 5370-5 MT 2 29- 1-Nov 16-Nov MT-009 R8-13 RB1,B9, Oct C-B Vessel Inside Radius Vol.

SW-Eli-D2-HX-01 IRS Inlet Nozzle to Head UT 13 CS-81 30- 1-Nov 15-Nov ISI-211-CoI UTOl R8-30 RB11,B9, Oct C-C Vessel Integral Attachment Surf.

SW-Ell-D2-HXS-05 Upper Shell Stiffener Weld MT 2 31- 1-Nov 16-Nov MT-013 R8-20 RBI .89, Oct SW-El I-D2-HXS-06 Lower Shell Stiffener Weld MT 2 31- 1-Nov 16-Nov MT-012, MT- R8-19 RB13819, CARD 01-20653 Oct 012A: Reportable Ind.

SW-El I-D2-HXS-07 Support Ring MT 2 31- I-Nov 16-Nov MT-014 RB-21 RBI13.9, Oct

'- - - "-.-._.'_'___.__ , . . .S~.Daetroit Edison Co., 2000 2nd Ave., Detroit,.Ml. 48226 Femi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MT 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 27

Sys/Comp 10 Description ISO Exams Procedure Cal Std Comp L III ANII Cal Sheet Data Sheet Report Loc/Az/El Remarks C-C Vessel Integral Attachment Surf.

SW-Ell-D2-HXS-09 Stiffener Plate MT 31- 1-Nov 16-Nov MT-015 R8-22 RBl ,B9, Oct SW-Eli -D2-HXS-10 Stiffener Plate MT 31- 1-Nov 16-Nov MT-016 R8-23 RBl ,B9, Oct SW-Ell-D2-HXS-11 Stiffener Plate MT 31- 1-Nov 16-Nov MT-017 R8-24 RB13,B9, Oct SW-Ell-D2-HXS-12 Stiffener Plate MT 31- 1-Nov 16-Nov MT-018 R8-25 RB13,B9, Oct SW-El1-D2-HXS-21 Stiffener Plate MT 31- 1-Nov 16-Nov MT-019 R8-26 RB,1,B9, Oct SW-El1-D2-HXS-22 Stiffener Plate MT 31- 1-Nov 16-Nov MT-020 R18-27 RB,1,B9, Oct SW-E 1-D2-HXS-23 Stiffener Plate MT 31- 1-Nov 16-Nov MT-02 R8-28 RB31,B9, Oct SW-Ell-D2-HXS-24 Stiffener Plate MT 31- 1-Nov 16-Nov MT-=2 RB-29 RB31,B9, Oct C-F-I Piping Circumferential Welds Surf.

FW-C41-2979-72S73 2' Elbow to Pipe 2979- PT 22- 26-Oct 16-Nov PT-l01 RB-02 RB4,668 5 Oct FW-C41-2979-2S3 2' Elbow to Reducer 2979- PT 31- 1-Nov 11-Nov PT-003 R8-33 RB2,C12,63 5 Oct 3 FW-C41-2979-l S2 2' Reducer to Pipe 2979- PT 31- 1-Nov 11-Nov PT-002 R8-32 RB2,C12,63 5 Oct 3 C-F-2 Piping Circumferential Welds Vol.i Surf. I VT FW-El 1-3146-5WO 18' Elbow to Valve 3146- MT 25- 29-Oct 16-Nov MT-=0 R8-03 Tor,B13,579 5 Oct FW-E11-3146-5WO 3146- UT CS-40 25- 29-Oct 16-Nov PDI-1.-C0 C02 UTOl R8-03 5 Oct SW-El 1-3153-13WD 24' Pipe to Elbow 3153- MT 24- 29-ct 16-Nov MT-006 R8-07 SW 5 Oct Ouad,543Y SW-E1I-3153-13WD .375' Std. 3153- UT PD1l-Alt 25- 29-ct 16-Nov PDI-1-C06, C07, UT03 R8-07 5 Oct C08 FW-E1 1-3159-OWl 12'Wol to Pipe 3159- MT 26- 31 -Oct 16-Nov MT-008 R8-0 Tor, 813,575 5 Oct FW-E1 1-3159-OWI .406 Schd. 40 3159- UT PDI1-Alt 26- 31-Oct 16-Nov PDI-1-C09, C1O, UT04 R8-09 5 Oct ClI, C12

. -.. 1... ."'. _; I - . p. ..... - -,- , _ - rt__ Detroit Edison Co.,200O02nd Ave., Detroit, M 48226. .X .., - ..

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RIV) 28

Sys/comp ID Description ISO Exams Procedure Cal Std Comp L III ANII Cal Sheet Data Sheet Report LocdAz/EI Remarks C-F-2 Piping Circumferential Welds Vol. 1 Surf. I VT SW-E21-3145-9WD 10" Elbowto Pipe 3145-5 VT-i 17 31- 31-Oct 16-Nov VT-001 R8-16 Tor,320,577 Oct SW-E21-3147-5WJ 14" Pipe to Elbow 3147-5 MT 2 23- 29-ct 16-Nov MT-O03 R8-04 SE Oct Quad,549Y SW-E21-3147-5WJ .438 Schd. 40 3147-5 UT 3 PDI1-Alt 24- 29-Oct 16-Nov PDI-1-C03, C04 UT02 R8-04 Oct SW-E21-3147-19WB 12" Elbowto Pipe 3147-5 MT 2 23- 29-Oct 16-Nov MT-004 R8-05 RB2,"C11,62 Oct 8 SW-E21-3147-19WB 3147-5 UT 3 CS-15 27- 29-ct 16-Nov PDI-l-C05 UTOS R8-05 Oct SW-E21-3148-5WD 20" Pipe to WOL 3148-5 MT 2 26- 27-Oct 11-Nov MT-005 Re-06 NE Oct Quad,541 FW-E41-3162-11WO & 24' Elbow to Pipe 3162-5 VT-i 17 29- 31-Oct 16-Nov VT-003 R8-18 Tor,G1 1,560 LD Oct SW-E41-3162-1 1WC 24" Elbow to Reducer 3162-5 VT-i 17 29- 31-Oct 16-Nov VT-00O2 R8-17 Tor,G11,560 Oct FW-N30-3259-4W0 24" Pipe to Valve 3259-5 MT 2 31- 1-Nov 16-Nov MT-024 R8-31 TB,L12,632 Oct FW-N30-3259-4W0 3259-5 UT 3 CS-9 31- 1-Nov 16-Nov ISI-35GC-02 UTO6i. UT07 R8-31 Oct PDI-C13, C14 FW-T48-04-2095-19W0 8" Pipe to Tee 2095-5 MT 2 19- 22-Oct 11-Nov MT-001 R8-01 RB1,B13,59 Oct 4 SW-El 1-3151-8WD 24" Pipe to Weldolet 3151-5 MT 2 28- 27-Oct 16-Nov MT-007 R8-08 Tor,B12,575 Oct SW-N30-3258-13WB 26" Pipe to Sweepolet 3258-5 MT 2 29- 30-Oct 16-Nov MT-010 R8-14 Stm,F12,598 Oct

,..1-111.--

<. .. -. I -1 . .. I I".. *.. Detroit Edison Co, 2000 2nd Ave.,IDetroit, Ml, 48226 Semi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 29

ANSI B31.1 GL 88-01 Category D FW-N21-3109-18W0 3109-1 UT 3/4 CS- 5-Nov 7-Nov 17-Nov PDI-1-C23, C24, UTI1, UT12 R8-56 TB3,P5,645 86/SSCL C25

-87 PDI-2-C10, Ct1, C12 SW-N21-01-B002-AWSE 3109-1 UT 3/4 Cs- 5-Nov 7-Nov 17-Nov PDI-1-C20, C21, UTO8, UT0g, R8-55 TB3,P5,645 86/SSCL C22 UTlO

-87 PDI-2-C07, C08, Cog FW-N2D-3105-OW13 3105-1 UT 3t4 CS- 10- 14-Nov 15-Nov PDI-1-C36, C37, UT19, UT20 R8-89 TB2,P4,623 11/SSCL Nov C38 UT17

-88 PDI-2-C15, C16, C17 SW-N20-03-BO1O-BWSE 3105-1 UT 3/4 CS- 10- 14-Nov 15-Nov PDI-1-C39, C42 UT21, UT22, R8-90 TB2,P4,623 11/SSCL Nov PDI-2-C18, C19, UT23

-88 C20 UTi5 Procedure Reference Code Procedure Reference Code 39.NDE.001 1 ISI-UT-55 10 39.NDE.002 2 GFRM2-ISI-246 11 PDI-UT-1 3 UNIXDETC 12 PDI-UT-2 4 ISI-UT-211 13 PDI-UT-5 5 ISI-UT-215 14 PDI-UT-6 6 43.000.017 15 ISI-UT-210 7 43.000.014 16 I/UX-PDI-254 8 43.000.019 17 GFRM2-ISI-54 9

....- .. .....- Detroit Edison Co.,2000 2nd Ave. Detroit, Ml48226 . . - .

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 30

2.3 Interval 2, Period 1,RF-07 Examinations Catltem Componenl B-D Reactor Vessel Nozzle Inside Radius Section B3.100 4-31C IRS (NUREG 0619) Inner Radius 5361-5 UT 70287 17-Apr AUT-IR-CO0 R7-01 B3.100 4-316E IRS (NUREG 0619) Inner Radius 5361-5 UT 70287 13-Apr AUT-IR-CO0 R7-02 83.100 4-316F IRS (NUREG 0619) Inner Radius 5361-5 UT 70287 17-Apr AUT-IR-CO1 R7-03 NU)REG 0619 Reactor Vessel Nozzle Inner Bore Region Atugmented 4-316C IBR FW Nozz Inner Bore Region 5361-5 UT 70287 16-Apr AUT4R-CO1 R7-01 Atigmented 4-316E IBR FW Nozz Inner Bore Region 5361-5 UT 70287 13-Apr AUT-IR-CO0 R7-02 At gnmented 4-316F IBR FW Nozz Inner Bore Region 5361-5 UT 70287 16-Apr AUT-IR-CO0 R7-03 B-F RPV / Piping RPV Noz to Safe End B5.10 N5B Dissimilar Metal Nozz-SE 3052-5 UT FER-44,45 12-Apr DETO-C05,C06 R7-04 N5B Core Spray 3052-5 PT N/A 11-Apr PT-05 R7-04 B5.10 2-303H Dissimilar Metal Nozz-SE 5356-5 UT FER-54,56 10-Apr DETC-CO1,002 R7-05 2-303H Recirc Inlet 5356-5 PT N/A 5-Apr PT-03 R7-05 B5.10 4-303A Dissimilar Metal Nozz-SE 5357-5 UT FER-55,57 12-Apr DETC-C03,004 R7-06 4-303A Recirc Suction 5357-5 PT N/A 7-Apr PT-04 R7-06 B5.10 102-304A Dissimilar Metal Nozz-SE 5361-5 UT FER47, AIL1 13-Apr PD1-1-015-17 UT-01 R7-07 13-Apr PDI-2-007-09 102-304A Jet Pump Instrumentation 5361-5 PT N/A 13-Apr PT-06 R7-07 B5.20 5-315 Dissimilar Metal Nozz-SE 5361-5 UT FER28 14-Apr PDI-2-CIO-12 UT-01 R7-08 5-315 Core DP and Liquid Control RI-91 PT NWA 14-Apr PT-07 1`7-08 Detroit Edison Co., 2000 2nd Ave,, Detroit, MI 48226 - I. - . . . .r - . ., . I . I II, 2I.. ".,It II I II Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 31

Catiltem Component ID DESCRIPTION ISO Procedure EXAMS CALSTD COMP CALSHT DATA SHT Report B1-K- Integral Attach For Piping, Pumps, Valves B10.10 SW-PS-2-A2-M1 Pipe Lug Class 1 5352-5 MT N/A 13-Apr MT-17 R7-09 SW-PS-2-A2-AA2 Pipe Lug 5352-5 MT N/A 13-Apr MT-18 R7-10 SW-PS-2-A2-M3 Pipe Lug 5352-5 MT N/A 13-Apr MT-19 R7-11 SW-PS-2-A2-AA4 Pipe Lug 5352-5 MT N/A 13-Apr MT-20 R7-12 C-C Integral Attach For Piping, Pumps, Vaives C3.20 PSFW-E21-3147-301 Class 2 Stanchion to pipe 3147-5 MT N/A 30-Mar MT-02 R7-13 C-F Pressure Retaining Welds In Piping C-F-i/Aug. FW-C41-2979-P 2' pipe to coupling 2979-5 PT N/A 30-Mar PT41 R7-15 C-F-I/Aug. FW-C41-336t-02W1 3' valve to pipe 3361-5 PT N/A 31-Mar PT-02 R7-16 C-F-2/C5.51 FW-Et 1-3146-6W10 20' tee to elbow 3146-5 MT N/A 6-Apr MT-1 I R7-17 FW-E1 1-3146-6W10 20' tee to elbow 3146-5 UT FER-41 8-Apr PDI-1 -C10 UT-01 R7-17 C-F-2/C5.51 FW-E1 1-3146-6WH 24' tee to pipe 3146-5 MT N/A 3-Apr MT-08 R7-18 FW-E1 1-3146-6WH 24' tee to pipe 3146-5 UT FER-43 4-Apr PDI-1-C03 UT-01 R7-18 C-F-2/C5.51 FW-El 1-3158-10WF4 20' pipe to nozzle 3158-5 MT N/A 14-Apr MT-05,05R R7-19 FW-E1 1-3158-10WF4 20' pipe to nozzle 3158-5 UT FER-42 14-Apr PDI-1-Cl 8 R7-19 C-F-2/CS.51 SW-N-30-3258-19WJ 26' pipe to reducer 3258-5 MT N/A 7-Apr MT-12 117-20 SW-N-30-3258-1 9WJ 26" pipe to reducer 3258-5 UT FER-5 8-Apr PDI-1-C09 UT-01 R7-20 C-F-2/C5.52 SW-N-30-3258-19WJLU intersecting long seam weld 3258-5 MT N/A 7-Apr MT-13 117-20 SW-N-30-3258-19WJLU intersecting long seam weld 3258-5 UT FER-5 8-Apr PDI-1-09 UT-02 R7-20 C-F-21C5.51 SW-El 1-3035-SWE 6' tee to reducer 3035-5 MT N/A 8-Apr MT-14 R7-21 C-F-2/C5.51 FW-E 1-3157-OW6 16' pump to expander 3157-5 MT N/A 31-Mar MT-06 R7-22 FW-E1 1-3157-OW6 16' pump to expander 3157-5 UT FER-40 31-Mar PDI-1-C-01 UT-01 R7-22 C-F-2/C5.51 FW-E21-3144-OW1 12' pump to expander 3144-5 MT N/A 30-Mar MT-01 R7-23

.. . - .- .....-Detroit Edison Co., 2000 2nd Ave., Detroit, M 48226-l , .-- .- ,.

1enni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 N8No. 21085 (RPV) 32

Catitem Component ID DESCRIPTION ISO Procedure EXAMS CAL STD COMP CAL SHT DATA SHT Report C-F-2/C5.51 FW-E21-3147-16W17 12' elbowto pipe 3147-5 2 MT N/A 3-Apr MT-0o R7-24 FW-E21-3147-16W17 12' elbow to pipe 3147-5 3 UT PDI -1 Alt. 6-Apr PD1-1-C04-5 UT-01 R7-24 C-F-21C5.51 SW-E21-3149-4WD 20' pipe to tee 3149-5 2 MT N/A 1-Apr MT-07 R7-25 SW-E21-3149-4WD 20' pipe to tee 3149-5 3 UT PDI -1 Alt. 1-Apr PDI C02 UT-01 R7-25 C-F-2VCS.51 FW-E41-3163-7W0 16' pipe to valve 3163-5 2 MT N/A 8-Apr MT-15 R7-26 FW-E41-3163-7WO 16' pipe to valve 3163-5 3 UT FER-85 10-Apr PDI COi UT-01 R7-26 C-F-21C5.51 FW-T48-04-2095-1 1W12 6' pipe to elbow 2095-5 2 MT N/A 30-Mar MT-03 R7-27 C-F-2/C6.51 FW-T48-04-2097-8W9 6' elbow to pipe 2097-5 2 MT N/A 30-Mar MT-04 R7-28 C-F-2/C5.51 SW-T48-04-2097-21WB 8' elbow to pipe 2097-5 7 VT-1 N/A 5-Apr VT-02 R7-29 C-F-2/C5.51 FW-T48-04-2097-20W21 8' pipe to tee 2097-5 2 MT N/A 8-Apr MT-16 R7-30 C-F-2/C5.51 SW-T48-04-2097-25WF 10' elbow to elbow 2097-5 7 VT-1 N/A 5-Apr VT-01 R7-31 C-F-2/C5.81 SW-Eli-3146-5WC 24' pipe to weldolet 3146-5 2 MT N/A 3-Apr MT-10 R7-32 Augmented FW-N20-3107-0W17 20' safe end to pipe (dm) 3107-1 3,4 UT FER-I1, 88 10-Apr PDI- C12-14 UT-01 R7-33 GL 88-01 PDI- C04-06 UT-01 Augmented SW-N20-03-B014-BWSE 20' nozzle to safe end (dm) 31 07-1 3,4 UT FER-11,88 10-Apr PDI--1-012-14 UT-02 R7-34 GL 88-01 PDI-.2-204-06 UT-02 Augmented FW-N20-3105-16W0 20' elbow to safe end (dm) 3105-1 3,4 UT FER-11, 88 6-Apr PDI-.1-006-08 UT-01 R7-35 GL 88-01 PDI- C0I-03 UT-01 Augmented SW-N20-03-B014-AWSE 20' safe end to nozzle (dm) 3105-1 3,4 UT FER-11,88 6-Apr PDI-1--C06-08 UT-02 R7-36 GL 88-01 PDI1-2-C01-03 UT-02 GE recommended Steam Dryer Support Ring Indications 5364-5 9 UT CAL-DSR01 18-Apr SDSSR-CALI/2 Dat-1/2 SDSR exam GE recommended exam Procedure Reference Code Procedure Reference Code 39.NDE.001 1 UNIXDETC 5 39.NDE.002 2 Ferml-800-1/2 6 PDI-UT-1 3 43.000.019 7 PDI-UT-2 4 43.000.004 8

.-. -Detroit Edison Co., 20002nd Ave., Detroit, Ml 48226. ..... .. . 1 . ...__ ., ,,:. ..... .-. . I .

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 33

SECTION 3

SUMMARY

OF REACTOR INTERNAL EXAMINATIONS I

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 34

3. Code Category Code Category B-N-1 and B-N-2 Inspections Interval 2, Period 1, RF-09 Components Techniaue Requirement Results / Remarks Brackets Feedwater Spargers (3) VT-3 EVT-1 BWRVIP-48 NRI Core Spray Piping (4) EVT-1 BWRVIP-48 RI (PB-015 Wear) -

Feedwater Spargers (3) VT-3 NUREG-0619 NRI Nozzles (3) VT-3 NUREG-0619 NRI Core Spray Piping / Welds EVT-1 BWRVIP-18 NRI (Note 1)

Spargers EVT-1 I VT-1 BWRRVIP-18 NRI (Note 1)

Jet Pump Riser Brace EVT-1 / VT-1 ASME/BWRVIP-41 NRI (JP No.3 & 4)

Risers (JP No.3,4 & 7) EVT-1 BWRVIP-41 RI (Note 2)

Assemblies (JP No.3 & 4) EVT-1 BWRVIP-41 NRI (Note 4)

Restrainer Bracket EVT-1 / VT-1/3 SIL 574 / SIL 629 Assemblies (JP No.1-20) RI (Note 6)

Sensing Lines (JP No.3 & 4) VT-3 SIL 420 NRI Nozzle Inner Radius Surfaces VT-1 Relief Request RR-A31 NRI (Note 5) and RR-A31 Top Guide / Core Plate 6 locations Top Guide VT-1 SIL 554 / BWRVIP-26 NRI Shroud Shroud Support EVT-1 BWRVIP-07 / 38 NRI (Note 3)

Gussets EVT-l BWRVIP-07 / 38 NRI (Note 3)

Steam Dryer Assembly 30% VT-3 SIL 474 No change in indications noted Steam Separator Assembly 30% VT-3 N/A NRI Shroud Head Bolts 50% VT-3 SIL 433 NRI Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 35

Notes:

(1) Examined accessible areas of all selected piping welds and components to the extent possible per BWRVIP-18 requirements. Sampling inspections were also performed on sparger welds.

(2) Reinspected indication adjacent to RS-1 weld (1.75") on Jet-Pumps 7 and 8 identified RF-06 (10/98) no change in length observed.

(3) Examined H-8 and H-9 between Jet Pumps 3 and 4. Examined accessible areas of gussets 2 and 15.

(4) All assembly welds visually inspected except for welds DF-3, AD-I 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. Reactor Recirculation outlet (1), Reactor Recirculation intlet (5).

(6) Second cracked tack weld discovered on restrainer screw for Jet-Pump No.15. Crimped screw and installed auxiliary spring wedge as a permanent repair.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 36

Code Category B-N-1 and B-N-2 Inspections Interval 2, Period 1, RF-08 Components Technique Reauirement Results / Remarks Brackets Steam Dryer Support (4) EVT-1 BWRVIP-48 NRI Feedwater Spargers (6) EVT-1 BWRVIP-48 NRI Guide Rod Bracket 0O&180° EVT-l / VT-3 BWRVIP-48 NRI Core Spray Piping (4) EVT-1 BWRVIP-48 NRI Feedwater Spargers (3) VT-3 NUREG-0619 NRI Nozzles (3) VT-3 NUTREG-0619 NRI Core Spray Piping / Welds EVT-1 BWRVIP-18 NRI (Note 1)

Spargers EVT-i/ VT-1 BWRVIP-18 NRI (Note 1)

Jet Pump Risers (JP No.7 & 8) EVT-1 BWRVIP-41 RI (Note 2)

Risers (QPNo.1 & 2) EVT-1 BWRVIP-41 NRI Assemblies (JP No.1 & 2) EVT-1 BWRVIP-41 NRI (Note 4)

Restrainer Bracket EVT-1 I VT-1/3 SIL 574/ SIL 629 Assemblies (JP No.1-20) NRI Sensing Lines VT-3 SIL 420 NRI Dry Tubes 4-SRM VT-1 SIL 409 / NRI 8-IRM VT-1 RICSIL-073 NRI Top Guide / Core Plate 8 locations Top Guide VT-1 SRL 554 I BWRVIP-26 NRI Core Plate Bolts (4 locations) VT-1 SIL 588 I BWRVIP-25 NRI (Note 6)

Shroud Shroud Support EVT-1 BWRVIP-07 / 38 NRI (Note 3)

Gussets EVT-1 BWRVIP-07 / 38 NRI (Note 3)

Steam Dryer Assembly 30% VT-3 SIL 474 No change in indications noted Steam Separator Assembly 30% VT-3 N/A NRI Shroud Head Bolts 50% VT-3 SIL 433 NRI Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 37

Components Technique Requirement IResults Results /I Remarks Remarks Components Technique Requirement Nozzle Inside Radius Sections VT-1 RR-A31 and RR-A32 NRI (Note 5)

(1 mul wire)

RPV Seal Surface N/A Head Flange VT-1 NRI Vessel Flange VT-1 NRI O-Rings VT-I (Direct) NRI Vessel Cladding VT-3 NRI Control Rod Guide Tubes (10) EVT-1/VT-3 BWRVIP-47 NRI Surveillance Specimen Bracket I EVT-1 I VT-3 BWRVIP-48 NRI Lugs Notes:

(1) Examined accessible areas of all welds and components-to the extent possible. BWRVIP baseline inspections were completed RF-06 and RF-07. Sampling inspections were performed on the spargers.

(2) Reinspected indication adjacent to RS-1 weld (1.75") identified RF-06 (10/98) no change in length observed.

(3) Examined approximately 22% of H-8 and H-9 at 00cand 1800 and between Jet Pumps 2 & 3. Examined accessible areas of gussets 1, 2, 3, 11, 12, & 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 folowing 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., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 38

Code Category B-N-1 and B-N-2 Inspections Interval 2, Period 1, RF-07 Components Technique Requirement Results / Remarks Brackets Steam Dryer Support (4) EVT-1 BWRVIP-48 NRI Feedwater Spargers (6) EVT-1 BWRVIP48 NRI Guide Rod Bracket @ 1800 EVT-1 / VT-3 BWRVIP48 NRI Core Spray Piping (4) EVT-1 BWRVIP48 NRI Feedwater Spargers VT-3 NUREG-0619 NRI Nozzles EVT-1 NUREG-0619 NRI Core Spray Piping I Welds EVT-1 BWRVIP-18 NRI (Note 1)

Spargers EVT-1 BWRVIP-18 NRI Jet Pump Risers (JP No.7 & 8) EVT-I BWRVIP-41 RI (Note 2)

Risers (JP No.11-20) EVT-I BWRVIP-41 NRI Assemblies (IP No.11-20) EVT-1 BWRVIP-41 NRI (Note 4)

Set Screw Tack Welds EVT-1 SL 574 NRI Sensing Lines VT-3 SRL 420 NRI Dry Tubes 4-SRM VT-i SE 409/ NRI 8-IRM VT-i RICSL-I073 NRI Top Guide I Core Plate 8 locations Top Guide VT-i SR 554 NRI Core Plate Bolts (4 locations) VT-i SIL 588 RI NRI Shroud H2 Indication EVT-I BWVRVIP-07 No change in indication Shroud Support EVT-I BWRVEP-07 NRI (Note 3)

Gussets EVT-I BVWRVIP-07 NRI (Note 3)

Steam Dryer Assembly 30% VT-3 SIL 474 No change Previous Indications VT-3IUT Indications have shallow depth as expected Steam Separator Assembly 30% VT-3 N/A NRI Shroud Head Bolts 50% VT-3 SIL 433 NRI Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 39

Components Technique Requirement Results / Remarks Control Rod Blade 02-39 EVT-1 CARD 98-17816 Re-look of previous indication - no significant changes.

RPV Seal Surface N/A Head Flange VT-1 NRI Vessel Flange VT-1 NRI O-Rings VT-1 (Direct) NRI Vessel Cladding VT-3 NRI Control Rod Guide Rods EVT-1IVT-3 BWRVIP-47 NRI Notes:

(1) Examined accessible areas of all welds except P-1, which was inaccessible.

(2) Reinspected indication adjacent to RS-1 weld (1.75") identified RF-06 (10/98) no change in length observed.

(3) Examined H-8 and H-9 at 0° and I8 0 only. Examined accessible areas of gussets between Jet Pumps No.11-20.

(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., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 40

SECTION 4

SUMMARY

OF COMPONENT SUPPORT EXAMINATIONS Detroit Edison Co, 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy. Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 41

4.

SUMMARY

OF COMPONENT SUPPORT EXAMINATIONS VT-3 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 Manual for functional testing of snubbers (Ref. Paragraph 5.1.)

4.1 ASME SECTION XI - IWF (Class 1 and 2) Credit for Component Supports for Interval 2, Period 2, Refuel-09.

CLASS COMPONENT SNUBBERS (1) TOTAL SUPPORTS 1 5 30 35 2 21 56 77 3 15 57 72 Other 55 55 NOTE (1) All Snubbers were visually inspected to the requirements of the Technical Requirements Manual 5.1 and ASME Section XI using Level I, Level II and m, VT-3 certified inspectors.

4.2 Technical Requirements Examinations 4.2.1 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 5.1. 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 Changeout was performed on 24 snubbers.

4.2.2 Refuel-08 Examinations

1. VT-3 examinations were performed on all Safety Related and Non Safety Related snubbers per Technical Requirements Manual 5.1. Total examined was 699.

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.

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 42 I

3. Seal Life Changeout was performed on 31 Snubbers.

4.2.3 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 5.1. 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. One additional snubber that failed functional testing during RF-06 was also functionally tested as required by the Technical Requirements Manual.

3. Seal Life Changeout 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.

4.2.4 Preservice 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 refueling outages RF-07, RF-08, and RF-09 (includes seal life changeout).

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 43

SECTION 5 ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE ACTIONS TAKEN Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Comunercial Service Dates 1-23-88 NBNo. 21085 (RPV) 44

ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE ACTIONS TAKEN 5.1 Refuel-09 The 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.

5.1.1 RPV Internals During RF-09 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 inspections on all 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 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, no repairs were required. Additionally, after 0-ring removal and prior to cleaning, the grooves were inspected and heavy silver deposits were noted to have been transferred 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 and Assemblies (No.3& No.4) to comply with the BWRVIP-41 reinspection recommendations.

Reinspection of a previously cracked restrainer set-screw on JP-15 revealed a second cracked tack weld (CARD 03-16929). All 20 Jet Pump 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 JP-15 was staked to prevent backing out and an auxiliary spring wedge was installed per EDP 32499.

During RF-06 a crack approximately 1 3/4" long was identified on the thermal sleeve to elbow weld (RS-1) on the riser of Jet Pumps 7 and 8 at 1200 AZ. This indication was evaluated and found acceptable for continued operation without repair. This indication was reinspected during RF-07, RF-08, and RF-09 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. Re-inspection 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 RF-09.

One additional tie rod on the steam dryer was found to have a cracked tack weld (TR-E-6) similar to those 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 should impact plant performance during the next operating cycle. Internal inspections are, Detroit Edison Co.. 2000 2nd Ave., Detroit, MI 48226 Ferni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 45

achieving their goal of detecting and monitoring 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 During RF-09 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 VUI/PDI procedures continue to be performed for the first time on scheduled weld locations. These more sensitive examinations are identifying a significantly larger number of manufacturing flaws than were reported during previous amplitude based examinations. These more sensitive inspections detected 4 indications/combinations that would have been unacceptable per IWB-35 10. These pre-existing welding flaws were confirmed by review of the construction radiographs and the pre-service UT 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 the flaw will not present a structural or leakage problem during the remaining service-life of the RPV with a projected 20% 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 l-F009-VBB and CARD 03-16366 was initiated. Investigation determihed 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, 03416371, and 03-16372 were initiated for loose bolting during the expanded sample examinations ofEl 1-F06OB-VBB, B21-FO11 B-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 RF-09 NDE. The RPV and piping systenis are in satisfactory condition to support future safe operation of the plant.

5.1.3 Component Supports Several hangers were found with discrepancies between the installed condition and their configuration documents. It was determined that these conditions did not effect 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 acceptance criteria.

Five of the failures were due to grease degradation. The other three failures were due to 4 overload. All snubbers were replaced with rebuilt and tested snubbers. An evaluation of the effect of the failed snubbers on their associated piping found no adverse effects. All required sample expansions were completed to meet the requirements of the Technical Requirements Manual 5.1. Reference the following CARDs: 03-16111, 03-03-16112, 03-16921, 03-16933, 03-16934, 03-16935, 03-16927.

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 46

It Ii 5.2 Refuel-08 The 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 RPV Intemals During RF-08 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 selected augmented inspections identified in Section 3. Fermi's intent was to perform the highest quality visual 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 (No.1& No.2) to comply with the BWRVIP-41 reinspection recommendations.

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 (No. -20) during RF-06 and RF-07, with the exception of welds DF-3, AD-l and AD-2. Inspection of these locations will be conducted during future outages when a technique is developed and qualified.

During RF-06 a crack approximately 1 3/4" long was identified on the thermal sleeve to elbow weld (RS-1) on the riser of Jet Pumps 7 and 8 at 1200 AZ. This indication was evaluated and found acceptable for continued operation without repair. This indication was reinspected during RF-07 and again in RF-08, 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. Re-inspection of this indication will again be performed during RF-09. This crack is similar to indications identified in at least 5 other BWR plants.

Because of recent industry findings, all 20 Jet Pump 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 still appears 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 the 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% 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 Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Ferni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 47

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 RF-08. Visual and ultrasonic inspections will continue to be performed during future outages.

Indications and conditions identified during previous outages were reinspected during RF-08.

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 daring 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.

5.2.2 RPV External Volumetric and ASME Piping Weld Examinations During RF-08 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, 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 i construction radiographs. -

During the performance of Class 2 weld inspections, one service related defect was detected at a stiffener plate weld adjacent to a vessel support ring on the division 2 RHR heat exchanger. The defect 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 repotted on CARD 01-20653 and the defect was ground out and repaired by welding. The repaired'irea was then re-inspected to verify defect removal.

No other service related conditions were noted during RF-08 inspections.

5.2.3 Component Supports Several hangers were found with discrepancies between the installed condition and their f configuration documents. It was determined that these conditions did not effect 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 Detroit Edison Co., 2000 2nd Ave.. Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 48

inspected. One minor discrepancy (loose jamb nut) was found and corrected. It was determined that this did not impact component operability.

5.3 Refuel-07 Nondestructive examinations have verified that RPV and internals piping systems and supports are. in good structural condition and can support safe and reliable operation during this operating cycle.

5.3.1 RPV Internals During RF-07 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% of the Jet Pump risers and assemblies (No.11-20) to comply with BWRVIP-41 inspection recommendations. These inspection points included welds not previously inspected. During RF-06 a crack approximately 1 3/4" long was identified oh the thermal sleeve to elbow weld (RS-1) on the riser of Jet Pumps 7 and 8 at 1200 AZ. This indication was evaluated and found acceptable for continued operation without repair. This indication was reinspected during RF-07 and there was no observable change in length or width.

This indication is within the allowable flaw acceptance tolerance for this location and repair is not necessary. Re-inspection of this indication will again be performed during RF-08. This crack is similar to indications identified in at least 5 other BWR plants.

All accessible and welds and locations on Jet Pumps assemblies No.11-20 were inspected and no recordable indication were identified. A baseline inspection has been completed for all Jet Pump welds (No.1-20) with the exception of welds DF-3, AD-I 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 RF-06. 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 RF-07. In addition, selected linear indications on the steam dryer support ring were ultrasonically inspected to determine the depth. The indications are shallow, less than V" 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 RF-06.

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".

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-2388 NBNo. 21085 (RPV) 49

• 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 h safe and reliable manner.

5.3.2 RPV External Volumetric and ASME Piping Weld Examinations No service related defects were detected during RF-07 by nondestructive examinations performed.

5.3.3 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 did affect operability.

Hangers N30-3258-G02, G03, G08, G1, Gil, GI2, G14,Gi5, 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 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 was determined that this did not impact component operability. The hangers were reset to their cold position.

These conditions were not reportable.

5.4 Refuel-06 5.4.1 RPV Internals During RF-06 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. 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% of the Jet Pump risers and assemblies to comply with BWRVIP inspection recommendations. These inspection points included welds not previously inspected on the risers. A crack approximately 1 3/4" long was identified on the thermal sleeve to elbow weld (RS-1) on the riser of Jet Pumps 7 and 8 at 1200 AZ. This Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1.23.88 NBNo. 21085 (RPV) 50

indication was evaluated and found acceptable for continued operation without repair. ReT-inspection of this indication will be performed during RF-07. This crack is similar to indications identified in at least 5 other BWR plants within the last year. i Inspections of 2 of the 20 original control rod blades identified cracking on the sheath area near the handle on blade 02-39. These indications were evaluated and are not detrimental to the operation of the control blade. However, Reactor Engineering is evaluating future inspection requirements for the additional old style blades. While not a code inspection, these blades are periodically inspected as recommended by General Electric, following the chemistry transient in 1993.

Several new indications were identified on the steam dryer assembly on welds or areas not" previously inspected. These indications are similar to other previously reported indications on the dryer. Both ISI and General Electric evaluated the indications. No repairs were required during RF-06, but recommendations were made to re-inspect the non-safety related dryer assembly, both visually and ultrasonically in future outages.

Indications and conditions identified during previous outages were reinspected during RF-06.

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.

• Shroud head bolt No.9 was replaced because it would not latch.

• RPV internal surfaces - "Bathtub Ring".

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 to address recent industry occurrences of cracking. No indications of cracking were identified.

The Core Shroud was ultrasonically inspected as required by NRC commitment in accordance with the latest techniques and methods included in the BWRVIP inspection standards. Fermi 2 surpassed eight years of hot operating time, as a result inspection of the H3, H4, H5, and H7 welds were required. Inspections were performed using focused phased array ultrasonic techniques. This inspection identified no evidence of IGSCC in the welds and because of the extensive coverage obtained with the GE tooling, reinspection will not be required for 6 years.

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 safe and reliable manner.

5.4.2 External Volumetric and ASME Piping Weld Examinations 7 No service related defects were detected during RF-06 by nondestructive examinations performed.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1.23-88 NBNo. 21085 (RPV) 51

Examinations were encountered with physical limitations that prevented complete code coverage from being achieved. Relief requests have been prepared or are being revised to address all limitations encountered during the First Inspection Interval.

NDE examinations have verified that ASME piping systems are in good structural condition and can support safe and reliable operation during the next operating cycle.

5.4.3 Component Supports Eight component supports were discovered with minor service related discrepancies from the RF-06 inspection population of 138 component supports. Structural integrity evaluations were performed which concluded all component supports satisfied operability requirements.

Therefore, no reportable conditions exist.

5.5 Refuel-05 5.5.1 RPV Internals During RF-05 two new concerns were identified and evaluated. Nine of the twelve SRM / IRM dry tubes were found not to be fully engaged in the top guide, but are sufficiently engaged to remain functional.

One of the two tack welds on a Jet Pump restrainer screw were found to be cracked. As a result, all 80 restrainer screw tack welds were inspected. No additional cracked welds were found.

This condition did not require repair this outage.

Extensive inspection of Core Spray internal piping and spargers was performed to address recent industry occurrences of cracking. No indications of cracking were identified.

Indications identified during previous outages were reinspected during RF-05. The reinspection included the following items:

• Core Shroud ID linear indications above the H2 weld.

• Steam Dryer tie-rod nut to washer tack welds cracks.

• Steam dryer support ring.

• RPV internal surfaces at the "bathtub ring".

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. Internals inspections are achieving their goal of detecting and monitoring degredation and effecting prudent repairs/replacements to maintain the plant in a safe and reliable manner.

Repairs or Replacements Outage(s)

Completed Shroud Head Bolt replacement RF-04, RF-05 Jet-Pump Beam replacement RF-04 Steam Dryer End Panel repair RF-03 welding Detroit Edison Co., 2000 2nd Ave., Detroit. MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 52

5.5.2 Reactor Pressure Vessel External/Volumetric and ASME Piping Weld Examinations No service related defects were detected during nondestructive examinations performed during RF-05. While it is still to early to draw any global conclusions about effectiveness of IGSCC mitigation treatments (IHSI, and MSIP) performed at Fermi, preliminary indications are good.

No IGSCC has been detected to date in any piping welds. Additionally, no evidence of fatigue cracking has been detected in any RPV, piping system, or support welds.

5.5.3 Component Supports Several component supports were found with discrepancies between the existing field configuration versus as-built hanger sketch. Deviation Event Reports were issued to perform structural integrity calculations. These evaluations determined that the existing field configurations did not effect the component operability; no reportable configurations were found.

No additional component supports were examined as a result of these observations.

5.6 Refuel-04 5.6.1 RPV Internals During inspection of the RPV Internals/Internal Components a number of indications were reported to Detroit Edison for review/disposition. The reported conditions are listed as follows:

Core Shroud - Extensive Visual Examination of the Core Shroud outside surface welds was performed following hydrolazing of each weld. The circumferential welds on the outside surface of the Core Shroud were visually examined (VT-1) to the maximum extent possible from the H-I weld through the H-7 weld with no indications being found. The H-8 and H-9 shroud support welds were also examined (VT-3) but from a greater distance and at a greater camera angle. No indications were found.

Core Shroud Inside Surface - The inside surface of the Core Shroud was inspected to the maximum extent on the H-2 through H4 welds (VT-i). No indications were found on the H-3 and H-4 welds on the inside surface of the shroud. Two small indications <I-inch long we'e found at the 1250 azimuth just above the H-2 weld but not in the H-2 weld. These indications were in a general vertical direction, jagged in nature, and tight with no visible separation. These indications appear to be different from indications found at other BWR's and most probably are a result of cold working during the fabrication process. These indications were evaluated against established flaw screening criteria and have no significant effect on the structural integrity of the shroud (reference deviation event report, DER 94-0221).

Corrosion Deposits/Biological Growth Deposits - Unusual surface conditions were identified during IVVI examinations on the unclad feedwater nozzles and also on the RPV cladding near the steam line nozzles 3600 around the vessel. As a result, a sampling dive into the RPV was performed. A diver successfully completed the necessary corrosion product sampling, visual examinations, and exploratory examinations in the Reactor Vessel. Corrosion deposit samnles were removed from both the "C" feedwater nozzle unclad area (1500) and the cladding at approximately the same azimuth. Based on the results of the sampling, there was no evidehce of micro biologically induced corrosion (MIC) in the vessel, although the samples did test positive for the presence of bacteria. (DER 94-0204)

Additionally, the diver found (loose corrosion) on the feedwater nozzles. The deposits were easy to scrape off. There was no base metal attachment to the unclad surfaces. The corrosion Detroit Edison Co., 2000 2nd Ave, Detroit, MI 48226.

Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 53

deposits on the vessel cladding (360°) were found to be more tightly adhered than the deposits on the feedwater nozzles. However, the vessel cladding corrosion deposits have been looked at and have been confirmed that there had been no base metal attack.

No pits or degradation of the cladding were identified. A special hydrolazing nozzle was utilized to remove the corrosion deposits on both the feedwater nozzles and the vessel cladding. The hydrolyzing was 100 percent effective in cleaning the feedwater nozzles and approximately 75 percent effective in removing the deposits on the vessel cladding.

Steam Dryer - Tie Rod Nut/Washer Tack Welds - Many of the 48 tie rod end washers/nuts protrude above the unit end plate surface. Fifteen of the protruding tie rods had cracked tack welds; however, all but 4 of these had at least 2 intact tack welds at each location. The remaining 4 tie rod nut/washers which had failed tack welds did not represent a structural or functional concern. There is little or no concern that these four nuts will back out during the current cycle with the remaining sound welds. Repairs made during RF-03 on the hood to end panel welds were re-inspected and found to be in good condition. (DER 94-0194)

Steam Dryer Support Ring - Two small indications were identified on the steam dryer support ring this outage; one indication was approximately 1/2" in length on the vertical face of the ring, the other indication was 4" - 6" in length on the horizontal face of the support ring. Based on experience with support ring cracking on similar dryers, these indications were caused by IGSCC. The primary source of stress is residual fabrication stress. Based on experience from similar dryers of the same design with more severe cracking, this crack does not present a concern for the structural adequacy of the support ring. (DER 94-0194)

Shroud Head Bolts - All Shroud Head Bolts were examined using Improved Ultrasonic TeAting procedures. Crack-like indications were found in 16 of 48 bolts. The crack location was identical to those found at other BWRs (i.e., at the collar crevice). The 16 cracked bolts wbre replaced with those of a new and more IGSCC crack resistant design. A 17th bolt was replaced since it had a slight bow that precluded reinstallation. The remaining old design bolts which had no indications were reviewed and found to be acceptable for the next operation cycle. These bolts were reinstalled returning the configuration to the original design of 48 bolts. A design review was performed, in part, to determine the structural significance of operating with indications in 16 shroud head bolts. This review determined that only 20 bolts are required to fulfill design requirements. (DER 94-0210)

Jet Pump Hold Down Beams - As a precaution Detroit Edison replaced the (20) Jet Pump liold down beams. This was done as a conservative measure based on recent industry experience with beam cracking and possible deleterious effects from the chemistry transient. Following replacement Detroit Edison performed a baseline pre-service examination of the installed beams prior to plant start-up using the latest available technique for detecting cracking. Of the 20 Jet Pump assemblies, 12 beam bolt assemblies were changed in situ, 7 required that the inlet mixer assembly be removed, and 2 mixer assemblies were removed to permit camera access to the RPV bottom head area. Each mixer which was removed had a camera inserted for RPV bottom area examination. No discrepancies were observed. (DER 93-0643) 5.7 Refuel-03 5.7.1 RPV Internals During inspection of the RPV Internals/Internal Components two cracks were reported to Detroit Edison for review/disposition. The reported conditions are listed as follows:

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 54

Crack Number 1 was located in hood to end plate weld HE-B-1. The crack was approximately 50" long, with a maximum gap of 1/2 inch. The crack ran through the throat of the weld and was caused by high cycle fatigue. This crack is not uncommon to the industry, having occurred at other plants.

Crack Number 2 is located in the end plate of dryer bank "A" just above the weld to the end plate of the drain trough. The crack is in the weld heat affected zone (HAZ) between Tie Rods TR-A-7 and TR-A-8. The crack is caused by Intergranular Stress Corrosion Cracking (IGSCC).

Crack Number 1 was repaired by grinding out the existing failed weld and preparing the base metal edges for the new weld, clamping the crack closed, rewelding the hood to end plate joint, and welding a new reinforcing plate over the replaced/existing weld. With the exception o6f the original failed weld repair, this repair process was repeated at three (3) similar locations where the potential future weld failure was high. This was performed as a preventive measure to preclude future joint failure, higher personnel exposure, and higher future repair costs.

An evaluation was performed on Crack Number 2, and it was determined that this crack did not require repair as there is low probability that this crack will propagate into weld or base metal outside the HAZ. The crack will tend to grow at a slow rate, as the stresses at this crack location during dryer operation are low. Crack Number 2 will continue to be monitored during future outages.

These indications previously identified during inspections performed in RF-01 and RF-02 Were again reinspected with no change in conditions noted. These areas in addition to the cracks identified and repairs performed during RF-03 will be monitored during further inspection of the RPV internals as required by ASME Section XI, Table IWB-2500-1 (B 13.10).

5.7.2 Component Supports I Several hangers were found with discrepancies between the installed condition and their configuration documents. Deviation Event Report (DER) 92-0573 was initiated for evaluation.

It was determined that their nature was such that it did not effect the components operability and was not reportable. No additional supports were inspected as a result of these observations.

5.8 Refuel-02 5.8.1 RPV Internals During inspection of the RPV Internals/Internal Components' an additional indication to the ones previously identified during RF-01 was reported to Detroit Edison for review/disposition. IThe reported indications are listed as follows:

An apparent arc strike was noted on core spray internal piping at 3100. This was not recorded in the previous inspection.

This condition and those previously identified during RF-01 were evaluated using prudent engineering practices and were determined not to be non-conforming to the original design requirement or detrimental to continued service.

Detroit Edison Co.. 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166  :

Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 55

No corrective action was taken to repair these indications. These areas will be monitored during future inspections of the RPV internals as required by ASME Section XL Table IWB-2500-1 (B13.10) 5.8.2 Piping Welds No service related defects were detected during the inspection of piping welds, 2 welds having rejectable indications were reported to Detroit Edison for review/disposition. The reported indications are listed as follows:

Weld SW-El 1-3151-lWH had rejectable surface indications identified during the magnetic particle examination; deviation event report DER 91-0262 was initiated for evaluation.

Weld SW-RD-2-B3-W5LU-B had rejectable surface indications identified during the liquid penetrant examination; DER 91-0234 was initiated for evaluation.

Both welds were subsequently blend ground to remove the indications and reexamined by both surface and volumetric techniques with acceptable results. The initial indications on both welds were most likely left over from construction. No additional welds were inspected as a result of these minor indications.

5.9 Refuel-Ol 5.9.1 RPV Internals During inspection of the RPV Internals/Internal Components several conditions were reported to Detroit Edison for review/disposition. The reported indications are listed as follows:

Tack weld on feedwater sparger bracket at 1800 for attachment nut/pin was not visible.

Unusual surface conditions (arc strikes and pitting) were noted on Loop A Core Spray Piping at approximately 1400. Additional light scratches were noted on both Loop A and Loop B Core Spray Internal Piping.

Small arc strikes were noted on the Core Spray Internal piping/sparger brackets at 15° and q500.

A small arc strike was noted on the Upper Core Spray Sparger (shroud area) at 1450.

The above conditions were evaluated using prudent engineering practices and were determined not to be non-conforming to the original design requirement or detrimental to continued service.

No corrective action was taken to repair these indications. These areas will be monitored during future inspections of the RPV internals as require by ASME Section XI, Table IWB-2500-1 (B13.10) 5.9.2 Component Supports Hanger T48-2097-G21 was found to have insufficient clearances. Deviation Event Report (DER) 89-1315 was initiated for evaluation. It was determined that this was not reportable. The hanger was reworked to provide acceptable clearances as specified on the hanger sketch.

Additional adjacent supports were visually inspected with no discrepancies identified.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newportn Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 56 l

is.

SECTION 6 PROGRAM STATUS, ASME SECTION XI CREDIT - IWB, IWC & IWF Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Comunercial Service Date: 1-23-88 NBNo. 21085 (RPV) 57

6. PROGRAM STATUS, ASME SECTION XI CREDIT - IWB, IWC, & IWF, Interval 2, Period 2, Refuel-09 (Excludes Pressure Testing) 6.1 CATEGORY B-A

6.1.1 CATEGORY

B-A Pressure Retaining Welds in Reactor Vessel ITEM NO: B.1.11 Shell Welds-Circumferential System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RPV 4 4 (Note 1) 0 0%

TOTALS: 4 4 (Note 1) 0 0%

NOTE (1) Relief Request RR-A25 was written to negate the need for examination of these welds beyond the overlap zone of the intersecting longitudinal seam.

6.1.2 CATEGORY

B-A Pressure Retaining Welds in Reactor Vessel rTEM NO: B.1.12 Shell Welds - Longitudinal System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RPV 14 14 7 50%

TOTALS: 14 14 7 50%

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 58

6.1.3 CATEGORY

B-A Pressure Retaining Welds in Reactor Vessel ITEM NO: B.1.21 Head Welds - Circumferential System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RPV 2 2 1 50%

Closure Head RPV 2 1(1) .5 50% 1 Bottom Head TOTALS 4 3 (1) 1.5 50.0%

NOTE (1) Some of these examinations are subject to limitations as identified in ISTINDE Program Plan, Table A. Relief Request RR-A1 documents these limitations.

6.1.4 CATEGORY

B-A Pressure Retaining Welds in Reactor Vessel ITEM NO: B1.22 Head Welds - Meridional System Total Total Examined Examined, Comp Requiring To To Date Examination Date (%)

RPV 13 13 6 46.2% '

Closure Head RPV 17 10(1) 6 60%

Bottom Head TOTALS: 30 23 (1) 12 52.2%

NOTE (1) Some of these examinations are subject to limitations or are inaccessible as identified in ISI/NDE Program Table A. Relief Request RR-AI documents these limitations.

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NMNo. 21085 (RPV) 59

6.1.5 CATEGORY

B-A Pressure Retaining Welds in Reactor Vessel ITEM NO: B 1.30 Shell-To-Flange System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%) (1)'

RPV 1 1 .5 50%

TOTALS: 1 1 .5 50%

NOTES (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 third inspection period. (Ref. IWB-2500-1, Category B-A, Footnote (4)).

6.1.6 CATEGORY

B-A Pressure Retaining Welds in Reactor Vessel ITEM NO: B1.40 Head-To-Flange System Total Total Examined Examined Comp. Requiring To To Date Examination Date 3%)

RPV I 1 -.33 (1) 33.3%

TOTALS: I 1 .33 (1) 33.3%

I Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 60

CATEGORY B-A Totals Item No. Total Examined To Minimum Maximum Requiring Date Required Allowed Examination (2) (1) (2)

(3)

B1.11 4 0(0%) N/A N/A B1.12 14 7 (50%) N/A N/A B1.21 3 1.5 (50%) N/A N/A B1.22 23 12(52.2%) N/A N/A B1.30 1 .5 (50%) N/A N/A B1.40 1 .33 (33.3%) N/A N/A TOTALS: 46 21.3 (46.3%) N/A 67%

NOTES (1) Table IWB-2500-1 allows deferral to the end of the inspection interval. However, i maximum credited/allowed shall not exceed percentages provided in Table IWB-2412-1.

(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 ISlINDE Program Plan A Table. Relief Request RR-A1 documents these limitations.

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 61

6.2 CATEGORY B-D

6.2.1 CATEGORY

B-D Full Penetration Welds of Nozzles in Vessels ITEM NO: B3.90 Nozzle-To-Vessel Welds System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%) (1)

RPV 30 30 17 56.6%

TOTALS: 30 30 17 56.6%

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 IWB-2500-1, Category B-D, Footnote (2)).

6.2.2 CATEGORY

B-D Full Penetration Welds of Nozzles in Vessels ITEM NO: B3.100 Nozzle Inside Radius Section System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%) (1)

RPV 30 30 19 63.3%

TOTALS: 30 30 19 63.3%

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 IWB-2500-1, Category B-D, Footnote (2)).

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 62

CATEGORY B-D TOTALS Item No. Category B-D Totals Examined Minimum Maximum Total Requiring to Required Allowed Examination Date (1) (1)

B3.90 30 17 (56.6%) 25% N/A B3.100 30 19 (63.3%) 25% N/A TOTALS: 60 36 (60%) 25% 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 IWB-2500-1, Category B-D, Footnote (2)).

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Ferni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Cormmercial Service Date: 1-23-88 NBNo. 21085 (RPV) 63

6.3 CATEGORY B-F

6.3.1 CATEGORY

B-F Pressure Retaining Dissimilar Metal Welds ITEM NO: B5.10 RPV Nozzle to Safe End Butt Welds > 4" Dia.

System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RRS 12 4 1 25%

CS 2 2 1 50%

RPV 3 2 1 50%

TOTALS: 17 8 3 37.5%

6.3.2 CATEGORY

B-F Pressure Retaining Dissimilar Metal Welds ITEM NO: B5.20 RPV Nozzle to Safe End Butt Welds < 4" Dia.

System Total Total Examined Examined Comp. Requiring To To Date Examination Date SLC 1 1 1 100%

TOTALS: 1 1 1 100%

6.3.3 CATEGORY

B-F Pressure Retaining Dissimilar Metal Welds iTEM NO: B5.130 Piping Butt Welds > 4" Dia.

System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RHR 3 2 1 50%

CS 2 2 1 50%

RWCU 2 0 0 0%

TOTALS: 7 4 2 50%

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fenni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 64

CATEGORY B-F TOTALS Item No. Category B-F Totals Examined Minimum Maximum Total Requiring to Required Allowed Examination (1) Date B5.10 8 3 (37.5%) (2) (2)

B5.20 1, 1(100%) (2) (2)

B5.130 4 2(50%) (2) (2)

TOTALS: 13 6 (46.1%) 16% 67%

NOTES (1) Risk Informed Inservice Inspection (RIlSI) Program sample size.

(2) Exam percentage requirements are based on Category totals, not item totals. Item percentages are supplied for information only.

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6.4 CATEGORY B-G-1

6.4.1 CATEGORY

B-G-1 Pressure Retaining Bolting Greater than 2" in Dia.

ITEM NO: B6.10 Closure Head Nuts System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RPV 68 68 45 66.2%

TOTALS: 68 68 45 66.2%

6.4.2 CATEGORY

B-G-1 Pressure Retaining Bolting Greater than 2" in Dia.

ITEM NO: B6.20 Closure Studs in Place System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RPV 68 64 (1) 19 29.7%

TOTALS: 68 64 (1) 19 29.7%

NOTES (1) Inspections are performed in conjunction with item No. B6.30. Four (4) studs are removed at each Reactor Refuel.

6.4.3 CATEGORY

B-G-1 Pressure Retaining Bolting Greater than 2" in Dia.

ITEM NO: B6.30 Closure Head Studs when Removed System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RPV 68 4 (1) 4 100%

TOTALS: 68 4(1) 4 100%

NOTES (1) Inspections are performed in conjunction with item No. B6.20. Four (4) studs are removed at each Reactor Refuel.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 66

6.4.4 CATEGORY

B-G-1 Pressure Retaining Bolting Greater than 2" in Dia.

ITEM NO: B6.40 Reactor Vessel Threads in Flange System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RPV 68 68 45 66.2%

TOTALS: 68 68 45 66.2%

6.4.5 CATEGORY

B-G-1 Pressure Retaining Bolting Greater than 2" in Dia.

ITEM NO: B6.50 Reactor Vessel Closure Washers, Bushings (When Removed)

System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

Washers RPV 68 68 45 66.2%

Bushings 68 68 (1) 0 0%

TOTALS: 136 136 (1) 45 33.1%

NOTE (1) Inspection of bushings is only required for connections that are disassembled.

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 67

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 Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RRS 32 32 16 50%

TOTALS: 32 32 16 50%

6.4.7 CATEGORY

B-G-1 Pressure Retaining Bolting Greater than 2" in Dia.

ITEM NO: B6.200 Pumps, Nuts, Bushings and Washers (1)

System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

(1)

RRS 32 32 16 50%

TOTALS: 32 32 16 50%

NOTES (1) Inspections are performed in conjunction with Stud UT inspection per item B6.180.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 68

CATEGORY B-G-1 TOTALS Item No. Total Examined Minimum Maximum Requiring To Date Required Allowed Examination B6.10 68 45 (66.2%) (1) (1)

B6.20 64 19 (29.7%) (1) (1)

B6.30 4 4(100%) (1) (1)

B6.40 68 45 (66.2%) (1) (1)

B6.50 136 (2) 45 (33.1%) (1) (1)

B6.180 32 16(50%) (1) (1)

B6.200 32 16(50%) (1) (1)

TOTALS: 404 190(47%) 16% 67%

NOTES (1) Exam percentage requirement are based on Category totals, not item totals. Item percentages are shown for information only.

(2) Inspection of bushings is only required for connections that are disassembled.

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 69

6.5 CATEGORY B-G-2

6.5.1 CATEGORY

B-G-2 Pressure Retaining Bolting 2" and smaller in Dia..

ITEM NO: B7.10 Reactor Vessel-Bolts, Studs and Nuts System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RPV 3 3 (1) 0 0%

TOTALS: 3 3 (1) 0 0%

NOTES (1) Represents Flanged/Bolted Connections-All bolts, studs and nuts were examined for each flanged connection examined.

6.5.2 CATEGORY

B-G-2 Pressure Retaining Bolting 2" and smaller in Dia.

ITEM NO: B7.50 Piping-Bolts, Studs and Nuts System Total Total Examined Examined Comp. Requiring To To Date Examination Date HPCL 2 2 (1) 2 100%

& RCIC TOTALS: 2 2(1) 2 100%

NOTES (1) Represents Flanged/Bolted Connections-All bolts, studs and nuts were examined for each flanged connection examined.

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6.5.3 CATEGORY

B-G-2 Pressure Retaining Bolting 2" and smaller in Dia.

ITEM NO: B7.60 Pump Bolts, Studs and Nuts, and Seal Bolting System Total Total Examined Examined Comp. Requiring To To Date Examination Date 0%

RRC 2 2 (1) 0 0%

TOTALS: 2 2 (1) 0 0%

NOTES (1) Represents flanged/bolted connections-all bolts, studs and nuts are examined for each connection examined.

6.5.4 CATEGORY

B-G-2 Pressure Retaining Bolting 2" and smaller in Dia.

ITEM NO: B7.70 Valves-Bolts, Studs and Nuts System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

(1) (2)

MS 38 38 18 47.4%

RRS 4 4 2 50%

RHR 10 10 5 50%

CS 6 6 4 66.6%

HPCI 3 3 1 33.3%

RCIC 3 3 2 66.6%

RWCU 9 9 3 33.3%

FW 8 8 4 50%

TOTALS: 81 81 39 48.1%

NOTES (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., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 71

I

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 Total Examined Examined Comp. Requiring To To Date Examination Date (%)

CRD 185 185 (1) 47 sets* 25.4%

TOTALS: 185 185 (1) 47 sets* 25.4%

• 100% of disassembled flange bolting.

NOTES (1) Inspections are only required when CRD Housing Flanges are disassembled (Ref. Table IWB-2500-1, Category B-G-2)

CATEGORY B-G-2 TOTALS Item No. Total Examined To Minimum Maximum Requiring Date Required Allowed Examination (2)

B7.10 3 0(0%) (1) (1)

B7.50 2 2(100%) (1) (1)

B7.60 2 0 (0%) (1) (1)

B7.70 81 39 (48.1%) (1) (1)

B7.80 185 (2) 47 (25.4%) - (1) (1) 273 88 (32.2%) 16% 67%

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.

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6.6 CATEGORY B-H

6.6.1 CATEGORY

B-H Integral Attachments for Vessels ITEM NO: B8.10 Reactor Vessel-Integrally Welded Attachments System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RPV 2 2 .2 10%

Support Skirt Stabilizer 8 1 1 100%

Bracket Welds Top Head 4 4 0 0%

Lifting Lugs TOTALS: 14 7 1.2 17.1%

6.7 CATEGORY B-J

6.7.1 CATEGORY

B-J Pressure Retaining Welds in Piping ITEM NO: B9.11 Circumferential Welds > 4" Dia.

System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

(1)

MS 113 11 5 45.5%

RRS 109 15 5 33.3%

RHR 71 5 3 60%

CS 42 3 0 0%

HPCI 14 2 2 100%

25 RCIC 16 2 2 100%

RWCU 70 7 1 14.3%

FW 123 18 7 38.9%

RPV 5 0 0 N/A TOTALS: 563 63 39.7%

(1) Risk Informed Inservice Inspection (RIISI) Program sample size.

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CATEGORY B-J TOTALS Item No. Total Examined To Minimum Maximum Requiring Date Required Allowed Examination (1) (1)

(63 B9.11 63 25 (39.7%) 16% 67%

NOTES (1) Fermi Risk Informed Inservice Inspection Program sample size.

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 74

6.8 CATEGORY B-K-I

6.8.1 CATEGORY

B-K-1 Integral Attachments for Piping Pumps and Valves ITEM NO: B10.10/ B10.20 Piping-Integrally Welded Attachments System Total Total Examined Examined Comp. Requiring To To Date (1) Examination Date (%)

(2) (3)

All Class 1 13 2 locations 1 location 50%

Piping B10.10 (8 welds) (4 welds)

Pumps B10.20 3 .1 0 0%

TOTALS: 16 3 1 33%

NOTES (1) Total component supports with integral attachments selected for examination per Code Case N-491-1 (2) Total examinations required for integral attachments per Code Case N-509.

(3) One location examined each period.

i Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 75

6.9 CATEGORY B-M-2

6.9.1 CATEGORY

B-M-2 Valve Bodies ITEM NO: B12.50 Valve Body, exceeding 4" Nominal Pipe Size System Total Total Examined Examined Comp. Requiring To To Date Examination Date (1) (%)

MS 23 23 7 30.4%

RRS 4 4 0 0%

RHR 10 10 3 33.3%

CS 6 6 2 33.3%

HPCI 3 3 0 0%

RCIC 1 1 0 0%

RWCU 5 5 0 0%

FW 8 8 6 75%

TOTALS: 60 60 18 (1)

NOTE (1) Per ASME Section XI IWB-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. Therefore, percentages are not applicable.

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6.10 CATEGORY B-O 6.10.1 CATEGORY: B-O Pressure Retaining Welds In Control Rod Housings ITEM NO: B14.10 (2) Reactor Vessel-Welds in CRD Housings System Total Total Examined Examined Minimum Maxi imum Comp. Requiring To To Date Req'd Alic owed Examination Date (%) (%) (3)

RPV 40 8 (1) 2 25% 16% 677%

TOTALS 40 8 (1) 2 25% 16% 67 (3)

NOTE (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: C-A Pressure Retaining Welds In Pressure Vessel ITEM NO: C1.10 Shell Circumferential Welds System Total Total Examined ExaminesI Comp. Requiring To To Date Examination Date (%)

RHR 1 1 1 100%

TOTALS: 1 1 1 100%

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6.11.2 CATEGORY: C-A Pressure Retaining Welds In Pressure Vessel ITEM NO: Cl.20. Head Circumferential Welds System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RHR 1 1 0 0%

TOTALS: 1 1 0 0%

CATEGORY C-A TOTALS Item No. Total Examined Minimum Maximum Requiring To Req'd Allowed Examination Date (%) (%) (1)

C1.10 1 1(100%) NIA N/A C1.20 1 0 (0%) N/A N/A 2 1 (50%) N/A (1) N/A (1)

NOTES (1) Exams scheduled for the I" and 3Yd period.

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6.12 CATEGORY C-B 6.12.1 CATEGORY: C-B Pressure Retaining Welds In Vessels ITEM NO: C2.21 Nozzle-To-Shell (or Head) Weld System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RHR 4 2 1 50%

TOTALS: 4 2 1 50%

6.12.2 CATEGORY: C-B Pressure Retaining Nozzle Welds In Vessels ITEM NO: C2.22 Nozzle Inside Radius Section System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

RHR 4 2 1 50%

TOTALS: 4 2 1 50%

CATEGORY C-B TOTALS Item No. Total Examined Minimum Maximum Requiring To Req'd Allowed Examination Date (%) (1)

C2.21 2 1(50%) NA N/A C2.22 2 1(50%) N/A N/A 4 2(50%) N/A (1) N/A (1)

NOTES (1) Exams scheduled for the 15' and 3'd examination period.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Ferni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 79

6.13 CATEGORY C-C 6.13.1 CATEGORY: C-C Integral Attachments for Vessels, Piping, Pumps and Valves ITEM NO: C3.10 Pressure Vessels System Total Total Examined Examined Comp. (1) Requiring To To Date Examination Date (%)

(2)

RHR 5 1(19 welds) 11 welds 57.9%

TOTALS: 5 1(19 welds) 11 welds 57.9%

NOTES (1) Total component supports with integral attachments welds selected for examination per Code Case N-491-1 (2) Total examinations required for integral attachment welds per Code Case N-509.

6.13.2 CATEGORY: C-C Integral Attachments for Vessels, Piping, Pumps and Valves ITEM NO: C3.20 Piping Integrally Welded Attachments System Total Total Examined Examined Comp. (1) Requiring To To Date Examination Date (%)

(2)

All Class 2 33 3 1 33.3%

Systems TOTALS: 33 3 1 33.3%

NOTES (1) Total component supports with integral attachment welds selected for

- examination per Code Case N-491-1 (2) Total examinations required for integral attachment welds per Code Case N-509.

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CATEGORY C-C TOTALS Item No. Total Examined Minimum Maximum Comp. To Req'd Allowed Requiring Date (%) (%)

Exam C3.10 1 .58 (58%) N/A N/A C3.20 3 - 1(33.3%) N/A N/A 4 1.58 (39.5%) 16% 67%

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6.14 CATEGORY C-F 6.14.1 CATEGORY: C-F-1 Socket Welds (1)

ITEM NO: N/A, NRC Augmented Commitment System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

SLC 131 16 8 50%

TOTALS: 131 16 8 50%

NOTES (1) The Class 2 portion of the Standby Liquid Control System is <4" NPS and is exempt per ASME Section XI. Fermi committed to examine 16 of 131 system, welds 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 / 5.81 Piping Welds > 3/8" in Normal Wall Thickness for Piping-> NPS System Total Total Examined Examined Comp. Requiring To To Date Examination Date (%)

MS 74 6 4 66.6%

CRD 34 3 1 33.3%

RHR 464 34 18 52.9%

CGC 113 6 2 33.3%

HPCI 154 12 4 33.3%

CS 196 15 7 46.7%

Containment Piping (1) 279 23 10 43.5%

TOTALS: 1314 99 46 46.5%

NOTES (1) Containment piping includes augmented selections made in accordance with Relief Request RR-A26.

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CATEGORY C-F TOTALS Total Examined Minimum Maximum Item No. Requiring To Req'd Allowed Examination Date (%) (2) (%) (2)

(1)

C-F-i (C5.11 Augmented) 16 8(50%) N/A N/A C-F-2 (C5.51 & C5.81) 99 46(46.5%) NIA N/A TOTALS: 115 54 (47%) 16% 67%

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.

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6.15 CATEGORY F-A 6.15.1 CATEGORY: F-A Plate and Shell Type Supports ITEM NO: Fl.10-Fl.40 Section System No. System ID Total Examined Examined XI Class Requiring To To Date Examination Date (%)

Class 1 B11 RPV 9 2 22.2%

B21 Steam Supply 8 4 50%

B31 Reactor Recirc 6 3 50%

Ell RHR 3 1 33.3%

E21 CS 3 2 66.7%

E41 HPCI 1 0 0%

E51 RCIC 1 1 100%

G33 RWCU 5 1 20%

N21 Feedwater 5 i '20%

CLASS 1 TOTALS 41 is 36.6%

Class 2 B21 SRV 6 3 50%

Cli CRD 4 3 .75%

Eli RHR 45 23 51.1%

E21 CS 16 6 37.5%

E41 HPCI 14 7 50%

N30 MS 6 4 66.7%

Pil Demin 1 1 400%

T48 GCG 16 8 j50%

CLASS 2 TOTALS 108 55 50.9%

Class 3 Ell RHRSW 14 8 57.1%

P42 RBCCW 1 I 100%

P44 EECW 33 14 42.4%

P45 - EESW 18 7 38.9%

R30 DGSW 10 6 60%

CLASS 3 TOTALS 76 36 47.4%

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TOTAL ALL CATEGORIES:F-A, F1.10-FlA0 Total Examined Examined Minimum Maximum Requiring To To Date (%) Req'd Allowed Examination Date (%) (%)

F-AClass l 41 15 36.6% N/A N/A F-A Class 2 108 55 50.9% N/A N/A F-A Class 3 76 36 47.4% N/A N/A N/A N/A TOTALS: 225 106 47.1% 16% 67% i tI i

I Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) i 85

SECTION 7 UPDATED PROGRAM TABLES Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Ferni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 86

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 XL 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 IOCFR50.55a, 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, Subarticles IWB-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 or licensing 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).

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NOTE A tentative schedule of specific examinations has been completed for the second 10 year interval. All exams are scheduled for inspection in accordance with the rules of ASME Section - XL IWA, IWB, IWC, IWD and IWF, and as augmented by specific commitments (i.e., NUREG 0313). Future 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 acceptable volumetric exams and either PT or MT is acceptable surface exams. Unique weld joint parameters may, of course, dictate more restrictive selection criteria; e.g., high background 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 CHi - PIS Number for the Control Rod Drive System C41 - PIS Number for the Standby Liquid Control System Ell - PIS Number for the Residual Heat Removal System E21 - 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., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 88

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., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 89

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., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 90

Outage Codes

", , y, 9

\ \ E~xam Status "Y" can equal the following codes:

C - = Completed S = Scheduled CP = Completed Partial CPL = Completed Partial Limited efuel Outage Sequential Number Example: 07C = Seventh Refueling Outage, Completed Exam 08S = Eighth Refueling Outage, Scheduled Exam 08CP = Eighth Refueling Outage, Completed Exam, Partial 08CPL = Eighth Refueling Outage, Completed Exam, Partial Limited Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 91

7.1.2 Inservice Inspection Program (Plan) Tables (Component Supports) 7.1.2.1 The accompanying tables list the component supports to be examined during the first inspection interval. The tables are divided into ISI Class - 1,2, and 3 and start with Class - 1. The tables contain the following information:

Code Class: is the ASME class as defined in accordance with the Code of Federal Regulations (10CFR5O.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, Subarticle IWF.

Item Number: NOT USED - Because IWF category is the main selection determining factor for component supports, Item No. was not used to make hanger selections. The item Number depicts inspection points and therefore is more appropriately addressed in inspection procedures. The item Numbers for each category was used to identify the type of visual examination(s) each component support will receive and this information is provided in the tables.

PIS No/System: Identifies the Plant Identification System Number (PIS No.) and the System Title for each group of component supports to be examined.

Isometric/Multiple Loop: Identifies the specific isometric drawing applicable to a particular group of component supports and the Multiple Loop identification No. if applicable.

Unique Identification: Identifies the specific component support subject to examination.

Exam Method - Exam Method Selected: Identifies the code required method of examination (i.e. visual) and the specific examination selected for each component shown (i.e. VT-1, VT-3).

Type: Identifies the type of component support to be examined.

Relief Request: If applicable, indicates the request for relief applicable in accordance with 10CFR50.55a (g) (5) (iii).

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

Remarks: is reserved for additional information to explain, amplify, or provide added details necessary to clarify the examination requirements.

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 92

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 identification those welds that may have additional augmented, regulatory, or PDI requirements applied to them.

NOTE 2 By Detroit Edison Documents NRC-88-0243, NRC-89-0297, and NRC-90-0103, in response to Generic Letter 88-01 and NUREG-0313 Rev. 2, Detroit Edison had committed 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-01-0038 Detroit Edison 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 Risk Informed Inservice Inspection Program for Category A welds, and BWRVIP-75 for all other 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-92-090. The NRC response (TAC No. M84117, 12-18-1992) 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 Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 93

failure of a jet pump hold down beams at another plant, SiL No. 330, Supplements 1 and 2, and RICSIL No. 065 were issued. As a result, during RF04 all jet pump hold down beams were replaced with beam assemblies that are less susceptible to IGSCC than the original assemblies. Subsequent UT and alternative inspections will be performed at future refueling outages based on industry experiences and the recommendations provided in IE Bulletin 80-07, NUREG/CR-3052, and the latest edition of BWRVIP-41.

All beams were reinspected in RF09.

NOTE 4 ASME Section XI Category B-E requires inspection of the external surfaces of 25%

nozzles 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 is identified, 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-491-1. 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 IWF 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 deternine 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 wfll be performed on the Jet Pumps scheduled for inspections during the refueling outage.

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 multiple refracted longitudinal waves (450 and 60° 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 afl axial and circumferential direction followed by a 450 shear wave if indications are identified using refracted longitudinal 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 Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 94

the nozzle bore has not occurred and extended into the low alloy nozzle material.

Beginning with RFO9, 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 RF-06 the Reactor Recirculation Pumps were modified to the 4th generation design configuration. This configuration was designed to mitigate known causes of shaft and cover cracking and provides for ultrasonic inspection of the shaft without requiring complete pump disassembly and removal. This change out also included change out of the 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 SEL No. 415, a supplemental 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 SEL 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.

NOTE 12 Per IE Bulletin 80-13, and SRL No. 289, Revision 1, Supplement 2, a visual inspection is performed on the core spray internal piping each Refuel Outage. Inspection points include those identified in IE Bulletin 80-13 and SEL No. 289, Revision 1, Supplement 2, and BWRVIP-18. The inspection plan will follow the inspection recommendations and frequency provided in BWRVIP-18 as detailed in PEP16, Appendix HI.

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 re-inspections will be based on industry experience and the inspection technique applied. Refer to PEP16, Appendix I.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 95

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 performed from 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 (Ref. NRC-87-0078).

Beginning with RFO8, ASME Section XI, Appendix VyI, Supplement 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 the manual examination process and indications will be recorded for further analysis and resolution.

NOTE 15 Visual inspections for leakage required by ASME Section XI Code Categories B-P, C-H, and D-B is performed using site procedures. Test Packages for all tests performed are developed 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, Eli, E21, E41, E51, G33, N21, and P34.

All components on the following systems are included in the Class 2 inspections: ClI, C41, Eli, E21, E41, G41, G51, Nil, N30, P34, T4804, and T50.

All components on the following systems are included in the Class 3 inspections: Eli, 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 other reasons. 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.

NOTE 17 The extent of inspection and frequency for Jet Pump components and welds will follow the recommendations provided in BWRVIP-41. BWRVIP-41 replaced/modified the recommendations of SIL Nos. 551 and 574. Inspections will continue to be performed per the recommendations of SRL No. 574 on the adjusting screw tack welds in conjunction with the inspection of those Jet Pumps scheduled for inspection each refuel. Repairs if required will be performed in accordance with the recommendations of SRL 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 Pumps selected for inspection per Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Comrnercial Service Date: 1-23-88 NBNo. 21085 (RPV) 96

the recommendations of RICSIL No. 078 NOTE 18 Per recommendation of SRL 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 re-inspection 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-01) utilizing techniques detailed in BWRVIP "Reactor Pressure Vessel and Internals Examination Guidelines"(BWRVIP-03). SIL No.

572, Revision 1 inspection recommendations have been superceded. 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 additional guidelines for inspection based on years of operation, materials, and conductivity. Based on the above, during RF-06 a baseline inspection of the shroud welds (H-3, H-4, H-5, and H-7) was completed (approximately 90% volumetric coverage) utilizing an augmented 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 per the BWR Core Shroud Evaluation Reports (BWRVIP-01 and GENE-523-A53-0494). Additional references include SRL No. 572, Rev 1, RICSIL No. 054, Rev 1, RICSEL 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, evaluation and/or repair. Additional detail is provided in PEP16, Appendix I.

NOTE 20 Additional augmented examinations were performed during RF04 and changes were made to 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 X1 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 but 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 IWE requirements were imposed. Relief Request RR-A26 documents Detroit Edison's proposed alternative examination requirements.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 97

NOTE 22 Inspections in addition to those listed for item no's B13.10, B13.20, B13.30 and B13.40 will be scheduled and performed as detailed in PEP16. Augmented inspection requirements for selected components and welds are detailed in PEP16 Appendicies, including the implementation of various BWRVIP inspection recommendations.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Ferni 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 98

IS! - NDE Program Rev. 2 Change 3 Page 1 INSERVICE INSPECTION NDE PROGRAM TABLE A

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 2 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks BR-A B1.11 Circunmferrential Shell Weld 1-313 UT All B-A Welds 5360-5 RR-A25 N/A N/A N/A Examined only at intersecting long seams 4-308A UT All B-A Welds 5360-5 RR-A25 N/A N/A N/A Examined only at intersecting long seams 4-308B UT Al B-A Welds 5360-5 RR-A25 N/A N/A N/A Examined only at intersecting long seams 9-307 UT All B-A Welds 5360-5 RR-A25 N/A N/A N/A Examined only at intersecting long seams B1.12 Longitudinal Shell Weld 1-308A UT All B-A Welds 5360-5 08C Note 14 Applies to all Category B-A Welds 1-308B UT All B-A Welds 5360-5 08C 1-308C UT All B-A Welds 5360-5 12S 1-308D UT All B-A Welds 5360-5 12S 15-308A UT All B-A Welds 5360-5 10S 15-308B UT All B-A Welds 5360-5 09C CARD 03-16383, RE10 exam to size indication 10sp No. 124 only 15-308C UT All B-A Welds 5360-5 08C 15-308D UT All B-A Welds 5360-5 11S 2-307A UT All B-A Welds 5360-5 08C 2-307B UT All B-A Welds 5360-5 10S 2-307C UT All B-A Welds 5360-5 09C 2-308A UT All B-A Welds 5360-5 10S 2-308B UT All B-A Welds 5360-5 09C 2-308C UT All B-A Welds 5360-5 lS B1.21 Circumferrential Head Weld 4-319 UT All B-A Welds 5360-5 08CP 09C 08 319C to 2-319E 40%

9 319E to 2-319C 60%

5-306 UT All B-A Welds 5360-5 RR-A1 Inaccessible Weld 5-319 UT All B-A Welds 5360-5 ilS 6-306 UT All B-A Welds 5360-5 08C IOS One sided exam 180-360 Deg, RFO8, 0-180 Deg, RF1O B1.22 Meridional Head Weld 1-306A UT All B-A Welds 5360-5 08C

DETROIT EDISON COMPANY - INSERVICE INSPECTON NDE PROGRAM IST- NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 3 Exams Selection Basis Relief Inspection Period Category / Item IdentificatIon Require Isometric Request 1 2 3 Remarks B-A B1.22 Meridional Head Weld 1-306B UT All B-A Welds 5360-5 lOS 1-306C UT All B-A Welds 5360-5 lOS 1-306D UT All B-A Welds 5360-5 08C 1-306E UT All B-A Welds 5360-5 08C 1-306F UT All B-A Welds 5360-5 12S 1-306G UT All B-A Welds 5360-5 08C 1-306H UT All B-A Welds 5360-5 llS 1-306J UT All B-A Welds 5360-5 09C 1-306K UT All B-A Welds 5360-5 08C 1-319A UT All B-A Welds 5360-5 RR-A1 12S 1-319B UT All B-A Welds 5360-5 08C 1-319C UT All B-A Welds 5360-5 RR-Al 12S 1-319D UT All B-A Welds 5360-5 09C 1-319E UT All B-A Welds 5360-5 RR-Al lOS 1-319F UT All B-A Welds 5360-5 10S 1-3190 UT All B-A Welds 5360-5 RR-Al 12S 1-319H UT All B-A Welds 5360-5 08C 2-306A UT All B-A Welds 5360-5 RR-A1 Inaccessible Weld 2-306B UT All B-A Welds 5360-5 RR-A1 Inaccessible Weld 2-306C UT All B-A Welds 5360-5 RR-A1 Inaccessible Weld 2-306D UT All B-A Welds 5360-5 RR-Al Inaccessible Weld 2-306E UT All B-A Welds 5360-5 RR-Al Inaccessible Weld 2-306F UT All B-A Welds 5360-5 RR-A1 Inaccessible Weld 2-306G UT All B-A Welds 5360-5 RR-A1 Inaccessible Weld 2-319A UT All B-A Welds 5360-5 08C 2-319B UT All B-A Welds 5360-5 08C 2-319C UT All B-A Welds 5360-5 08C 2-319D UT All B-A Welds 5360-5 liS

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 4 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-A B1.22 Meridional Head Weld 2-319E UT All B-A Welds 5360-5 lS B1.30 Shell to Flange Weld 13-308 (from flange) UT All B-A Welds 5360-5 RR-Al 08CP 12SP 0-180 Deg, RF-08: 180-0 Deg, RF-12 13-308 (from shell) UT All B-A Welds 5360-5 RR-A1 08CP 10SP 12SP 1/3 of weld each scheduled Inspection Period B1.40 Head to Flange Weld 3-319 UT/MT All B-A Welds 5360-5 08CP 10SP 12SP 1/3 of weld each scheduled Inspection Period B-D B3.100 RPV Nozzle Inside Radius Section 13-314A IRS VT All BD-IRS 5361-5 RR-A32 08C 13-314B IRS VT All BD-IRS 5361-5 RR-A32 08C 13-314C IRS VT All BD-IRS 5361-5 RR-A32 10S 13-314D IRS VT All BD-IRS 5361-5 RR-A32 09C 13-314E IRS VT All BD-IRS 5361-5 RR-A32 09C 13-314F IRS VT All BD-IRS 5361-5 RR-A32 09C 13-314G IRS VT All BD-IRS 5361-5 RR-A32 09C 13-314HIRS VT All BD-IRS 5361-5 RR-A32 12S 13-314J IRS VT All BD-IRS 5361-5 R~R-A32 11S 13-314K IRS VT All BD-IRS 5361-5 RR-A32 09C 14-316A IRS VT All BD-IRS 5361-5 RR-A32 12S 14-316B IRS VT All BD-IRS 5361-5 RR-A32 08C 15-315 IRS VT All BD-IRS 5361-5 RR-A31I 08C 19-314A IRS VT All BD Nozzles 5361-5 RR-A32 los 19-314B IRS VT All BD Nozzles 5361-5 RR-A32 08C 2-318 IRS UT All BD Nozzles 5361-5 RR-A31 los 4-316A IBR UT A 5361-5 08CA NUREG-0619/GE-NE-523-A71-594 4-316A IRS UT All BD-IRS 5361-5 08CA NUTREG-0619/GE-NE-523-A71-594 4-316B IBR UT A 5361-5 08CA NUREG-0619/GE-NE-523-A7 1-594 4-316B IRS UT All BD-IRS 5361-5 08CA NUREG-0619/GE-NE-523-A7 1-594

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 5 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-Dl B3.100 RPV Nozzle Inside Radius Section 4-316C IBR UT A 5361-5 07CA NUREG-0619/GE-NE-523-A71-594 4-3 16C IRS UT All BD-IRS 5361-5 07CA NUREG-0619/GE-NE-523-A71-594 4-316D IBR UT A 5361-5 08CA NUTREG-0619/GE-NE-523-A71-594 4-316D IRS UT All BD-IRS 5361-5 08CA NUREG-0619/GE-NE-523-A71-594 4-316E IBR UT A 5361-5 07CA NUREG-0619/GE-NE-523-A71-594 4-316E IRS UT All BD-IRS 5361-5 07CA NUREG-0619/GE-NE-523-A71-594 4-316F IBR UT A 5361-5 07CA NUREG-0619/GE-NE-523-A71-594 4-316F IRS UT All BD-IRS 5361-5 07CA NUREG-0619/GE-NE-523-A7 1-594 4-318A IRS VT All BD Nozzles 5361-5 RR-A31 11S 4-318B IRS VT All BD Nozzles 5361-5 RR-A31 liS 5-314A IRS VT All BD-IRS 5361-5 RR-A31 08C 5-314B IRS VT All BD-IRS 5361-5 RR-A31 12S 8-316A IRS VT All BD-IRS 5361-5 RR-A31 08C 8-316B IRS VT All BD-IRS 5361-5 RR-A3 1 08C 8-316C IRS VT All BD-IRS 5361-5 RR-A31 12S 8-316D IRS VT All BD-IRS 5361-5 RR-A3 1 12S B3.90 RPV Nozzle to Vessel Weld 13-314A UT All B-D Nozzles 5361-5 RR-A6 08C 13-314B UT All B-D Nozzles 5361-5 RR-A6 08C 13-314C UT All B-D Nozzles 5361-5 RR-A6 los 13-314D UT All B-D Nozzles 5361-5 RR-A6 08C 13-314E UT All B-D Nozzles 5361-5 RR-A6 09C 13-314F UT All B-D Nozzles 5361-5 RR-A6 09C 13-314G UT All B-D Nozzles 5361-5 RR-A6 08C 13-314H UT All B-D Nozzles 5361-5 RR-A6 12S 13-314J UT All B-D Nozzles 5361-5 RR-A6 11S 13-314K" t- UT All B-D Nozzles 5361-5 RR-A6 08C 14-316A UT All B-D Nozzles 5361-5 RR-A6 los

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 6 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-D B3.90 RPV Nozzle to Vessel Weld 14-316B UT All B-D Nozzles 5361-5 RR-A6 08C 15-315 UT All B-D Nozzles 5361-5 RR-A6 09C 19-314A UT All B-D Nozzles 5361-5 RR-A6 10S 19-314B UT All B-D Nozzles 5361-5 RR-A6 08C 2-318 UT All B-D Nozzles 5361-5 RR-A6 los 4-316A UT All B-D Nozzles 5361-5 RR-A6 08C 4-316B UT All B-D Nozzles 5361-5 RR-A6 08C 4-316C UT All B-D Nozzles 5361-5 RR-A6 09C 4-316D UT AD B-D Nozzles 5361-5 RR-A6 08C 4-316E UT All B-D Nozzles 5361-5 RR-A6 llS 4-316F UT All B-D Nozzles 5361-5 RR-A6 lS 4-318A UT All B-D Nozzles 5361-5 RR-A6 1lS 4-318B UT All B-D Nozzles 5361-5 RR-A6 1lS 5-314A UT All B-D Nozzles 5361-5 RR-A6 08C 5-314B UT All B-D Nozzles 5361-5 RR-A6 12S 8-316A UT All B-D Nozzles 5361-5 RR-A6 08C Note 14 Applies to all Category B-D Welds 8-316B UT All B-D Nozzles 5361-5 RR-A6 08C 8-316C UT All B-D Nozzles 5361-5 RR-A6 12S 8-316D UT All B-D Nozzles 5361-5 RR-A6 12S B-E B4.11 Partial Penetration Vessel Nozzles17-315 VT-2 5361-5 07C, 09C, lis, 08C los 12S 7-315 VT-2 5361-5 07C, 09C, lS, Each Refuel Outage - Note 4 applies to all B-E 08C WoS 12S Items B4.12 Partial Penetration CRD Nozzles I -1

---

3I0-Xm-'Y'--.*1. . ...- -~ VT,-2 -- -'5363- - -07C, 09C, HS,

• 25% Nozzles External Surfaces - Note 4 ^ -- - ,....

08C 10S 12S

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 7 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-E B4.12 Partial Penetration CR1D Nozzles CRDH-Y~--X,- VT-2 5363-5 07C, 09C, 11S, 08C 10S 12S B4.13 Partial Penetration Instrumentation Nozzles 2-315A VT-2 5361-5 07C, 09C, 11S, 08C loS 12S 2-315B VT-2 5361-5 07C, 09C, llS, 08C los 12S 2-315C VT-2 5361-5 07C, 09C, llS, 08C los 12S 2-315D VT-2 5361-5 07C, 09C, lls, 08C los 12S 2-315F VT-2 5361-5 07C, 09C, 1 is, 08C los 12S IH-X-Y_ (55) VT-2 5363-5 07C, 09C, 11s, 08C 10S 12S B-F B5.10 Dissimilar Metal RPV Nozzle to Safe End Weld 4" NPS and Larger 101-304E UT A, RI (GSCC) 5358-5 RR-A30 los Notes 2 & 8 Cat. B 102-304A UT A (IGSCC) 5361-5 07C 12S Notes 2 & 8 Cat. B 2-303G UT A, RI (IGSCC) 5356-5 RR-A30 09C Notes 2 & 8 Cat. B 2-303H UT A, RI (IGSCC) 5356-5 RR-A30 07C 12S Notes 2 & 8 Cat. B 4-303A UT A, RI (IGSCC) 5357-5 RR-A30 07C 12S Notes 2 & 8 Cat. B N-9 UT A, RI (IGSCC) 5361-5 RR-A30 09C Notes 2 & 8 Cat. B NSA UT A, (IGSCC, CC) 3053-5 1OSA Notes 2 & 8 Cat. B NSB UT A, RI (IGSCC, CC) 3052-5 RR-A30 08C Notes 2 & 8 Cat. B B5.130 Dissimilar Metal Piping Butt Weld 4" NPS and Larger SW-El 1-2298-6WC UT A, RI (IGSCC) 2298-5 RR-A30 08C Note I & 2, Category B

-, X--SW-E11-2327-6WC UT . A (IGSCC) ... 23275 Notes I &.2, Category Bz. I -,'; 1 ..'- , .'

SW-E21-3052-4WOX UT A, RI (IGSCC) 3052-5 RR-A30 08C Notes 1, 2 & 8 Category B (IGSCC)

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 8 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-F B5.130 Dissimilar Metal Piping Butt Weld 4" NPS and Larger SW-E21-3053-4WOX UT A (IGSCC) 3053-5 10S Notes 1, 2 & 8 Category B (TGSCC)

B5.20 Dissimilar Metal RPV Nozzle to Safe End Weld Less Than 4" NPS 5-315 PT A R1-91 07C Note 18 5-315 UT A 07C Note 18 B-G-1 B6.10 RPV Cloure Head Nuts Greater Than 2" 326-02, 1 through 68 MT >2 dia." 5362-5 08CP 09CP 1lSP 1/3 EachPeriod B6.180 Pump Studs Greater Than 2" RRC Pump A, Studs 1 through 16 UT >2 dia." 5365-5 08C RRC Pump B, Studs 1 through 16 UT >2 dia." 5365-5 itS B6.190 Pump Flange Surface, When Disassembled RRC Pump A, Flange VT-1 >2 dia." 5365-5 Perform if disassembled RRC Pump B, Flange VT-1 >2 dia." 5365-5 Perform if disassembled B6.20 RPV Closure Studs Greater Than 2", In-place 326-01, 1 through 68 UT >2 dia." 5362-5 08CP 10SP 1lSP 1/3 EachPeriod B6.200 Pump Nuts, Bushings, and Washers RRC Pump A Nuts, Bushings & VT-1 >2 dia." 5365-5 08C Washers Set 1 - 16 RRC Pump B Nuts, Bushings & VT-1 >2 dia." 5365-5 HS Washers Set I - 16 B6.30 RPV Closure Studs Greater Than 2", When Removed 326-01, 1 through 68 MT >2 dia." 5362-5 08C 48-51 Removed w/refueling chute I B6.40 RPV, Threads in Flange 1 through 68 UT >2 dia." 5362-5 08CP 09CP liSP 1/3 Each Period B6.50 RPV Closure Washers and Bushings 326-03, Washers 1 through 68 VT-1 >2 dia." 5362-5 08CP 09CP 1ISP 1/3 Each Period

-Bushings 1through68 6*--.'-1

• VT-i >2dia." a --art . .362.5 I- r1 1. w - - - - a*?1

s. 12S Only required when studsare removed (48L51- - - I removed with refueling shute) I

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM IS! - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 9 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-G-2 B7.10 RPV Bolts, Studs, and Nuts 2" and Less Instrumentation Nozzle VT-i < 2 dia." 5361-5 11S Spare Flange (ODeg) VT-i < 2 dia." 5361-5 its Spare Flange (18ODeg) VT-i < 2 dia." 5361-5 luS B7.50 Piping Bolts, Studs, and Nuts 2" and Less FBC-E41-2297-01 VT-1 < 2 dia." 2297-5 09C FBC-E51-2192-01 VT-1 < 2 dia." 2192-5 08C B7.60 Pump Bolts, Studs, and Nuts 2" and Less RRC Pump A Seal Bolting VT-1 < 2 dia" 5365-5 lOS RRC Pump B Seal Bolting VT-i < 2 dia." 5365-5 12S B7.70 Valve Bolts, Studs, and Nuts 2" and Less B21-FOIOA-VBB VT-i < 2 dia." 3537-5 12S B21-FOIOB-VBB VT-i < 2 dia." 3536-5 09C B21-FO1IA-VBB VT-1 < 2 dia." 3537-5 08C B21-FOIIB-VBB VT-i < 2 dia." 3536-5 09C B21-FO13A-VBB VT-I < 2 dia." 5355-5 07C B21-FO13B-VBB VT-1 < 2 dia." 5354-5 08C B21-FO13C-VBB VT-1 < 2 dia." 5353-5 loS B21-FO13D-VBB VT-i < 2 dia." 5353-5 07C B21-FO13E-VBB VT-i < 2 dia." 5354-5 loS B21-FO13F-VBB VT-i < 2 dia." 5353-5 lOS B21-FO13G-VBB VT-l < 2 dia." 5353-5 08C B21-FO13H-VBB VT-1 < 2 din." 5354-5 12S B21-F0l3J-VBB VT-i < 2 dia." 5354-5 07C B21-FO13K-VBB VT-1 < 2 dia." 5353-5 08C B21-FO13L-VBB VT-i < 2 din." 5352-5 08C B21-FO13M-VBB VT-1 < 2 din." 5352-5 07C I B21-FA13N-VBB C sVT-i --'2 dia."^ i- I . .5352-5 -2.s 51 1 .1.,, -.. . ._.,

w- .-- . .

B21-FO13P-VBB VT-1 < 2 dia." 5355-5 12S

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 10 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-G-2 B7.70 Valve Bolts, Studs, and Nuts 2" and Less B21-FO13R-VBB VT-I < 2 dia." 5354-5 12S B21-F022A-VBB VT-i < 2 dia." 5352-5 11S B21-F022B-VBB VT-1 < 2 dia" 5353-5 12S B21-F022C-VBB VT-I < 2 dia." 5354-5 los B21-F022D-VBB VT-i < 2 dia." 5355-5 12S B21-F028A-VBB VT-I < 2 dia." 5352-5 los B21-F028B-VBB VT-i < 2 dia." 5353-5 08C B21-F028C-VBB VT-i < 2 dia." 5354-5 1iS B21-F028D-VBB VT-1 < 2 dia." 5355-5 08C B21-F032A-VBB VT-1 < 2 dia." 3537-5 09C B21-F032B-VBB VT-i < 2 dia." 3536-5 1is B21-F076A-VBB VT-I < 2 dia." 3537-5 'is B21-F076B-VBB VT-I < 2 dia." 3536-5 11S B31-F023A-VBB VT-i < 2 dia." 5357-5 09C B31-F023B-VBB VT-1 < 2 dia." 5359-5 11S B31-FO31A-VBB VT-i < 2 dia." 5357-5 09C B31-FO31B-VBB VT-I < 2 dia." 5359-5 IS E1I-F008-VBB VT-I < 2 dia." 2299-5 12S El1-F009-VBB VT-I < 2 dia." 2299-5 09C El i-FO15A-VBB VT-i < 2 dia." 2298-5 07C El I-FO15B-VBB VT-1 < 2 dia" 2327-5 liS El -F050A-VBB VT-i < 2 dia." 2298-5 07C El l-F050B-VBB VT-I < 2 dia." 2327-5 07C El l-F060A-VBB VT-I < 2 dia." 2298-5 12S El1-F060B-VBB VT-i < 2 dia." 2327-5 los E1I-F067-VBB VT-I < 2 dia." 2299-5 09C E1 -iF608AVBB - -VT-I ,< 2 dia" 2299-11 HIS E21-PO05A-VBB VT-1 < 2 dia." 3052-5 09C

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 11 Examnis Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-G-2 B7.70 Valve Bolts, Studs, and Nuts 2" and Less E21-F005B-VBB VT-1 < 2 dia" 3053-5 09C E21-FO06A-VBB VT-1 < 2 dia." 3052-5 08C E21-FO06B-VBB VT-1 < 2 dia." 3053-5 07C E21-F007A-VBB VT-1 < 2 dia." 3052-5 12S E21-F007B-VBB VT-i < 2 dia" 3053-5 12S E41-F002-VBB VT-1 < 2 dia." 2297-5 11S E41-F003-VBB VT-i < 2 dia." 2297-5 08C E41-F006-VBB VT-i < 2 dia." 3537-5 10S E51-F007-VBB VT-i < 2 dia." 2192-5 09C E51-F008-VBB VT-1 < 2 dia." 2192-5 07C E51-FO13-VBB VT-1 < 2 dia." 3536-5 lS FBC-B21-5352-OIL VT-1 < 2 dia." 5352-5 08C FBC-B21-5352-0OM VT-i < 2 dia." 5352-5 07C FBC-B21-5352-OIN VT-1 < 2 dia." 5352-5 l1S FBC-B21-5353-OlC VT-i < 2 dia." 5353-5 lOS FBC-B21-5353-O4D VT-I < 2 dia." 5353-5 07C FBC-B21-5353-OIF VT-I < 2 dia." 5353-5 lOS FBC-B21-5353-OlG VT-1 < 2 dia." 5353-5 08C FBC-B21-5353-OIK VT-i < 2 dia." 5353-5 08C FBC-B21-5354-01B VT-i < 2 dia." 5354-5 08C FBC-B21-5354-OIE VT-i < 2 dia." 5354-5 lOS FBC-B21-5354-OlH VT-i < 2 dia." 5354-5 12S FBC-B21-5354-OIJ VT-i < 2 dia." 5354-5 07C FBC-B21-5354-O1R VT-i < 2 dia." 5354-5 12S FBC-B21-5355-OlA VT-i < 2 dia." 5355-5 07C FBC-B21-5355-O1P VT-1 < 2 dia." 5355-5 .12S G33-FOOP1VBB -VT-I <2 dia." 3096-5 08C G33-F004-VBB VT-i < 2 dia." 3096-5 09C

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 12 Exams Selection Basis Relief Inspection Period Category / Item Identilfcation Require Isometric Request 1 2 3 Remarks B-G-2 B7.70 Valve Bolts, Studs, and Nuts 2" and Less G33-FIOO-VBB VT-I < 2 dia." 5351-5 los G33-FIOI-VBB VT-i < 2 dia." 3096-5 12S G33-F102-VBB VT-i < 2 dia." 5351-5 12S G33-FI06-VBB VT-1 < 2 dia." 5351-5 H'S G33-FI20-VBB VT-i < 2 dia." 3536-5 08C G33-F121-VBB VT-i < 2 dia." 3536-5 07C G33-F220-VBB VT-1 < 2 dia." 3536-5 10S B7.80 CRD Bolts, Studs, and Nuts 2" and Less 185 sets of Bolts, Studs and Nuts Visual < 2 dia" 08CP 09CP When Disassembled (24 sets, 08), (23 sets, 09)

VT-I B-H BS1o RPV Integral Attachment Weld 10-324A MT B-H Weld 5360-5 08C Code Case N-509 3-306/4-309 UT B-H Weld 5360-5 O8CP 10% of Weld length 3-306/4-309 MT B-H Weld 5360-5 08CP 10% of Weld length 8-319A MT B-H Weld 5360-5 12S Supplemental exam for weld 1-391A, RR-Al 8-319B MT B-H Weld 5360-S 12S Supplemental exam for weld 1-391C, RR-Al 8-319C I ~

MT B-H Weld 5360-5 los Supplemental exam for weld 1-391E, RR-Al 8-319D MT B-H Weld 5360-5 12S Supplemental exam for weld 1-391G, RR-Al B-J B9.11 Circumferential Piping Weld 4" NPS or Larger 3-316A UT RI CASCS, CC) 3537-5 RR-A30 08C 3-316D UT RI (TASCS, CC) 3536-5 RR-A30 12S 3-316E UT RI (TASCS, CC) 3536-5 RR-A30 HlS 7-316A UT RI 5352-5 RR-A30 08C FW-E 1i-2298-6W0 UT A, (IGSCC) 2298-5 08C Note 2, Category I FW-E11 -2299-2WF3 UT RI 2299-5 RR-A30 09C

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM IST - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 13 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-J B9.11 Circumferential Piping Weld 4" NPS or Larger FW-E1 1-2327-OWI UT RI 2327-5 RR-A30 08C FW-E1 1-2327-OW6 UT RI 2327-5 RR-A30 1lS FW-E1 1-2327-6WO PT A (IGSCC) 2327-5 11S Note 2 Category B FW-E21-3052-4WF1 UT RI 3052-5 RR-A30 12S FW-E41-2297-0W4 MT RI 2297-5 RR-A30 08C FW-E41-2297-2W3 UT RI 2297-5 RR-A30 08C FW-E5 1-2192-1W2 UT RI 2192-5 RR-A30 09C FW-E5 1-2192-2W3 UT RI 2192-5 RR-A30 09C FW-G33-3096-IOWF3 UT A, RI (IGSCC) 5351-5 RR-A30 08C FW-G33-3096-6WF5 UT RI 3096-5 RR-A30 1lS FW-G33-3096-8W1 1 UT RI 5351-5 RR-A30 lOs FW-G33-3096-8W9 UT RI 5351-5 RR-A30 los FW-G33-3096-9WFI UT RI 5351-5 RR-A30 los FW-N21-2336-13WI4 UT RI 3537-5 RR-A30 los FW-N21-2336-14WFI UT RI 3537-5 RR-A30 los FW-N21-2336-15WO UT RI (TASCS) 3537-5 RR-A30 08C FW-N21-2336-16WI9 UT RI 3537-5 RR-A30 lHS FW-N21-2336-3W4 UT RI 3536-5 RR-A30 09C RCIC Selection FW-PS-2-A6 UT RI 5352-5 RR-A30 12S FW-PS-2-C3 UT RI 5354-5 RR-A30 lOS FV.V-RD-2-Al-WI UT RI, A (IGSCC) 5357-5 RR-A30 12S Note No. 2, Cat. B FW-RD-2-A1l1 UT RI, A (IGSCC) 5356-5 RR-A30 11S Note 2, Category B (CRC)

FW-RD-2-A16 UT RI, A (IGSCC) 5356-5 RR-A30 09C Note 2, Category B (CRC)

FW-RD-2-A17 UT A (IGSCC) 5356-5 12S Note 2, Category B(CRC)

FW-RD-2-A9 UT A (IGSCC) 5357-5 08CA Note 2, Category B FW-RD-2-B 1-WI UT RI, A(IGSCC) 5359-5 RR-A30 lS Note 2, Category B UFSAR 5.2.3.2 FW-RD*--B 19 UT A,(IGSCC) - 5359-s5 -lOSA Note 2, Category B (CRC)

FW-RS-2-Al UT A (IGSCC) 5357-5 12SA Note No. 2, Cat. B

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 14 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-J B9.11 Circumferential Piping Weld 4" NPS or Larger N4A UT RI (TASCS, CC) 3537-5 RR-A30 08C N4D UT RI (TASCS,CC) 3536-5 RR-A30 12S N4E UT RI (TASCS, CC) 3536-5 RR-A30 1lS SW-E21-3053-3WN UT RI 3053-5 RR-A30 09C SW-E21-3053-3WP UT RI 3053-5 RR-A30 09C SW-G33-3096-5WD UT RI 3096-5 RR-A30 ilS SW-G33-3096-SWH UT RI 3096-5 RR-A30 llS SW-N21-2335-IWD UT RI 3536-5 RR-A30 09C RCIC Selection SW-N21-2336-13WC UT RI 3537-5 RR-A30 'Os SW-N21-2336-13WE UT RI 3537-5 RR-A30 los SW-N21-2336-15WP UT RI (TASCS) 3537-5 RR-A30 08C SW-N21-2336-lWL UT RI (TASCS) 3536-5 RR-A30 09C SW-N21-2336-1WU UT RI 3536-5 RR-A30 09C RCIC Selection SW-N21-2336-3WC UT RI 3536-5 RR-A30 09C RCIC Selection SW-PS-2-A1-A UT RI 5352-5 RR-A30 08C SW-PS-2-A1-B UT RI 5352-5 RR-A30 08C SW-PS-2-A4-B UT RI 5352-5 RR-A30 12S SW-PS-2-C3-A UT RI 5354-5 RR-A30 1Os SW-PS-2-C3-C UT RI 5354-5 RR-A30 10s SW-PS-2-C3-D UT RI 5354-5 RR-A30 10S SW-PS-2C3-J UT RI 5354-5 RR-A30 08C SW-PS-2-C3-K UT RI 5354-5 RR-A30 08C SW-RD-2-A3-W7 UT RI, A (IGSCC) 5356-5 RR-A30 lis Note 2, Category B SW-RD-2-A4-W2 UT RI 5356-5 RR-A30 lis Note 2, Category A SW-RD-2-B4-W2 UT RL A 5358-5 RR-A30 12S Note 2, Category A SW-RD-2-B8-Wi UT RI,A 5358-5 RR-A30 08C Note 2, Category A SW-RD-2-B8-W2 -" RR-A30 di) ~~~

-UT RlA . -5358-5 '08C' Note 2, Category-AX SW-RS-2-A2-W1 UT A (IGSCC) 5357-5 09C Note No. 2, Cat. B

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 15 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-J B9.11 Circumferential Piping Weld 4" NPS or Larger SW-RS-2-B1-W1 UT RI, A (IGSCC) 5359-5 RR-A30 lHS Note 2, Category B SW-RS-2Al-W1 UT RI, A (IGSCC) 5357-5 RR-A30 12S Note No. 2, Cat. B B-K-1 B10.1O Piping Integral Attachment Weld SW-N21-2336-20WB MT > 5/8 T" 3537-5 1Os ISI Eval.99-055; Code Case N-509 SW-N21-2336-20WC MT > 5/8 T" 3537-5 los ISI Eval.99-055; Code Case N-509 SW-N21-2336-20WD MT > 5/8 T" 3537-5 10S ISI Eval.99-055; Code Case N-509 SW-N21-2336-20WE MT > 5/8 T" 3537-5 1Os ISI Eval.99-055; Code Case N-509 SW-PS-2-A2-AA1 MT > 5/8 T" 5352-5 07C ISI Eval.99-055; Code Case N-509 SW-PS-2-A2-AA2 MT >5/8T" 5352-5 07C ISI Eval.99-055; Code Case N-509 SW-PS-2-A2-AA3 MT > 5/8 T" 5352-5 07C ISI Eval.99-055; Code Case N-509 SW-PS-2-A2-AA4 MT > 5/8 T" 5352-5 07C ISI Eval.99-055; Code Case N-509 B10.20 Pump Integral Attachment Weld SW-B31-5365-Pump A-WA PT > 5/8 T" 5365-5 12S ISI Eval.99-055; Code Case N-509 B-L-2 B12.20 Pump Casing RRC Pump A VT-3 Visual VT-3 5365-5 Only if Disassembled, Note 10 RRC Pump B VT-3 Visual VT-3 5365-5 Only if Disassembled, Note 10 B-M-2 B12.50 Valve Body B21FO1OA VT-3 >4 NPS" 3537-5 08C 09C Only if Disassembled B21FOlOB VTr-3 >4 NPS" 3536-5 07C 09C Only if Disassembled B21FOIIA VT-3 >4 NPS" 3537-5 Only if Disassembled B21FO11B VT-3 >4 NPS" . 3536-5 Only if Disassembled B21FO13A VT-3 >4 NPS" 5355-5 Only if Disassembled B21F0I3B - .- V'-3' )A4 qPS" -5354-5 Ohily if Disassembled B21FO13C VT-3 >4 NPS" 5353-5 08C Only if Disassembled

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 16 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-M-2 B12.50 Valve Body B21FO13D VT-3 >4 NPS" 5353-5 Only if Disassembled B21FO13E VT-3 >4 NPS" 5354-5 Only if Disassembled B21FO13F VT-3 >4 NPS" 5353-5 08C Only if Disassembled B21FO13G VT-3 >4 NPS" 5353-5 Only if Disassembled B21FO13H VT-3 >4 NPS" 5354-5 Only if Disassembled B21FO13J VT-3 >4 NPS" 5354-5 Only if Disassembled B21FO13K VT-3 >4 NPS" 5353-5 08C Only if Disassembled B21FO13L VT-3 >4 NPS" 5352-5 Only if Disassembled B21FO13M VT-3 >4 NPS" 5352-5 Only if Disassembled B21FO13N VT-3 >4 NPS" 5352-5 08C Only if Disassembled B21F013P VT-3 >4 NPS" 5355-5 Only if Disassembled B21FO13R VT-3 >4 NPS" 5354-5 Only if Disassembled B21F022A VT-3 >4 NPS" 5352-5 Only if Disassembled B21F022B VT-3 >4 NPS" 5353-5 Only if Disassembled B21F022C VT-3 >4 NPS" 5354-5 Only if Disassembled B21F022D VT-3 >4 NPS" 5355-5 07C Only if Disassembled B21F028A VT-3 >4 NPS" 5352-5 Only if Disassembled B21F028B VT-3 >4 NPS" 5353-5 07C Only if Disassembled B21F028C VT-3 >4 NPS" 5354-5 07C Only if Disassembled B21F028D VT-3 >4 NPS" 5355-5 Only if Disassembled B21F032A VT-3 >4 NPS" 3537-5 07C Only if Disassembled B21F032B VT-3 >4 NPS" 3536-5 07C Only if Disassembled B21F076A VT-3 >4 NPS" 3537-5 07C Only if Disassembled B21F076B VT-3 >4 NPS" 3536-5 07C 09C Only if Disassembled B3 1F023A VT-3 >4 NPS" 5357-5 Only if Disassembled B31F023B VT-3 >4 NPS" 5359-5 Only if Disassembled B31F03 IA . VT-3 >4 NPSx 5357-5, Only if-Disassembled B31FO31B VT-3 >4 NPS" 5359-5 Only if Disassembled

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 17 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks B-M-2 B12.5o Valve Body El IF008 VT-3 >4 NPS" 2299-5 Only if Disassembled El lF009 VT-3 >4 NPS" 2299-5 Only if Disassembled ElIFOlSA VT-3 >4 NPS" 2298-5 07C Only if Disassembled ElI FOl5B VT-3 >4 NPS" 2327-5 Only if Disassembled El lF050A VT-3 >4 NPS" 2298-5 07C 09C Only if Disassembled El IFO5OB VT-3 ,4NPS" 2327-5 07C 09C Only if Disassembled El lFO60A VT-3 >4 NPS" 2298-5 Only if Disassembled El IF060B VT-3 >4 NPS" 2327-5 Only if Disassembled E1 F067 VT-3 >4 NPS" 2299-5 Only if Disassembled El lF608 VT-3 >4 NPS" 2299-5 Only if Disassembled E21FO05A VT-3 >4NPS" 3052-5 Only if Disassembled E21FOOSB VT-3 >4 NPS" 3053-5 Only if Disassembled E21F006A VT-3 >4 NPS" 3052-5 08C Only if Disassembled E21F006B VT-3 >4 NPS" 3053-5 07C 09C Only if Disassembled E21F007A VT-3 >4 NPS" 3052-5 Only if Disassembled E21FO07B VT-3 >4 NPS" 3053-5 Only if Disassembled E41F002 VT-3 >4 NPS" 2297-5 Only if Disassembled E41F003 VT-3 >4 NPS" 2297-5 Only if Disassembled E41F006 VT-3 >4 NPS" 5352-5 Only if Disassembled ESlFO13 VT-3 >4 NPS" 3536-5 Only if Disassembled G33F001 VT-3 >4 NPS" 3096-5 Only if Disassembled G33F004 VT-3 >4 NPS" 3096-5 Only if Disassembled G33F100 VT-3 >4 NPS" 5351-5 Only if Disassembled G33F102 VT-3 >4 NPS" 5351-5 Only if Disassembled G33F106 VT-3 >4 NPS" 5351-5 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. More detailed techniques are utilized as per BWRVIP I&E Guidelines (Note 22).

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM IS - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 18 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 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).

Access Hole Cover VT-1 Vessel Interior, A 09C Note No. 13 CDP and SLC Line VT-3 Vessel Interior Only if Accessible Control Rod Drive Housings VT-3 Vessel Interior Only if Accessible Core Shroud VT-I Vessel Interior, A 07CP/ Note No. 19 08CP Core Shroud VT-3 Vessel Interior 07CPI Note No. 19 08CP Core Shroud Welds UT Vessel Interior, A 12S Note No. 19 Core Spray Sparger and Interior VT-3 1 Vessel Interior, A 07C/0 09CP Note No. 12 Piping VT-1 8CP Feedwater Sparger VT-3 Vessel Interior 07CP/ 09CP NUREG 0619 at least once every 4 Cycles 08CP Flux Monitor Housings VT-3 Vessel Interior Only if Accessible Guide Rod Holders / Brackets VT-3 Vessel Interior 07CP/ 12SP 08CP Instrumentation Lines VT-3 Vessel Interior, A 07CP/ 09CP Note No. 7 08CP Jet Pump Components VT-3 / Vessel Interior, A 07CP/ 09CP Note No. 17 UT 08CP Jet Pump Hold Down Beams VT-3 Vessel Interior 07CPI 09CP 08CP Jet Pump Hold Down Beams UT Vessel Interior, A 09C Note No. 3 Recirculation Inlet Nozzle VT-3 Vessel Interior 08CP 09CP 10SP Sample Holders VT-3 Vessel Interior 08CP 10SP 12SP Shroud Head VT-3 Vessel Interior 07CP/ 09CP 08CP Shroud Head Bolts UT A Note No. 9 Shroud Head Bolts VT-3 Vessel Interior 07CP/ 09CP .- .. I 08CP

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 19 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 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).

Steam Dryer Assembly I Hold VT-3 Vessel Interior 07CP/ 09CP Note No. 11 Downs 08CP Steam Separator Assy. VT-3 Vessel Interior 07CP/ 09CP 08CP Top Guide VT-3 Vessel Interior 07CP/ 09CP Note No. 16 08CP 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 07CPI 09CP 08CP Surveillance Specimen Bracket VT-I Attachment Weld 07CPI 10SP 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 07CPI 09C Beyond Beltline 08CP Feedwater Sparger Brackets VT-3 Interior Attachment 07CP/

Beyond Beltline 08CP Shroud Support Welds VT-3 / Interior Attachment O9CP llS NoteNo. 19 UT Beyond Betline Steam Dryer Support Lugs VT-3 Interior Attachment 07CPt Beyond Beltline 08CP B13.40 Welded Core Support Structure - 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 Support Assy. & Bolts VT-3 / A 07CP/ BWRVIP-25 UT 08CP Lower Core Shroud VT-3 Core Support, A 07CP 09CP Note No. 19 Peripheral Fuel Support .T-3 A 07CP -09CP .1 . . I 08CP

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 20 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometrlic Request 1 2 3 Remarks B-o B14.10 Welds In CRD Housing CRDH-X02-Y27-W1 PT 109o Peripheral 5363-5 08C Housing Welds CRDH-X02-Y27-W2 PT 10% Peripheral 5363-5 08C Housing Welds CRDH-X02-Y31-Wi PT 10% Peripheral 5363-5 los Housing Welds CRDH-X02-Y31-W2 PT 10% Peripheral 5363-5 10S Housing Welds CRDH-X02-Y35-W1 PT 10% Peripheral 5363-5 ilS Housing Welds CRDH-X02-Y35-W2 PT 10%6 Peripheral 5363-5 lS Housing Welds CRDH-X02-Y39-W1 PT 10% Peripheral 5363-5 12S Housing Welds CRDH-X02-Y39-W2 PT 10% Peripheral 5363-5 12S Housing Welds B-P B15.X Class 1 Pressure Retaining Boundary B21, B31. C41, El1, E21, E41, VT-2 Classl Pressure 07C, 09C, llS X Includes items - B 15.10, B 15.50, B15.60 and E5 1, G33, N21, P34 Retaining Boundary 08C 10S B15.70. Each Refueling Outage; Note 15 B21, B31, C41, Ell, E21, E41, VT-2 Classl Pressure 12S X Includes items -B15.11, B15.51, B15.61 and E51, G33, N21, P34 Retaining Boundary B15.71. Each Interval, Code Case N498-1 C-A C1.10 Shell Circumferential Weld SW-El l-D2-HX-1 1 UT Gross Structural 5370-5 08C Discontinuity C1.20 Head Circumferential V SW-El i-D2-HX-05 UT Gross Structural 5370-5 11S

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DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM 11 - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 21 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks C-B C2.21 Nozzle to Shell (or Head) Weld SW-El 1-D2-1X-01 MT Shell - T >.5" 5370-5 08C SW-El 1-D2-HX-01 UT Shell - T >.5" 5370-5 08C SW-El l-D2-HX-10 UT Shell - T >.5" 5370-5 luS SW-El l-D2-HX-10 MT Shell - T >.5" 5370-5 lS C2.22 Nozzle Inside Radius Section SW-El l-D2-HX-01 IRS I UT Selected Nozzle 08C SW-El l-D2-HX-10 IRS UT Selected Nozzle IHS C-C C3.10 Intregally Welded Attachment (Vessel)

SW-El l-D2-HXS-05 MT 10% 5370-5 08C Code Case N-509 SW-El l-D2-HXS-06 MT 10% 5370-5 08C Code Case N-509 SW-El I-D2-HXS-07 MT 10% 5370-5 08C Code Case N-509 SW-El l-D2-HXS-09 MT 10% 5370-5 08C Code Case N-509 SW-El 1-D2-HXS-10 MT 10% 5370-5 08C Code Case N-509 SW-El l-D2-HXS-1 1 MT 10% 5370-5 08C Code Case N-509 SW-El l-D2-HXS-12 MT 10% 5370-5 08C Code Case N-509 SW-El l-D2-HXS-13 MT 10% 5370-5 09C Code Case N-509 SW-El 1-D2-HXS-14 MT 10% 5370-5 09C Code Case N-509 SW-El 1-D2-HXS-15 MT 10% 5370-5 09C Code Case N-509 SW-El l-D2-HXS-16 MT 10% 5370-5 09C Code Case N-509 SW-El1-D2-HXS-17 MT 10% 5370-5 HtS Code Case N-509 SW-El 1-D2-HXS-18 MT 10% 5370-5 HlS Code Case N-509 SW-El 1-D2-HXS-19 MT 10% 5370-5 HlS Code Case N-509 SW-El l-D2-HXS-20 MT 10% 5370-5 HlS Code Case N-509 SW-El l-D2-HXS-21 MT 10% 5370-5 llS Code Case N-509 SW-El l-D2-HXS-22 MT 10% 5370-5 UlS Code Case N-509 S-El 1-D2-HXS-23 MT 10%.0 5370-5 lis Code Case N-509 SW-El l-D2-HXS-24 MT 10% 5370-5 ils Code Case N-509

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM 1S - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 22 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks C-C C3.20 Intregally Welded Attachment (Piping)

CI1-50-2113-G262A MT 10% 5375-5 1is Code Case N-509 C11-50-2113-G262B MT 10% 5375-5 11S Code Case N-509 Cl1-50-2113-G262C MT 10% 5375-5 11S Code Case N-509 C1 1-50-2113-G262D MT 10% 5375-5 11S Code Case N-509 Cl 1-50-2113-G262E MT 1090 5375-5 11S Code Case N-509 C1I1-50-2113-G262F MT 10% 5375-5 1is Code Case N-509 C11-50-2113-G262G MT 10% 5375-5 1S Code Case N-509 C11-50-2113-G262H MT 10% 5375-5 llS Code Case N-509 PSFW-E21-3147-301 MT 10% 3147-5 07C Code Case N-509 PSFW-E41-3167-IWE MT 10% 3167-5 10S Code Case N-509 PSFW-E41-3167-IWF MT 10% 3167-5 los Code Case N-509 PSFW-E41-3167-lWG MT 10% 3167-5 los Code Case N-509 PSFW-E41-3167-IWH MT 10% 3167-5 los Code Case N-509 SW-E 1-3151-4WE MT 10% 3151-5 12S Code Case N-509 SW-El 1-3151-4WF MT 10% 3151-5 12S Code Case N-509 SW-El 1-3151-4WG MT 10% 3151-5 12S Code Case N-509 SW-El1-3151-4WH MT 10% 3151-5 12S Code Case N-509 SW-El 1-3151-4WJ MT 10% 3151-5 12S Code Case N-509 SW-El 1-3151-4WK MT 10% 3151-5 12S Code Case N-509 C-F-1 Augmente NRC Commitment FW-C41-2979-1 IS12 PT A 2979-5 10S EF2-53.873 FW-C41-2979-17S18 PT A 2979-5 12S EF2-53.873 FW-C41-2979-1S2 PT A 2979-5 08C EF2-53.873 FW-C41-2979-2S3 PT A 2979-5 08C EF2-53.873 FW-C41-2979-5OS5 1 PT A 2979-5 11S EF2-53.873 FW-C41-2979-63S64 PT A 2979-5 09C EF2-53.873 FW-C41-2979-64S65 PT A 2979-5 09C EF2-53.873

DETROIT EDISON COMPANY- INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 23 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks C-F-1 Augmente NRC Commitment FW-C41-2979-72S73 PT A 2979-5 08C EF2-53.873 FW-C41-2979-81S82 PT A 2979-5 12S EF2-53.873 FW-C41-2979-L PT A 2979-5 1os EF2-53.873 FW-C41-2979-P PT A 2979-5 07C EF2-53.873 FW-C41-3361-02W1 PT A 3361-5 07C EF2-53.873 FW-C41-3361-1WF22 PT A 3361-5 12S EF2-53.873 FW-C41-3361-1WF25 PT A 3361-5 l1S EF2-53.873 FW-C41-5058-54S55 PT A 5374-5 09C EF2-53.873 FW-C41-5058-65S66 PT A 5374-5 11S EF2-53.873 C-F-2 C5.51 Circumferential Weld FW-C11-2113-249-B MT R 5372-5 12S FW-C1 1-2113-249-B UT R 5372-5 12S FW-E11-3146-SWO UT MS 3146-5 08C FW-E11-3146-5WO MT MS 3146-5 08C FW-E1 1-3146-6W10 MT MS 3146-5 07C FW-E1 1-3146-6W10 UT MS 3146-5 07C FW-E1 1-3146-OWI MT TE 3146-5 lls FW-E11-3146-OWI UT TE 3146-5 llS FW-E11-3151-lOWO MT TE 3151-5 llS FW-El1-3151-lOWO UT TE 3151-5 FW-EI 1-3151-3WF2 UT MS 3151-5 09C FW-E1 1-3151-3WF2 MT MS 3151-5 09C FW-E1 1-3151-7WI 1 MT MS 3151-5 10S FW-E1 1-3151-7WI I UT MS 3151-5 10S FW-E11-3154-13WO UT TE 3154-5 09C FW-E1 1-3154-13WO MT TE 3154-5 09C FW-E1 1-3154-4WO UT TE 3154-5 12S

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 24 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks C-F-2 C5.51 Circumferential Weld FW-EI 1-3154-4WO MT TE 3154-5 12S FW-EI 1-3157-OW6 MT TE 3157-5 07C FW-EI 1-3157-OW6 UT TE 3157-5 07C FW-EI 1-3158-IOWF4 UT TE 3158-5 07C FW-EI 1-3158-lOWF4 MT TE 3158-5 07C FW-EI 1-3158-1W2 UT R 3158-5 09C FW-EI 1-3158-1W2 MT R 3158-5 09C FW-E1 l-3158-9WF2 MT R 3158-5 09C FW-E11-3158-9WF2 UT R 3158-5 09C FW-EI 1-3159-OWI UT HS 3159-5 08C FW-E1 1-3159-OWI MT HS 3159-5 08C FW-EI 1-3160-OW2 VT-i R 3160-5 RR-A26 1lS Note 21 FW-El 1-3161-4WF5 VT-i R 3161-5 RR-A26 12S Note 21 FW-EI 1-3164-4W5 UT R 3164-5 12S FW-EI 1-3164-4W5 MT R 3164-5 12S FW-EI 1-461 1-iW2 VT-I R 4611-5 RR-A26 12S Note 21 FW-El 1-461 1-IWF2 VT-i R 4611-5 RR-A26 12S Note 21 FW-EI 1-4612-3WF4 VT-i R 4612-5 RR-A26 12S Note 21 FW-EI 1-46124W5 VT-i R 4612-5 RR-A26 lOS Note 21 FW-EI 1-4612-4WFI VT-i R 4612-5 RR-A26 12S Note 21 FW-E l-4612-7W8 VT-i R 4612-5 RR-A26 los Note 21 FW-EI 1-4612-8WF3 VT-I R 4612-5 RR-A26 lOS Note 21 FW-E1 1-4612-9WO VT-i R 4612-5 RR-A26 11S Note 21 FW-E21-3144-OW4 MT TE 3144-5 lOS FW-E21-3144-OW4 UT TR 3144-5 lOS FW-E21-3144-OWI MT TE 3144-5 07C FW-E21-3145-1 IWO Mr R 3145-5 lOS FW-E21-3147-16W17 UT R. 3147-5 07C

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 25 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks C-F-2 C5.51 Circumferential Weld FW-E21-3147-16W17 MT R 3147-5 07C FW-E21-3148-OW8 MT TE 3148-5 12S FW-E21-3148-OW8 UT TE 3148-5 12S FW-E21-3148-7WO MT TE 3148-5 09C FW-E21-3148-7WO UT TE 3148-5 09C FW-E41-3162-1 lWF1 VT-1 R 3162-5 RR-A26 09C Note 21 FW-E41-3162-1 1WF4 VT-I R 3162-5 RR-A26 09C Note 21 FW-E41-3162-1 lWF5 VT-1 R 3162-5 RR-A26 09C Note 21 FW-E41-3162- liWO Vr-i R 3162-5 RR-A26 08C Note 21 FW-E41-3162-1W2 UT R 3162-5 lOS FW-E41-3162-1W2 MT R 3162-5 los FW-E41-3162-9WFO UT Te 3162-5 12S FW-E41-3162-9WFO MT TE 3162-5 12S FW-E41-3163-7WO MT TE 3163-5 07C FW-E41-3163-7WO UT TE 3163-5 07C FW-E41-3163-8WO UT TE 3163-5 lis FW-E41-3163-8WO MT TE 3163-5 11S FW-E41-3167-1W2 MT R 3167-5 12S FW-E41-3167-1W2 UT R 3167-5 12S FW-E41-3167-9WO MT TE 3167-5 IlS FW-E41-3167-9WO UT TE 3167-5 llS FW-E41-3167-OW1 MT TE 3167-5 09C FW-E41-3167-OW1 UT TE 3167-5 09C FW-E41-3169-2WO UT R 3169-5 09C FW-E41-3169-2WO MT R 3167-5 09C FW-E41-3172-OW1 UT TE 3172-5 lOS FW-E41-3172-OW1 MT TB 3172-5 w 1 -1OS, . .,I ,.s b..

FW-E41-3172-OW8 UT R 3172-5 12S

DETROIT EDISON COMPANY. INSERVICE INSPECTION NDE PROGRAM ISI . NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 26 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks C F-2 C551 Circumferential Weld FW-E41-3172-OW8 MT R 3172-5 12S FW-G41-3669-OW9 MT MS 3669-5 12S FW-N30-3259-4WO MT TE 3259-5 08C FW-N30-3259-4WO UT TE 3259-5 08C EW-T48-04-2095-1 IW12 MT R 2095-5 07C FW-T48-04-2095-19WO MT MS 2095-5 RR-A26 08C Note 21 FW-T48-04-2095-7W8 MT R 2095-5 10S FW-T48-04-2097-20W21 MT MS 2097-5 RR-A26 07C Note 21 FW-T48-04-2097-8W9 MT R 2097-5 07C SW-Cl 1-2113-172-A UT R 5375-5 09C SW-Cl 1-2113-172-A MT R 5375-5 09C SW-C1 1-2113-303-A UT R 5372-5 lIS SW-C1 1-2113-303-A MT R 5372-5 liS SW-El1-3035-5WE MT R 3035-5 07C SW-El1-3035-7WB MT R 3035-5 09C SW-El1-3146-6WE UT HS 3146-5 10S SW-El 1-3146-6WE MT HS 3146-5 10S SW-E 11-3146-6WH UT HS 3146-5 07C SW-El 1-3146-6WH MT HS 3146-5 07C SW-El 1-3153-13WD UT R 3153-5 08C SW-Ell-3153-13WD MT R 3153-5 08C SW-El 1-3154-4WC MT R 3154-5 09C SW-El1-3154-4WC UT R 3154-5 09C SW-El 1-3157-IWB UT R 3157-5 12S SW-El1-3157-lWB MT R 3157-5 12S SW-El 1-3158-4WD MT R 3158-5 llS 1.@.

SW-El 1-3158-4WD UT 3158-5 '1lS . -I . ... I I,.1 SW-El1-3158-8WG UT R 3158-5 S11

DETROIT EDISON COMPANY. INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 27 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks C-F-2 C5.51 Circumferential Weld SW-Ell-3158-8WG MT 3158-5 11S SW-Ell-3161-lWH MT 3161-5 12S SW-El 1-31614WB VT-I 3161-5 RR-A26 10S5 Note 21 SW-El1-3161-4WK VT-1 3161-5 RR-A26 12S Note 21 SW-El1-3177-6WD MT 3177-5 l1S SW-E1l1-3177-6WD UT 3177-5 1IS SW-El1-3177-9WE MT 3177-5 09C SW-El 1-3177-9WE UT 3177-5 09C SW-E21-3145-9WD VT-1 3145-5 RR-A26 08C Note 21 SW-E21-3147-15WF UT 3147-5 llS SW-E21-3147-1SWF MT 3147-5 lS SW-E21-3147-15WG MT 3147-5 los SW-E21-3147-1SWG UT 3147-5 los SW-E21-3147-19WB UT 3147-5 08C SW-E21-3147-19WB MT 3147-5 08C SW-E21-3147-5WJ UT 3147-5 08C SW-E21-3147-5WJ MT 3147-5 08C SW-E21-3148-5WD MT 3148-5 08C SW-E21-31494WD MT 3149-5 07C SW-E21-31494WD UT 3149-5 07C SW-E21-3149-6WC UT 3149-5 12S SW-E21-3149-6WC MT 3149-5 12S SW-E21-3149-6WL UT 3149-5 1IS SW-E21-3149-6WL MT 3149-5 lS SW-E41-3162-1lWC VT-I 3162-5 RR-A26 08C Note 21 SW-E41-3162-lWU MT 3162-5 10S SW-E41 3I62-lWU 3162-5 - -- " IOS . '

SW-E41-5373-GW3 MT 5373-5 09C

DETROIT EDISON COMPANY- INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 28 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks C-F-2 C5.51 Circumferential Weld SW-E41-5373-GW3 MT R 5373-5 09C SW-G41-3669-3WB MT R 3669-5 10S SW-N30-3258-13WJ UT MS 3258-5 12S SW-N30-3258-13WJ MT MS 3258-5 12S SW-N30-3258-19WJ MT MS 3258-5 07C SW-N30-3258-19WJ UT MS 3258-5 07C SW-N30-3258-1WJ MT MS 3258-5 los SW-N30-3258-1WJ UT MS 3258-5 10S SW-N30-3258-7WK MT MS 3258-5 09C SW-N30-3258-7WK UT MS 3258-5 09C SW-T48-04-2095-5WD MT R 2095-5 lls SW-T48-04-2095-WSW3 MT R 2095-5 llS SW-T48-04-2097-18WC MT R 2097-5 10S SW-T48-04-2097-20WD MT MS 3258-5 RR-A26 1S Note 21 SW-T48-04-2097-21WB VT-I R 2097-5 RR-A26 07C Note 21 SW-T48-04-2097-25WF VT-1 R 2097-5 RR-A26 07C Note 21 C5.52 Longitninal Weld SW-E41-3162-11WOLD VT-1 R 3162-5 RR-A26 08C Note 21 SW-N30-3258-13W1LU MT 3258-5 12S SW-N30-3258-13WJLU UT 3258-5 12S SW-N30-3258-19WJLU UT 3258-5 07C SW-N30-3258-19WJLU MT 3258-5 07C SW-N30-3258-IWlLU MT 3258-5 10S SW-N30-3258-7WKLU UT 3258-5 09C SW-N30-3258-7WKLU MT 3258-5 09C C5.81 Branch Connection Weld FW l l3146-I5FW01 > -MT - MS ','3146&5 I"T.. 1, I 12S ..-

1, . . .. - .

FW-E11-3157-4WFO1 MT R 3157-5 12S

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 29 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks C-F-2 C5.81 Branch Connection Weld SW-Ell-3146-5WC MT MS 3146-5 07C SW-El1-3146-5WM MT HS 3146-5 10S SW-Ell-3146-7WC MT HS 3146-5 12S SW-El 1-3151-8WD MT HS 3151-5 08C SW-El 1-3160-1WD MT HS 3160-5 09C SW-E21-3144-5WE MT R 3144-5 llS SW-N30-3258-13WB MT R 3258-5 08C C-H C.7X Class 2 Pressure Rett mining Boundary B21 Main Steam VT-2 Class 2 Boundary 5808-1 08C 10S X includes items C7.10, C7.30, C7.50 and 5808-2 C7.70. Perform each Period El I Residual Heat Removal System VT-2 Class 2 Boundary 5813-1 08C 10S X includes items C7.10, C7.30, C7.50 and 5813-2 C7.70. Perform each Period 5813-3 E21 Core Spray System VT-2 Class 2 Boundary 5814 08C lOS X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period E41 High Pressure Coolant VT-2 Class 2 Boundary 5815 08C 10S X includes items C7.10, C7.30, C7.50 and Injection C7.70. Perform each Period G41 Fuel Pool Cooling & Cleanup VT-2 Class 2 Boundary 5819 08C 10S X includes items C7.10, C7.30, C7.50 and System C7.70. Perform each Period G51 Torus Water Management VT-2 Class 2 Boundary 5820 08C 10S X includes items C7.10, C7.30, C7.50 and System C7.70. Perform each Period N30 Main & Reheat Steam S VT-2 Class 2 Boundary 5822 08C lOS X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period P34 Post Accident Sampling VT-2 Class 2 Boundary 5824 08C lOS X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period T48-04 Containment Atmosp VT-2 Class 2 Boundary 5830-1 08C lOS X includes items C7.10, C7.30, C7.50 and Control System 5830-2 C7.70. Perform each Period I-, ' T50 Prinay Containment . I~ 'V-2

' "Class 2Botindary " 5831 ' " 08C 10S- ' X includes iteis C7.'10, C7.30, C7.50 anid'

.... ', 'l .-

, I... .

Monitoring System C7.70. Perform each Period

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 30 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks C-H C7.X Class 2 Pressure Rett filning Boundary B21 Main Steam VT-2 Class 2 Boundary 5808-1 12S X includes items C7.20, C7.40, C7.60 and 5808-2 C7.80. Perform each Interval; Code Case N498-1 CII Control Rod Drive System VT-2 Class 2 Boundary 5810-1 08C los X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C11 Control Rod Drive System VT-2 Class 2 Boundary 5810-1 12S 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 Class 2 Boundary 5811 08C lOS X includes items C7.10, C7.30, C7.50 and C7.70. Perform each Period C41 Standby liquid Control System VT-2 Class 2 Boundary 5811 12S X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 ElI Residual Heat Removal System VT-2 Class 2 Boundary 5813-1 12S X includes items C7.20, C7.40, C7.60 and 5813-2 C7.80. Perform each Interval; Code Case N498-1 5813-3 E21 Core Spray System VT-2 Class 2 Boundary 5814 12S X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 E41 High Pressure Coolant VT-2 Class 2 Boundary 5815 RR-A19 12S X includes items C7.20, C7.40, C7.60 and Injection C7.80. Perform each Interval; Code Case N498-1 G41 Fuel Pool Cooling & Cleanup VT-2 Class 2 Boundary 5819 12S X includes items C7.20, C7.40, C7.60 and System C7.80. Perform each Interval; Code Case N498-1 G51 Torus Water Management VT-2 Class 2 Boundary 5820 12S X includes items C7.20, C7.40, C7.60 and System C7.80. Perform each Interval; Code Case N498-1 N30 Main & Reheat Steam System VT-2 Class 2 Boundary 5822 12S X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 P34 Post Accident Sampling VT-2 Class 2 Boundary 5824 12S X includes items C7.20, C7.40, C7.60 and C7.80. Perform each Interval; Code Case N498-1 T48-04 Containment Atmosphere, VT-2 Class 2 Boundary 5830-1 12S X includes items C7.20, C7.40, C7.60 and Control System 5830-2 C7.80. Perform each Interval; Code Case N498-1 T50 Primary Containment VT-2 Class 2 Boundary 5831 12S X includes items C7.20, C7.40, C7.60 and Monitoring System C7.80. Perform each Interval; Code Case N498-1 D2.10 Pressure Retaining Components

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 31 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks D-B D2.10 Pressure Retaining Components El I Residual Heat RemovalSystem Visual, System Func,tion Class 3 08C 10S 12S Note 15 Perform Each Period; Code Case 498-1 Functional Boundary VT-2 Systems P42 Reactor Building Closed Visual, System Func:tion Class 3 08C 10S 12S Note 15 Perform Each Period; Code Case 498-1 Cooling Water VT-2 Systems P44 Emergency Equipment Visual, System Func,tion Class 3 08C 10S 12S Note 15 Perform Each Period; Code Case 498-1 Cooling Water VT-2 Systems P45 Emergency Equipment Service Visual, System Func,bon Class 3 08C 10S 12S Note 15 Perform Each Period; Code Case 498-1 Water VT-2 Systems R30 Emergency Diesel Generator Visual, System Fun(ction Class 3 08C 10S 12S Note 15 Perform Each Period; Code Case 498-1

& Service Water VT-2 Systems D2.20 Intregal Attachment (Supports and Restraints)

P45-3360-Gil VT-3 Integral 3360-2 11S Attachment Weld D2.40 Intregal Attachment El 1-3184-G08 VT-3 Integral 3184-2 09C Attachment Weld P44-3048-G10 VT-3 Integral 3048-2 07C Attachment Weld N/A N/A ANSI B31.1 Augmented FW-N20-3105-22WO UT NUREG 0313 3105-1 09C Note 2, Category D FW-N20-3105-0W13 UT NUREG 0313 3105-1 08C Note 2, Category D FW-N20-3105-OWlS UT NUREG 0313 3105-1 12S Note 2, Category D FW-N20-3105-0W23 UT NUREG 0313 3105-1 09C Note 2, Category D FW-N20-3105-14WO UT NUREG 0313 3105-1 12S Note 2, Category D FW-N20-3105-16W0 UT NUREG 0313 3105-1 07C Note 2, Category D FW-N20-3105-24W0 UT NUREG 0313 3105-1 lOS Note 2, Category D FW-N20-3105-OW21 UT NUREG 0313 3105-1 lS Note 2, Category D FW-N20-3107-OWI UT NUREG 0313 3107-1 lOS Note 2, Category D

DETROIT EDISON COMPANY - INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program FERMI 2 TABLE A Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 32 Exams Selection Basis Relief Inspection Period Category / Item Identification Require Isometric Request 1 2 3 Remarks N/A NIA ANSI B31.1 Augmented FW-N20-3107-OW17 UT NUREG 0313 3107-1 07C Note 2, Category D FW-N21-3109-18W0 UT NUREG 0313 3109-1 08C Note 2, Category D FW-N21-3109-29WO UT NUREG 0313 3109-1 IlS Note 2, Category D SW-N20-03-B009-BWSE UT NUREG 0313 3105-1 1S Note 2, Category D SW-N20-03-B010-BWSE UT NUREG 0313 3105-1 08C Note 2, Category D SW-N20-03-BO11-AWSE UT NUREG 0313 3105-1 09C Note 2, Category D SW-N20-03-BO11-BWSE UT NUREG 0313 3105-1 09C Note 2, Category D SW-N20-03-B012-AWSE UT NUREG 0313 3105-1 12S Note 2, Category D SW-N20-03-B012-BWSE UT NUREG 0313 3105-1 12S Note 2, Category D SW-N20-03-B013-AWSE UT NUREG 0313 3105-1 los Note 2, Category D SW-N20-03-B013-BWSE UT NUREG 0313 3107-1 los Note 2, Category D SW-N20-03-B014-AWSE UT NUREG 0313 3105-1 07C Note 2, Category D SW-N20-03-B014-BWSE UT NUREG 0313 3107-1 07C Note 2, Category D SW-N21-01-BOO1-AWSE .UT NUREG 0313 3109-1 11S Note 2, Category D SW-N21-01-B002-AWSE UT NUREG 0313 3109-1 08C Note 2, Category D

IST - NDE Program Rev. 2 Change 3 Page 1 INSERVICE INSPECTION NDE PROGRAM TABLE B

DETROIT EDISON COMPANY - FERMI 2 INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program TABLE B Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 2 Exams Component Relief Inspection Period Code Clas S Identification Number Method Support Type Request 1 2 3 Remarks 1 Bl1-5360-Skirt VT-3 A 08C RPV Skirt & Bolting 1 Bl1-5360-STAB-A VT-3 G 10S RPV Stabilizer Supports 1 B1 1-5360-STAB-B VT-3 G 08C RPV Stabilizer Supports 1 Bl 1-5360-STAB-C VT-3 G 10S RPV Stabilizer Supports 1 BE1-5360-STAB-D VT-3 G los RPV Stabilizer Supports I BE1-5360-STAB-E VT-3 G itS RPV Stabilizer Supports 1 B1 1-5360-STAB-F VT-3 G 12S RPV Stabilizer Supports 1 B1 1-5360-STAB-G VT-3 G 115 RPV Stabilizer Supports llS I Bl1-5360-STAB-H VT-3 G 105 RPV Stabilizer Supports 1 B21-2192-G02 VT-3 SP 12S 1 B21-2192-G13 VT-3 G 12S B21-2297-G14 VT-3 G 10S 1 B21-5352-HAI VT-3 SP 07C 1 B21-5353-HB2 VT-3 'SP 08C 1

B21-5354-ACI VT-3 A 10S 1

B21-5354-HC3 VT-3 SP 08C 1

B21-5355-GDI VT-3 G 07C I

B31-5356-HA4 VT-3 SP 12S 1

B31-5357-HA1 VT-3 SP 10S 1I B31-5357-HA7 VT-3 C 08C 1

B31-5358-HB3 VT-3 SP 07C 1

B31-5359-HB6 VT-3 C 10S 1

B31-5359-HB7 VT-3 C 09C 1

El 1-2298-GOI VT-3 SP IIS 1

El 1-2299-G03 VT-3 SP its 1

El 1-2327-G03 VT-3 R 09C 1

E21-3052-G02 VT-3 SP 09C 1

E21-3053-G01 VT-3 SP 09C 1

E21-3053-G03 VT-3 R 12S

DETROIT EDISON COMPANY - FERMI 2 INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program TABLE B Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 3 Exams Component Relief Inspection Period Code Clas' Identification Number Method Support Type Request 1 2 3 Remarks 1 E41-2297-G05 VT-3 SP 12S 1 ES1-2192-G01 VT-3 SP 07C 1 G33-3096-G01 VT-3 SP los 1 G33-3096-G04 VT-3 SP 07C 1 G33-3096-10 VT-3 SP llS 1 G33-3096-G32 VT-3 G 11S I N21-3536-402 VT-3 SP 09C 1 N21-3536-403 VT-3 SP 12S 1 N21-3536-407 VT-3 SP ilS I N21-3537-G04 VT-3 SP los 1 N21-3537-G06 VT-3 SP los 2 B21-2586-G02 VT-3 R 12S Augmented exam - See ISI 99-056 2 B21-2587-G06 VT-3 SP 1S Augmented exam - See ISI 99-056 2 B21-2590-G12 VT-3 SP l0S Augmented exam - See ISI 99-056 2 B21-2592-G04 VT-3 R 07C Augmented exam - See ISI 99-056 2 B21-2594-G06 VT-3 SP 09C Augmented exam - See ISI 99-056 2 B21-4095-006 VT-3 R 07C Augmented exam - See ISI99-056 2 C11-2113-G262 VT-3 G 11S 2 C1 1-2113-G266 VT-3 R 09C 2 Cl 1-2113-G274 VT-3 G 09C 2 Cl 1-2113-G294 VT-3 G 07C 2 El 1-3035-002 VT-3 R lOS 2 El 1-3035-G05 VT-3 SP 09C 2 El 1-3035-G19 VT-3 G lOS 2 El 1-3035-G24 VT-3 R 12S 2 El 1-3146-G30 VT-3 G 12S 2 El 1-3146-G32 VT-3 SP 09C 2 El1-3146-G36 VT-3 l.10S .11 5 2 El 1-3151-G05 VT-3 SP llS

DETROIT EDISON COMPANY - FERMI 2 INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program TABLE B Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 4 Exams Component Relief Inspection Period Code Classs Identification Number Method Support Type Request 1 2 3 Remarks 2 El 1-3151-025A VT-3 R 07C 2 El1-3151-G29 VT-3 R 09C 2 El1-3153-G10 VT-3 G 08C 2 E11-3153-G12 VT-3 09C 2 El 1-3153-G16 VT-3 R. 12S 2 El1-3154-G05 VT-3 SP lOS 2 El 1-3154-G09 VT-3 R 08C 2 El 1-3154-G22 VT-3 R llS 2 El 1-3154-G28 VT-3 R 09C 2 El 1-3157-G04 VT-3 SP 07C 2 El 1-3157-G24 VT-3 R 09C 2 El1-3157-G29 VT-3 R los 2 El1-3158-G33 VT-3 R 09C 2 El 1-3158-G46 VT-3 R 09C 2 El 1-3158-G50 VT-3 Sp 12S 2 El 1-3159-G06 VT-3 R 07C 2 El 1-3159-G09 VT-3 R llS 2 El 1-3160-G01 VT-3 SP 08C 2 Ell-3160-G19 VT-3 0 12S 2 El 1-3161-Gll VT-3 R 12S 2 El1-3161-G15 VT-3 R 08C 2 El 1-3164-GlI VT-3 G 07C 2 El1-3164-Gl7A VT-3 R 12S 2 El 1-3164-G21 VT-3 SP 08C 2 El1-3177-G18 VT-3 R los 2 El1-3177-G19 VT-3 R 08C 2 El 1-3177-G30 VT-3 G los 2 E11-4611-G04 VT-3 SP 12S, X..t ,. . .

2 Ell-4611-G09 VT-3 R. 12S

DETROIT EDISON COMPANY - FERMI 2 INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program TABLE B Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 5 Exans Component Relief Inspection Period Code Classs Identification Number Method Support Type Request 1 2 3 Remarks 2 El1-4611-G15 VT-3 R 08C 2 El 1-4612-GIO VT-3 R llS 2 El 1-4612-012 VT-3 G 08C 2 El 1-5370-G01 VT-3 G lS Div2 RHR HTX Supports 2 El 1-5370-G02 VT-3 G 08C Div 2 RHR HTX Supports 2 El 1-5370-G03 VT-3 G 09C Div 2 RHR HTX Supports 2 El 1-5370-G04 VT-3 0 11S Div2 RHR HTX Supports 2 El 1-5370-G05 VT-3 A 08C Div 2 RHR HTX Supports 2 E21-3144-603 VT-3 SP 07C 2 E21-3144-G06 VT-3 A 11S 2 E21-3144-GI1 VT-3 R los 2 E21-3144-G16 VT-3 R 08C 2 E21-3144-G20 VT-3 R lS 2 E21-3145-G05 VT-3 SP 12S 2 E21-3147-G13 VT-3 R 12S 2 E21-3147-G20 VT-3 G 09C 2 E21-3147-G35 VT-3 R 07C 2 E21-3147-G39 VT-3 SP 10S 2 E21-3148-G29 VT-3 R 09C 2 E21-3148-G37 VT-3 SP 10S 2 E21-3148-G48 VT-3 R 12S 2 E21-3149-G05 VT-3 SP llS 2 E21-3149-G06 VT-3 R lls 2 E21-3150-G02 VT-3 R 07C 2 E41-3162-G01 VT-3 SP 09C 2 E41-3162-G03 VT-3 R 09C 2 E41-3162-G13 VT-3 G 12S

• .\ I 2 E41-3163-GOI VT-3 SP 08C -11.- - w.I -

2 E41-3163-G12 VT-3 R 12S

DETROIT EDISON COMPANY - FERMI 2 INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program TABLE B Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 6 Exams Component Relief Inspection Period Code Class Identification Number Method Support Type Request 1 2 3 Remarks I

2 E41-3167-GO1 VT-3 R 07C 2 E41-3167-G13 VT-3 SP los 2 E41-3167-G15 VT-3 R 12S 2 E41-3169-GIOO VT-3 G 08C 2 E41-3169-G13 VT-3 SP 09G 2 E41-3169-G17 VT-3 R los 2 E41-3172-GOI VT-3 SP 07C 2 E41-3172-G14 VT-3 R 11S 2 E41-3172-G18 VT-3 G 11S 2 N30-3258-002 VT-3 C 07C 2 N30-3258-G07 VT-3 C 07C 2 N30-3258-G17(A-D) VT-3 R 1os 2 N30-3259-G02 VT-3 C 07C 2 N30-3259-G25 VT-3 R 09C 2 N30-3259-G73 VT-3 SP 12S 2 P11-3566-G10 VT-3 SP 07C 2 T48-2095-GOl VT-3 SP 08C 2 T48-2095-GO7B VT-3 R 1is 2 T48-2095-G1OA VT-3 R 10S 2 T48-2095-G19 VT-3 G 11S 2 T48-2095-G22 VT-3 R 09C 2 T48-2095-G24A VT-3 R 10S 2 T48-2095-G25 VT-3 R 07C 2 T48-2095-G26A VT-3 R 12S 2 T48-2097-G07 VT-3 R 1Os 2 T48-2097-G13B VT-3 R 07C 2 T48-2097-G17 VT-3 R llS T48-2097-G19 VT-3 0-,G

- 1, -1ts- .--

2 T48-2097-G21 VT-3 R 07C

DETROIT EDISON COMPANY. FERMI 2 INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program TABLE B Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 7 Exams Component Relief Inspection Period Code Class Identification Number Method Support Type Request 1 2 3 Remarks I

2 T48-2097-G22A VT-3 R 09C 2 T48-2097-G25A VT-3 R 08C 2 T48-2097-G34 VT-3 G 09C 3 El1-2179-G20 VT-3 R 07C 3 El1-2180-G14 VT-3 G 12S 3 El 1-2183-G07 VT-3 G 10S 3 El 1-2183-015 VT-3 R 08C 3 El1-2184-G12 VT-3 R los 3 El1-2184-G22 VT-3 G 08C 3 El 1-3184-G04 VT-3 G 12S 3 El 1-3184-G08 VT-3 R 09C 3 El 1-3184-GIO VT-3 R llS 3 Ell-3184-G18 VT-3 R 07C 3 El 1-3185-040 VT-3 R 09C 3 El 1-3185-G53 VT-3 SP 09C 3 El 1-3185-G58 VT-3 SP 12S 3 El 1-3185-G60 VT-3 G 09C 3 G33-3096-009 VT-3 R los 3 P42-3340-G06 VT-3 SP 09C 3 P44-3047-G28 VT-3 G llS 3 P44-3048-G10 VT-3 SP 07C 3 P44-3084-G10 VT-3 R 07C 3 P44-3084-G15 VT-3 R 10S 3 P44-3189-G38 VT-3 SP 08C 3 P44-3189-G42 VT-3 R 10S 3 P44-3189-G47 VT-3 R 07C 3 P44-3336-G01 VT-3 A 09C P44-3336-015 'IVT-3' - R '"Ills" 3 P44-3337-G13 VT-3 R 12S

DETROIT EDISON COMPANY - FERMI 2 INSERVICE INSPECTION NDE PROGRAM ISI- NDE Program TABLE B Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 8 Exams Component Relief Inspection Period Code Clas Identification Number Method Support Type Request 1 2 3 Remarks 3 P44-3337-G16 VT-3 R los 3 P44-3345-02 VT-3 G 08C 3 P44-3345-G08 VT-3 R 09C 3 P44-3346-G02 VT-3 G llS 3 P44-3346-G12 VT-3 R 12S 3 P44-3347-Gl0 VT-3 R 07C 3 P44-3347-G14 VT-3 R 12S 3 P44-3348-G12 VT-3 A 07C 3 P44-3351-G28 VT-3 R 08C 3 P44-3351-G41 VT-3 SP 12S 3 P44-3368-G31 VT-3 R llS 3 P44-3368-G38 VT-3 R 12S 3 P44-3558-014 VT-3 R 12S 3 P44-3559-G12 VT-3 R 1 1S 3 P44-4624-G01 VT-3 G IIS 3 P44-4624-G12 VT-3 R 12S 3 P444625-G03 VT-3 G HS 3 P44-4625-G13 VT-3 R 09S 3 P444628-002 VT-3 R 10S 3 P444629-G05 VT-3 G 09S 3 P44-4629-G08 VT-3 R 08C 3 P44-EECW Head Tank Sprts (Div. 2) VT-3 08C 3 P44-EECW Htr Sprts (Div. 1) VT-3 12S 3 P45-2178-G09 VT-3 R 09S 3 P45-2204-Gl l VT-3 R HS 3 P45-3352-G02 VT-3 G 12S 3 P45-3352-G06 VT-3 R 07C

.- - , .,- 3 P45-3353-G05 IVT-3 I R 3 P45-3359-G03 VT-3 G 08C

DETROIT EDISON COMPANY - FERMI 2 INSERVICE INSPECTION NDE PROGRAM ISI - NDE Program TABLE B Rev. 2 Change 3 FERMI 2 NUCLEAR POWER PLANT Page 9 Exams Component Relief Inspection Period Code Class Identification Number Method Support Type Request 1 2 3 Remarks 3 P45-3359-Gil VT-3 SP HS 3 P45-3360-G04 VT-3 R 10S 3 P45-3360-G07 VT-3 G 09S 3 P45-4626-G03 VT-3 G 12S 3 P45-4626-008 VT-3 A lS 3 P454627-006 VT-3 A 12S 3 P45-4627-G12 VT-3 R lS 3 P454630-G04 VT-3 R 09S 3 P45-4631-G04 VT-3 R 09S 3 P45-4632-G08 VT-3 R los 3 P45-4632-010 VT-3 G lS 3 R30-2176-G17 VT-3 G 07C 3 R30-2176-G28 VT-3 A 10S 3 R30-2176-G31 VT-3 G 08C 3 R30-2177-G04 VT-3 - R 09S 3 R30-2177-G27 VT-3 R 11S 3 R30-2177-G31 VT-3 G 08C 3 R30-2181-G04 VT-3 R 11S 3 R30-2181-G15 VT-3 R 10S 3 R30-2182-G02 VT-3 G 09S 3 R30-2182-G14 VT-3 R 07C 1-1 -- l-....,

SECTION 8

SUMMARY

OF CONTAINMENT INSPECTIONS (MTE)

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 99

8. INTRODUCTiON Section 8 is a Summary of the IWE inspection -activities completed at Fermi 2 during the ninth refueling outage. The RF-09 scope included the 2"d period 100% inspection of the accessible surfaces of the primary containment and a representative sample of VT-1 and VT-3 inspections of primary containment components. This is the second refuel, in the 2d period, consisting of three refuels, with RF-09 containing the majority of the inspections.

8.1 ABSTRACT OF CONDITIONS NOTED AND CORRECTIVE ACTIONS TAKEN Locations where degraded coating was identified during RF-07 and RF-08 were re-inspected prior to their 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 RF-09, 11 locations below the 583' 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' azimuth 77 deg, was cleaned and re-painted. Finally, seven arc strikes, which had been previously blend ground, were re-coated.

During RF-09, areas that were repaired during RF-07 were re-inspected with particular attention being 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 or unexpected degradation.

The inspections of the remaineder of the primary containment resulted in the issuance of 7 corrective action 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.

I r

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 100

8.2 PROGRAM STATUS, ASME SECTION XI CREDIT - YWE

8.2.1 CATEGORY

E-A Containment Surfaces (1)

ITEM NO: E1.11 Accessible Surface Areas (each period)

Description Total ITotal Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date (%) (%)

Accessible I 1 1 100% 100% 100%

Liner Surfaces TOTALS 1 1 1 100% 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 (RF-07) and once every period after. During RF-09, a 100%

inspection was completed of the accessible areas of the primary containment this completes the inspection requirement for the 2nd period.

8.2.2 CATEGORY

E-A Containment Surfaces iTEM NO: El.12 Accessible Surface Areas Description Total Total Examined Examined Minimum Makimum Comp Requiring To To Date Required Allowed Examination Date (%) (%) (1) (%)

Accessible 1 1 0 (Note 1) 0% N/A MIA Liner Surfaces TOTALS 1 1 0 (Note 1) 0% N/A N/A NOTE (1) Inspections (VT-3) are required to be performed during the 3P(Period, Refuel Outages 11 and 12.

I Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 101

8.2.3 CATEGORY

E-A Containment Surfaces ITEM NO: El.20 Vent System - Accessible Surface Areas Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date (%)I (%) (1) (%)I Accessible 1 1 0 (Note 1) 0% N/A N/A Liner Surfaces TOTALS 1 1 0 (Note 1) 0% N/A N/A NOTE (1) Inspections (VT-3) are required to be performed during 3rd Period, Refuel Outages 11 and 12.

8.2.4 CATEGORY

E-C Containment Surfaces Requiring Augmented Examination ITEM NO: E4.11 Visible Surface Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination (1) Date (1) (%) (%) (%)

Visual 0 0 0 0% 0% 0%

Surfaces TOTAL 0 0 0 0% 0% 0%

NOTE (1) No Visual augmented examinations have been identified.

8.2.5 CATEGORY

E-C Containment Surfaces Requiring Augmented Examination ITEM NO: E1.12 Surface Area Grid, Min Wall Thickness Locations Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination (1) Date (%) (%) (%)

Surface 0 0 0 N/A N/A N/A Area Grid TOTAL 0 0 0 N/A N/A N/A NOTE (1) No Visual augmented examinations have been identified.

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, MI 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 102 II

8.2.6 CATEGORY

E-D Seals, Gaskets, and Moisture Barriers ITEM NO: E5.10 Seals (1)

Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date .

Seals 61 61 (Note 1) N/A N/A N/A TOTAL 61 61 (Note 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-001 has been approved to verify the leak tightness of seals and gaskets in accordance with 10CFR50, Appendix J.

8.2.7 CATEGORY

E-D Seals, Gaskets, and Moisture Barriers ITEM NO: E5.20 Gaskets (1)

Description Total Total - Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date  %): (%) (%)

Gasket 31 31 (Note 1) N/A N/A WN/A TOTAL 31 31 (Note 1) N/A NIA WNA NOTE (1) Code requires a visual examination, VT-3, of all seals, gaskets, and other devices once each interval. Request for Relief CISI-001 has been approved to verify the leak tightness of seals and gaskets in accordance with 10CFR50 Appendix J.

8.2.8 CATEGORY

E-D Seals, Gaskets, and Moisture Barriers ITEM NO: E5.30 Moisture Barrier Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date (%) (%) (%)

Moisture 1 1 1 67% 35% 67%

Barrier TOTAL 1 i 1 67% 35% 67%

NOTE During RF-07, 100% of the moisture barrier was inspected and replaced. There was no damage to the liner at this location. During RF-08 and RF-09, it was inspected again with no degradation identified. 67% credited for RF-08 and RF-09.

Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 103

8.2.9 CATEGORY

E-G Pressure Retaining Bolting ITEM NO: E8.10 Bolting Connections Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date Bolting 89 89 48 53.9% 34% :67%

Connections TOTAL 89 89 48 53.9% 34% 67%

8.2.10 CATEGORY: E-G Pressure Retaining Bolting ITEM NO: E8.20 Bolting Connections - (Note 1)

Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date (%) (%) (%)

Bolting 89 89 (Note 1) N/A N/A N/A Connections Torque TOTAL 89 89 (Note 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 IOCFR50, Appendix J.

8.2.11 CATEGORY: E-P Pressure Retaining Components ITEM NO: E9.10 Pressure Retaining Boundary Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date (%) (%) (%)

Pressure 1 1 (Note 1) N/A NIA NIA Retaining I Boundary TOTAL 1 1 (Note 1) N/A NIA N/A NOTE (1) Will be tested in accordance with 10CFR50, Appendix J Program.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 104

8.2.12 CATEGORY: E-P Pressure Retaining Components ITEM NO: E9.20 Containment Penetration Bellows Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date (%)

Containment 29 29 (Note 1) N/A N/A N/A Penetration i Bellows TOTAL 29 29 (Note 1) N/A N/A NIA NOTE (1) Will be tested in accordance with 10CFR50, Appendix J Program.

8.2.13 CATEGORY: E-P Pressure Retaining Components ITEM NO: E9.30 Airlocks Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date Airlock 1 1 (Note 1) N/A N/A N/A 1 1 (Note 1) N/A N/A NOTE (1) Will be tested in accordance with 10CFR50, Appendix J Program. i 8.2.14 CATEGORY: E-P Pressure Retaining Components ITEM NO: E9.40 Seals and Gaskets Description Total Total Examined Examined Minimum Maximum Comp Requiring To To Date Required Allowed Examination Date (%) (%)  %)

Seals 92 92 (Note 1) N/A N/A N/A And Gaskets 92 92 (Note 1) N/A N/A 9/A NOTE (1) Will be tested in accordance with 10CFR50, Appendix J Program.

Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 105

SECTION 9 II SECTION XI REPAIR/REPLACEMENT NIS-2 FORMS INDEX 4 Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 106

I!

9. NIS-2 DATA REPORT INDEX LOG No. WORK PKG. COMPONENT No. ASME DESCRIPTION No. CLASS02-001 B273060100 B2104F013R 1 SRV Refurbishment 02-002 R300040100 R3000F142A 3 Replace carbon steel disc with carbon steel disc.

02-006A 000Z020786 E1100F050A 1 Replace Disc 02-006B 000Z020787 E1100FO5OB 1 Replace Disc 02-007 VARIOUS B2104F013A-R 1 RF-09 SRV Replacement 02-008 A498030100 VARIOUS N/A RF-09 mechanical snubber rebuild A519030100 02-009 A497030100 VARIOUS N/A RF-09 hydraulic snubber rebuild A514030100 02-010 000Z021705 R3000F142A 3 Replace carbon steel disc with stainless steel 02-012 R303020100 R3000F142D 3 Replace carbon steel disc with stainless steel 02-014 000Z011314/ P45F400 3 Replace Valve 000Z022265 02-015 VARIOUS VARIOUS 1 CRDM Rebuilds02-016 000Z021044 N30-2186-018 N/A Rework hanger 02-017 N/A E1100F025B Refurbish relief valve 02-019 000Z023784 E51-3174-G07 N/A Modify Pipe Support 03-001 VARIOUS VARIOUS 1 RF-09 CRDM replacement installation and replacement bolting 03-002 00OZ002161 G4100F231 3 Install new throttle valve for Fuel-Pool Cooling System 03-003 000Z023688 Ell-3185-G051 N/A Replace leaking snubber Detroit Edison Co., 2000 2nd Ave., Detroit, MI 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 107

ILOG No. WORK PKG. COMPONENT No. SME DESCRIPTION No. CI iASS03-011 Y664030100 T2300F400D 2 Replace Bolting 03-012 P521630100 G3300F120 1 Replace Bolting 03-013 00OZ031288 El 151COO1C 3 Replace Bolting 03-014 00Z03Z1277 El S1COOlA 3 Replace Bolting 03-016 OOOZ031322, R3001C007, 3 Bolting replacement and pump column 000Z031323 R3001C008 repair 03-017 00OZ031324 P4500C002B 3 Bolting replacement and pump column repair 03-018 OOOZ031320, E1151COO1B, 3 Bolting replacement and pump column OOOZ031321, E11SCOOlD repair 000Z031466 03-019 0OZ03Z1253 T4804F603A 2 Bolting replacement 03-020 00OZ023952 El 10OF031 2 Replace valve disc 03-021 OOOZ031294, P4500C002A 3 Repair pump column and replace 0OZ03Z1597 bolting 03-022 OOOZ031290, R3001C005, 3 Repair pump column and replace 00OOO31293 R3001C006 bolting 03-023 OOOZ031478, E115lCOOlA, 3 Repair pump column and replace 0OZ03Z1597 E11 l51COOlC bolting 03-024 00OZ031598 B2104F013J 1 Repair inlet flange/gasket surface 03-025 00OZ030591 P44F402A 3 Replace cage, stem and plug Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport. Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 108

LOG No. WORK PKG. COMPONENT No. ASME DESCRIPTION No. CLASS03-028 00OZ031881 G3300F120 1 Bolting replacement 03-029 000Z031863 El 100FO5OA 1 Bolting replacement for Bonnet Detroit Edison Co., 2000 2nd Ave., Detroit, Ml 48226 Fermi 2 Nuclear Power Plant, 6400 N. Dixie Hwy., Newport, Ml 48166 Commercial Service Date: 1-23-88 NBNo. 21085 (RPV) 109

02-001 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl

. 1. Owner Detroit Edison Company Date 03/19103 I- Name

• : 6400 North Dixie Highway, Newport Ml 48166 Sheet I of 2 Address X I -

2. Plant Fermi 2 Nuclear Power Plant ULit 2

- Name Repair Target Rock Corp, P.O. NS-325856

' 6400 North Dixie Highway, Newport Ml 481668 0 Testing: NWS Technologies, P.O. NS-325815 Address Rep*at Otganization P.O. No., Job No., otc

3. Work Performed by Detroit Edison Company  : Type Code Symbol N/A Stamp .

Name Authorization No. N/A 6400 North Dixe Highway,'Newport; MI 48166 Expiration Date N/A Address

4. Identification of System - B21 Nuclear Boiler, Main Steam Safety Relief Valve Pilot Assemblies, and Main Bodies.

5. (a) ApplicablenConstruction Code ASME Ill I:

Class 1 19 71 Edtion S'1970 Addenda, NA Code Case

• ' (b) Applicable Edition of Section Xi Utilized for Repairs or Replacements 1992 92 Addenda

6. Idenrification 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. Identiticaton Built or Replacement Stamped (yes

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~~~N~~

o).~~~~~~~~or SRV Pilot Assemblies Target Rock Various, See N/A 82104F013A-R NWA Replacement Yes

.________________________ .___- ___. __ attached list -

SRV Main Body Assemblies Target Rock Various, See N/A B2104F013A-R N/A - Replacement Yes

._ _ _ _ _ .attachedlist _ _ AL L _ _ _' __

7. Description of Work Rebulid & Test 1S SRV Pilot Assemblies, and 4 SRV Main Bodies as required.

8. Tests Conducted: Hydrostatic 0- Pneumatic a Nominal Operating Pressure I Other 1 Pressure - psi Test Temp. 'F)

Note: Supplemental sheets Inform of lists, sketches, or drawings may be used provided (I) size is81/2 In.X I1In., (2)informa-tion initems 1through 6on this report isIncluded on each sheet and (3)each sheet isnumbered and the number of sheets Isrecorded at the top of this form.

IA -j

(10194)

Form NIS-2 (Back)

9. Remarlcs Applicable Manufacturer's Data Reports to be attached where requred.

All 15 SRV Pilot Assemblies, and 4 main Bodies were rebuilt and tested as necessary under Target Rock P.O. NS-325856, and NWS P.O. NS-325815. All Parts used are recorded inWork Request B273060100, as well as the Target Rock final document package from refurbishment activities. See attachment (1)Ust of SRV Main Body Serial Numbers that Pressure Retaining Parts were used on. No welding repairs were performed.

CERTIFICATE OF COMPIJANCE We certify that the statements made inthe report are correct and this reptacement conforms to the rules of the ASME Code, Section XL repairor replaerment Type Code Symbol Stamp Original Code Data Reoort to be supplemented by Section Xl Program 02-001 and TR field Service report 02Z.O10 Certificate of Authdzation No. NtA Expiration Date NtA Sibnada A . ( U1 A2L,%YNI -Date_:SAY_ 2-1 .2003

'Owners0i=e~s Designee, Tide CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding avalid commission Issued by the National Board of Bollar and Pressure Vessel Inspectors and the State or Province of Michilan and employed by H.S.B.I. &1.Co. d One State Street, Hartford. CT 06102 haw inected the components described inthis Owner's Report during the period A-(o ve Jz o toC) - 2 '24e°8 and state that to the best of my knowiedge and belief, the Owner has performed examinations and taken corcve masures described inthis Owner's Report inaccordance 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 descnbed inthis Owners Report. Furthermore, neither the Inspector nor his employer shall be liable Inany manner for any personal Injuy or property damage or aloss of any kind arisIng from or connected with this Inspection.

Commissions C- z 0 Inspector's Signature National Board, State, Province, and Endorsements Date / :L 2003 (10/94)

-Attachment (1)NIS-2 Repair Replacement Program 02-001 Presure Retaining~Parts Installed in SRV Main Bodies Main Valve Piot Base to body Nut P.O. #, Lot#, or HT#

Body SN# 1-118-12 inf. Stock#252-0544 _ _ _ _ _ _ _ _ _ _ _

336 4ea- P.O.# 362415, HT#D230 338 4ea. P.O.# 362415, HT#D230 318 4ea. P.O.# 362415, HT#D230 319 4ea. P.O.# 362415, HT#D230

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS02-002 As Required by the Provisions of the ASME Code Section Xl

1. Owner Detroit Edison Company Date May 23, 2002 Name 6400 North Dixie Highway, Newport MI 48166 Sheet 1 of 2 Address

2. Plant Fermi 2 Nuclear Power Plant Unit 2 Name 6400 North Dixie Highway, Newport Ml 48166 DECo Maintenance Address RepairOrganization P.O. No., Job No, etc.

3. Work Performed by Detroit Edison Company Type Code Symbol Stamp WNA Name Authorization No. NIA 6400 North Dixie Highway, Newport, Ml 48166 Expiration Date N/A Address'

4. Identification of System T & B N5-5 Diesel Generator Service Water (Div. 1)

- -- ' ' ~~~~ASME III .i--: --

5. (a) Applicable Construction Code. CfassM3 19 71 Edition W71 Addenda, NWA Code Case (b) Applicable Edition of Section Xl Utilized for Repairs or Replacements 1992 -92 Addenda

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

National :i; ASME Name of Component Name of Manufacturer Board Other Year Repaired, Replaced, Code Manufacturer Serial No No. Identification Built or Replacement Stamped (Yes or Nol Wm.'- _

R300OF1 42A Powell 661 71-8 NIA V15-2096 -1976 'Replacement Y

7. Description of Work Install Replacement Carbon SteeVStainless Steel Faced Disc in'Check Valve.

8. Tests IConducted: Hydrostatic a Pneumatic 0 Nominal Operating Pressure - -

Other i Pressure -_- psi Test Temp. ' P Note: Supplemental sheets inform of lists, sketches, or drawings may be used provided (1)size is8 1/2 In.X 11 in., (2) information initems 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.

(12102) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E.47th St., New York, N.Y.10017

Form NIS-2 (Back)

9. Remarks Replacement Disc procurred per P.O. #357513, Serial No. CM8886B.

Stainless Alloy Disc will be installed at a later time. (CARD 02-14702)

I CERTIFICATE OF COMPUANCE We certify that the statements made inthe 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 Dat Reoort N5-5(T&B) to be suolemented by Owners Section Xl Prooram 02-002 Certificate of Authorization No. N/A Expiration Date NIA Signed R.M. Hambleon.Lead ISI Enaineer -ADate ' Z?, _200_

Owner or Owner's Designee., rie CERTIFICATE OF INSERVICE INSPECTION I,the undersigned, holding avalid 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 .3 -Z 5 - 2- to O -.z /- ='Z , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis Owner's Report inaccordance 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 Inthis Owner's Report Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or aloss of any kind arising Irom or connected with this inspection.

CommissionsAA$fZ9&. A/X4_rf Z o Inspector's Signature National Board, State, Province, and Endorsements Date /b e '22/ 20 C02.

(12182)

For complete work package, see Work Request R300040100

- - ~~~As Required by the Provisions of the ASME Code Rules, Section Ill. Div. 1 7 1.(al Manulactured by....he Win. -Powell Company, 3233 Colerain Avenue, Cincinnati, OH 45225 (Name arnd add'ess Of NPT Certi cate lHolcerl b) Manufactured f1 for..D.etroit Edisoni 6400 Dixie Highways Newport, MI 48166 M C e (Nane ano addres ofN Cetificate Holder for Co' le.1tdted iIarcomponentI

2. IdentificatiOn-CertifiCate Holder's Senii: No. Par, CH~ -8886B 0la

. _____________ No. ____________

(a) Constructed According to Drai~ng No.P/N 26-109986-20000-19 DaigPeae b,'The Wmn. Powell Co.

lb) Oescription of Part Inspected 1 Disc for 8" Figure 3061 Swing Check Valve (cI Appliecable ASME Code' Section Ill. Edition ..L2L...... Adna7a1itr71 Cs o N/A C'aiss

3. Remarks - -..- ~ic ~ sdse~

Item 4-8 inclusive to be compleleo for sminle walt vessels. jackets of jacketed vessels, o' shells of heat exchangers.

4. Shell Material T.S.......Nom.Thk.-...n. .Cor-r.Atlow.-.in. Diamn...ft.-..in. Le-;"-' ftI in.

IK.Ad & Soec Nota iAn. of range specifiedl

5. Seams. Long...... _______ T' _________R.T. Eff~ciency Gi'th H.~..iT.' R.T. No. of Courses

6. Heads Ia) Material T.S. ____________ b) Msteras! ___________ T.S.

Locat.om 'too. Crown Knuckle Etolpical_ . Con-Cal "*-;4,SofemwCal Flat S :1 -o F'ess..-et Doltorm. @nitrcs ThC~tess Raidius Raaius Ratio .Apex Angle 11160us Diam. ICOP .e. of concave.;

If remoi.able. bolts used Dotler fastenl.ng a Szec. No.. T.S.. Stze. Numbri ) ~ 10oscribe or attach S.etc.1 7 Jv'ke: C~osuree-10ese. 0e as og.. and .%eld. bar. Set. If bar. g-vaaeOens-ons. '1 bo'!C0. 00esebe Or Sketchi S. saii Dei~gn Pressu-el _ _ __ _ _ s, at P__ _ _ _ __ _ _ _ _ 9__F fol Mni. Pfessu-e-Tst Temg .

Items 9 and 10 to be completed'far tube sect-ons.

9. Tube Sheets~: Stationarv. Maweral__________Osam. _________in. Thk.._____in. Attachment IK."a & Sfec. No.) (Subject to ores I (We oeC, botled)

Floating. Mate-tal_________ Oiam i n. Thkc.______in. Attachment

10. Tubes. Material ______O.D. _______ n. Thk. o' gage

-______in Number ______Type (Straight or U, Items 11.14 inclusive to be corroeted for .nner chambers of jacketed vessels or channels of heat exc'aange-s.

I11. Shell. Material. .... ____ .T.S. Nom. Thk...in. Cart. Allow.....n. Diarn..ft.-...n. Length....t.-in I Kind Soec. No I IMmn. of range s5oiCfltd)

12. Seams Long N.T.'____________R.T. __________EffIiciency Girth__________H.T.'___________R.T. _________No. of Courses

13. Heads: a) aterial ____________T.S. - b) Material l__________ ___________T.S.___________

Crown -Knuckle Elliptical Conical Hemispherical Flat Side to Pressure Location - Thickness Radius Raoius Ratio Apex Angle Radius Djam. lconvex or concave)

(aII Too, bottom, ends_____

lb? Channel _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

If removable, bolts used la)__________ bI _________ (ci _________ ther fastening l0esctibe oF attach sketchi

14. la) Design Pressure' psi at __________F fb) Min. Pressure-Tost Temp.F It~ postweld heat-treated. 'List other Internal or external pressures with coincident temperature when ap0plicable.-

-Supplemental Sheets in form of !ists, Sketches, or drawings may be used provIdied: (1) Size Is I314 in. xI33in.; (23 information In items I and 2 of this Data Report Is Included on each Sheet. and 13) each Sheet IS numbered and number of Sheets is recorded in item 3, Remarks.

112/SO) This form fE000401 may be obtained from the Order Dept.. ASME. 345 E. 47th St., New York. N.Y. 10017

FORM N-2 (Back)

Z11 Items be'ow to be completed for all vessels where applicable.

15. Safety Valve Outlets: Number - Size _ Location_

16. Nozzles:

Purpose liniet Reitnforcement outlet, arain) Number Oiam. or Size Type Material Tfucxness Material No.% Attached

17. Insoect on Manholes: No. S-ze Location Openings Handholes: No. S-Ze _ Location Threaded. No. _ Sao _ Location 18 S.pports Skirt Lugs Legs O-her _ Attached IYes or nol INumoeri (Number) (Describe) tw*re &rio:.'

We certify trat the statements made in this report are correct and this vessel part or appurtenance asdef ned in the Code conlarnrs to tIc rues of construction of the ASME Code. Secer: IIl

1. The applicable Design Specification and Design Report are not the responsibility of the NPT Certificate Holder for paDjs An %PT Certificate Holder for appurtenances is responsible for furnmshing a separate Design Specification and Design Report if the aWp-,-te.

mance is not included in the component Design Spec.'.ca: on and Design Report.)

Date June 25 y~c2001 neSdmlThe Wm. Powell Co. _ _ _ _ _ _

tNPT Certificate NO4oerl Cct ficate of Authorization Expires 12/13/03 Certificate of Authorization No. N1579 CERTIFICATION OF DESIGN FOR APPURTENANCE (when applicable)

Des gn nformation on file at S--ess anaiis-s report on file at Des-gmn sPec ' cations certified by Prof. Eng. State Reg. No l S-ess ana(v Isreport certified by Prof. Eng. State Reg. No.

CERTIFICATE OF SHOP INSPECTION I

1. -he unde's gned holding a valid commission issued by the Natornal Board of Boiler and Pressure Vessel Inspectors and the State or P own of a o Ohid and employed by H.S.B.I t I Co.

of- rford, CT ^have inspected the Part of apressure vessel descr bed in this Partial Data Report on _W_ -and state that. to the best of my knorledge and belief, the NPT Certificate Holder has constructed this part inaccordance with the ASME Code. Section 1111 By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the part de-scribed in this Partial Data Report. Furthermore, ne ther the Inspector nor his employer shill be liable in any manner for any personal injury or property damage or a loss o0any kind uris.ng from or connected with this inspection.

Date

-Ar In~co' Signature NtionaaorSEta)<te Prvic an No.

- InsPector's Signature National Board, State. Province and No.

02-006A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS03-029 As Required by the Provisions of the ASME Code Section Xi):

-. Owner Detroit Edison Company Date June 2,2003' Name 6400 North Dixie Highway, Newport Ml 48166 Sheet I of 2 Address

2. Plant Ferni 2 Nuclear Power Plant Unit I:- 2 . .

Name 6400 North Dixie Highway, Newport Ml 48166

- Deco Maintenance  ;

Address  : RepairOrganzation P.O. No. Job Non etc.

3 Work Performed by Detroit Edison Company Type Code Syrnbol NWA Stamp --

Name Authorization No. WA 6400 North Dixie Highway, Newport, Ml 48166 Exporation Date . N/AA Address

4. Identification N5-094 Residual Heat Removal (LPCI) Division 1' of System

5. (a) Applicable Construction Code 'ASME III,.

class 1 -19 71 Edition 71 Addenda NWA Code Case (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 Name of Name of Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, Code No. or Replacement Stamped

_____________ _ .or No)

El1100FD50A Anchor Darling IN-069 N/A VS-2163. 1974 Replacement Y

• Description

7. of Work Install replacement Disc and replace bofting material as determined by the Maintenance Suoervisor following valve disassembly

8. Tests Conducted: Hydrostatic II] - Pneumatic [I Nominal Operating Pressure [X I Other I Pressure , -- psi- , Test Temp._ _

Note: Supplemental sheets Inform of Usts, sketches, or drawings may be used provided (1)size is81/2 In.X 11 in., (2)informa-ton initems 1through 6 on this report isincluded on each sheet, and (3)each sheet isnumbered and the number of sheets Is recorded at the top of this form.

(1/94)

Form NIS-2 (Back)

9. Remarks: Replacement Parts included a new Disc that was previously-modified per Section X1 Program 01-006B that was procured per PO # 357655, SA 105, HT Code 4460, SN 2. (Applicable Data Report Atached)

In addition, the following quantities of bolting material was also replaced.

(8) 1-1/4"-8 TPI Studs PO# 880392, SA 193, Grade B7, Trace E171 (4) 518"-1 1 TPI Studs PO# 955769, SA 193, Grade B7, Trace C232 (8) 5/8"- 8 TPI Nuts PO# 965260, SA 194, Grade 2H, Trace F554 (8) 1-14"-8 TPI Nuts PO# 739669, SA 194, Grade 7, Trace RH98 Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made Inthe report are correct and this Replacement conforms to the rules of theASME Code, Section Xl.

Type Code Symbol Stamp Original Code data reoort N5-094 to be supplemented by Owners Section Xl Proaram 02.006A and Section XI Prooram 03-029 Certificate of Authorization No. NWA \ Expiration Date NIA Sgned R.M. Hambleton Lead ISI Engineer &h I 3.20° O 3 Owner or Owner's Designee, TiMe CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by t1BCTLof One State Street. Hartford, CT 06102 have inspected the components described inthis Owner's Report during the period ntspZ 3? to -2. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis 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 Inthis Owners Report. Furthermore, neither the Inspector nor his employer shag be liable inany manner for any personal Injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions--'L'4--- ' 0

" ' t spector's nIn Signature National Board, State, Province, and Endorsements Date 2 /0 00 (1094)

For complete work package, see Work Request 000Z020786 and 000Z031863

FOm N2 NTT CEMT1fCAITE HOEDT MTA WOrr FO NUEAR FAT AND Aa.ftquwcd by the croysouf o e ASUE Code Rulcs. Setion 11. Div. *

(a) ~ Floserve Corvoration, 71Frt tre W 1iSp tPA 17701

,.ae am E ofl _Carie wo (b)M a.,=U~d,' Detroit

. Edison, P.Q. Box 1659, Detroit, MI 48231 (Damb awm of It Cgrdam IW "Of a s.u.arcin olmoaies"Cw

-. e, -aCersumte Moldez sirw mNo.- PtAe 2 .- - -- u.NC.

N~~~/A--

(a) Consuuctrd cemDg - D11726.1R/A -p,,j, Fiowserve , CorD. -

A o Dmwiag -iN.___________d snn -Flwsrv

- (bVVeseripdd - I n.g Check Disc w/Stellite less Res. Seat, Ht. #14460 SA105 ^

tb) - DcxaspuiG of Fart bapected

- Appia~ble (c) wrleilS4EcReseclx1980

{Ci ASUE Code: Section la, Edlion "dsdwc dcdd umme*

i~!.LCs N/A

,jI..caxs a ,

L~... 1

- -- Part(s) for 24"-900:#~Swing Check ValVe (witho ut.Resilient Seat) *

-Spare

3. R rmuk. -ona 4..mwse* .g o. whic amat was Cdmguo,4 Flowserve S.D. and Item No: P932G-1 -

- - W1TEr- No HFydrotesting Perforned -

Enrico Fermi 2 Site.

• Ye certift chuthate amowntr- 'ad

• tMis epena co ct d s or appWeaataenaadd Z de Code cak fatma so the rles f cCosuctin of the A24E e Secion -L

he appaalle Desi Speelw am sm Rewt am sobt She risvooudbmtr orthe xPr Cermieaue molder tar A: ,Y1 Cem2.

uc Holder for ap uan= is rtspume fo ftnuadug a SCp m Design Specdficdnac.-d S£ epr i the a pcmanr C.s 'at included i ze Desl= Speclflcauon ad Sav Recw:

D./ f )i su ~Flowserve corporatio r ccegt ofef~

-Certiricate Andurrization Wi -

• Expwes 4/l5/04  !' 'C C/15/fi.ate dt[ortilt4 ~1Aj~h**;_w N1713 CE- FICATION OF DESGN FOR APPURTENANCE (wbca applicable)

Design Anofmados on file o Ss anlsis report an fae at Design Spcificatios certied Prof. En.Star _ eg.No.te Sness analysis .. Po: ceteife4 PEoLEna. Seate P( Fc. No.

CERTnICATE OF SHOP INSPECnON

1. she undersigned. balding-a vslid eomissim gissued by the Nationsl Board af Boiler and Preure Vessel Inspects.

. d.rhereizeazeqE4xfxelf Pennsylvania and M Conmmercial Union Insurance Compan

-ef Boston. Mass. -  ; pan of a pressim vessel described inthis.

parW Data Iew Z an fL/tem%

lUL2_10I ef- l E / UI_-. and smte that to the ben of my wledze and belief. the N?? CitIcate Holder has eo etd tus Ms In acaee wi the-ISME Code Section IL signin this eertiicae, neither the inspector aet kis emplyiter akes may warany. erpressedor C.mplied. euclerb.

Ilg the panL descrIbed la thwi -Parla Data leicts. Furthermore. neither the.

shall be liable in Mr asaer for my persnal iniluy ar plOperty damage or a loss of any kind arisang In-g r InSiectOr mar his emtalarer c M with this inspecdio-.

(21

-CU Ch~~eadss ~Pennsylvania

• i.,t0immiitSS ahbrl s bass. .bat emm- ma, Sm0.44 e.~atme it) Baa. C 3 5t. (2s A.,,Board. sime.

2392 mma. I :4 1101771 ~~~~~This faint EM00SOnmaybeobtained fgm ug Oraar Ceo..ASME. 345E L7ln St.. NewYore. N.Y. 10017

02-006B FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required by the Provisions of the ASME Code Section -

1. Owner '- Detroit Edison Company- 0 ' ' " - Date .June 2,2003

~ I' Name - -

6400 North Dixie Highway, Newport Ml 48166 Sheet I 1of 2

.. Address. . -

2. Plant - Fermi 2 Nuclear Power Plant -- - Unit 2

• - -- Name I I II 6400 North Dbde Highway, Newport MI 48166-II., I Deco Maintenance Address

.'Address..- Repal Organization P.O. No, Job No., et

3. Work Performed by

• Detroit Edison Company Type Code Symbol NIA Stamp- - :_ _ _ _

Name I  : Authorization No. WIA 6400 North Dixie Highway, Newport, MI 48166 Expiration Date -

NIA Address

4. identification N5-0312 Residual Heat Removal ILPCfl Division 2 of System -

5. (a) Applicable Construction'Code ASME III, Class1 19 71 Edition 71 Addenda WA Code Case (b) Applicable Edition/Addenda of Section )aUtilized for Repairs or Replacements 1992-92 Addenda

6. Idenifcation of Components Repaired or Replaced and Replacement Componns. -

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

._-_._._._____._. or No)

E110O0F50B Anchor Darling IN-077 N/A V8-21 4 1974 Replacement Y Description

7. of Work Install replacement Disc and replace bolting material as determined by the Maintenance Supervisor following valve disassembly

8. Tests Conducted: Hydrostatic [I Pneumatic (j Nominal Operating Pressure [ X ]

.Other [ I Pressure PsI -: Test Ternp.

Note: Supplemental sheets inform of lists, sketches, or drawings may be used provided (1)size is8112 in.X I1 in., (2)informa-ton initems t through 6 on this report isincluded on each sheet, and (3)each sheet is numbered and the number of sheets is recorded at the top of this forn.

(1/94)

I 11 L I I . I I i 4 I Form NIS-2 (Back)

9. Remarks: Replacement Parts included a new Disc that was previously modified per Section XI Program 01-006A that was procured per PO#

279604, SA 105, HT Code C1788, SN 1.(Appricable Data Reports Atached) Inaddition, the following quantities of bolting material was also replaced.

4 1-1/4"-8 TPI Studs PO# 965330, SA 193, Grade B7, Trace F556 4 1-1/4"-8 TPI Studs PO# 880390, SA 193, Grade B7, Trace E171 8 1-1/4"-8 TI1 Nuts PO# 880299, SA 194, Grade 7, Trace 68395 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this Replacement conforns to the rules of theASME Code, Section Xl.

Type Code Symbol Stamp Oricinal Code data report N5-0312 to be suoolemented by Owners Section Xl Program 02-006B Certificate ol Authorization No. N/A Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer f iAl C Date .K Z .2 0 °3 Owner or Owner's Designee, MTe CERTIFICATE OF INSERVICE INSPECTION.

1,the undersigned, holding avalid commission issued by the National Board of Boler 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 Inh s Owners Report dudng the period _ Z~ o 14' -,2 7- 3 . and state that to the best of my knaowledge and belief, the Owner has performed exarninations and taken corrective measures described inthis 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 inthis Ownees Report Furthermore, neither the Inspector nor his employer shag be liable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this inspection.

God: '~2' I e Commissions Inspectors Signature National Board, State, Province, and Endorsements Date 2° 2e 02 (10/94)

For complete work package, see Work Request 00OZ020787

14 T' WTC T9 RWLZ= DATA WMI FM~ X)CL PAVt AM *M&.

Aa eqw et by fttenums d at ASULE Coaf *uim. Sadi M1. Wv. 57w a2-o00f0B

_____ s~~~~~~~~~~~~~~

2oZ..-

ACtifor/Darlim; Vilve Co., 701 First St., 1livamport. PA 17701 h - - A - - -

- -~~~~~~~~~ . -- X .___

IL

- cm man ""O" "M s. ditI I Us'? s WA

~~ - - ~~h M ~~ D11726 R/A Dew6pq.jrl n a y L Disc, 18 Ketfo aterial: SA1OE

-. Sum '82 -f m ~Sepat Psr ro.o 244M9O-Exercisable Swing Check VAl e, Dwg. 222n-3.1 by. _N

£$.O. E3039-1; SJO 3020-5.-;et't so P.D. 1C-279604;

'A/Dv S.O. 'P-WIO1 Z- I_ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _

ki 1"yra Pr-fa "a -

ao- aml fomu oah A" - we awa"a "V ,. 4w 'a a~ de6co" Cm.

UWVN of- -- t ft Sumft li $W u N mitf 4ZnIRCAIM OF =(L' FOR APM)RTL(AfC Ms qgiosb.)

~~ s ~imp W-a~w W Pvw#. tagl. *M.* a..i

• CMI FCAMt OF VWO L'NSPWEhCW Uno OWNs 6~abawmw.ftAYjlvn~anI~ -- ,~ Cpm'ac1 Ufo InuaCts na U

• C~ ~ ~~Is WI lfl m 9) vus m's LSisNa "Ifno Il Iisftsmin2" OastsIan tftn~mrw-. spaejau *ssmt wb

___ alo, p~wfmamvn'" &WV of p"*em lifam W a 'sSi a" wd MUM Ifsa w

~..... tnnsylvania 2392

• "sw9=N- -orm~

am Gae -. To VW.XTmI

02-007 03-024 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl  :

1.' Owner Detroit Edison Company I ' Date 5108103

-- Name 6400 North Die Highway, Newport Ml 48166 Sheet 1 of 2 Address

2. Plant Fermi 2 Nuclear Power Plant Unit 2 Name 6400 North Dbde Highway, Newport Ml 48166 DECo Maintenance Address Repair Organization P.O. No., Job No., etc.

3. Work Performed by Detroit Edison Company Type Code Symbol I : I N/A .

Stamp Name Authorization No. : NIA 6400 North Dixe lfghway, Newport, Ml 48166 Expiration Date N/A

- - -- Address

4. Identification of System X B21 Nuclear Boiler, Main Steam Safety Reflef Valve Pilot Assemblies, and Base Assemblies:

5. (a): Appflcable Construction Code ASMEIII ' i - - -l

-ClassI - 71 Edition W7-71 Addenda, NA Code Case (b) Applicable Edition of Section Xl Utified for Repairs or Replacements 1992,92 Addenda

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 or Replacement Stamped (yes

________ _  ; o0r No)

SRV Pilot Assemblies Target Rock Various (See N/A B2104F1o3A-R NWA Replacement Yes attached fist) ___X_ ' Various

-SRV Main Body Assemblies -Target Rock Various (See WA 82104F013A-R N/A Replacement Yes

_________ attached fist) ___ Various _

7. Description of Work During RF09, Replaced all 15 SRV Pilot Assemblies. Replaced Main Bodies on B2104F01 3G, H,L & P.

8. Tests Conducted: Hydrostatic 0 Pneumatic 10 Nominal Operating Pressure E  :

Other l Pressure - , psi Test Temp. F)

VT-2 Per 43.000.005 and 24.137.21, Operability Test per 24.137.11 Note: Supplemental sheets Inform of lists, sketches, or drawings may be used provided (1)size Is81/2 In.X 1Iin., (2)informa-ton in items 1through 6 on this report Isincluded on each sheet, and (3)each sheet Isnumbered and the number of sheets is recorded at the top of this form.

(10194)

I 9. Remarks Applicable Manufacturers Data Reports to be attached All 15 SRV Pilots, and 4 Main Bodies were replaced using station Work Requests B350030100 thru B364010100.

I . Boltine material was changed out on SRV12103F011H (1) 1-3/8" x 6UNC-2Ax10". SA-193 vrade R7. PO# 686576, I} (2) 13/8 P9nuts. SA-1194- Grade 7. PO# R20-42fl Se attached li'qtinIT for.RRV exrhanve matrix I SRV Pil ots were refurbished per Section XI Program 02-001. and Work Reauest B273060100. The B2104F013J i position SRV Reactor side. and Valve side Tnlet Flancres were weld renaired due to minor steam cutting using WRAO(f )ZO3 1598 ner Sectinn XT Prtwrram fl3-024 CERTIFICATE OF COMPLIANCE We certify that the statements made Inthe report are correct and this reolacement 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 Proaram 02407.034024 and TR Field Service Regort Number 02Z010 Certificate of Authorization No. N.A Expiration Date N/A Signed R.M.Hambletn. ISI Enreeer Data MAY. 08 2003 Owner or Owners Designee, Tnit 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 Inthis Owners Report during the period /0 2.. to 40 -/. - 03 . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described Inthis Owner's Report Inaccordance with the requirements of the ASME Code,Section X.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described Inthis Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this inspection.

cf Co1 Commissions r'9/ A .° Inspectors Signature National Board, State, Province, and Endorsements Date 1c-3 . 2003 (10/94)

NIS-2 For 02-0071 03'024 Sheet 2 of 2 2003 Refueling Outage SRV Replacement Matrix RF09 Division PIS Number Steam Isometric Code Set Point Work Valvel Pilot SIN

.Lne Draing Data psig- Request Body SIN Report

.. . . . . ~~~N-5: - -.  :

I (LLS) B2104F013A D M-4095 265 1135 B350030100 389 342 B2104F013B C M-2591 301 1135 B351030100 331 1197 II IB2104F013C B M-2594 291 1135 B352030100 391 1184

_B2104F013D B M-2593 278 -1145 B353030100 328 327

.______ B2104F013E C M2592 309 1155 B354030100 339 336 B2104F013F B M-2596 290 1145 B355030100 327 339 (LLS) B2104F013G B M-2587 321 1135 B357030100 . 1200 B2104F013H C M2588 266 1155 B356030100 ... . 1199 B2104F013J C M2589 308 1155 B358030100- 332 328 B2104F013K B M2595 -311 1135 B359030100 330 332 B2104F013L A M-4094 313 1145 B360030100 319 B2104F013M A M-2586 268 1145 B361030100 342 1198 B2104F013N A M-4093 310 1145 B362030100 341 330 B2104F013P D M-4096 322 - 1155 B363030100 1160 318 B2104F013R C M-2590 288 1155 B364030100 371 1180

._______ All 15 SRV Pilots were replaced, and the 4 Shaded Bodies were replaced as well

j .- 7 -

. - 7 . - -r - - . 1. -1. I.

. - - I I I. I II t , . .

I . . I I I  ; , r . , ., I

02-008 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

. As Required by the Provisions of the ASME Code Section Xl

1. Owner Detroit Edison Company Date May 14, 2003 Name ' i 6400 North Dixe Highway, Newport Ml 48166 Sheet 2 of (D Address

2. Plant Fermi 2 Nuclear Power Plant Unit 2 I Name 6400 North Dixie Highway, Newport Ml 48166 DECo Maintenance Address - -: I = - - f RepairOrganization P.O. No, Job No. etc.

3. Work Performed by Detroit Edison Company -'-- -Type Code Symbol Stamp N/A Name I Authorization No. N/A 6400 North Dixe Highway, Newport, MI 48166 Expiration Date N/A Address

4. Identification of System Various Component Supports (Mechanical Snubbers)  :

ANSI B31.7, 19 69 Articles 720 & 1-721

5. (a) Applicable Construction Code ANSI B31.1 19 67 Article '121 (b) Applicable Edition of Section Xi Utilized for Repairs or Replacements 1992-W'92

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 or Replacement Stamped (Yes

___________ __________ ~~~~~~~~~~

No)

PLANT MECHANICAL Pacific Various NA NONE Various REPLACEMENTS N.

SNUBBERS Scientific _ _ ______-__

7. Description of Work Refurbish Mechanical Snubbers for future installation

8. Tests Conducted: Hydrostatic 0 Pneumatic a Nominal Operating Pressure Cl Other ID Pressun e i psi Test Temp. -__ _ F Functional test &visual Inspection Note: Supplemental sheets inform of lists, sketches, or drawings may be used provided (1)size Is8 1/2 in.X I1 in., (2)

Information Initems 1 through 6 on this report IsIncluded on each sheet, and (3)each sheet Isnumbered and the number of sheets Isrecorded at the top of is form. I - -

(12r82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E.47th St., New York, N.Y.10017

Form NIS-2 (Back)

9. Remarks Attached are listings of Mechanical Snubbers that were refurbished and changed out during testing activities during RF09.

Applicable Manufacturers Data Reports to be attached Note the fisting of the Mechanical Snubbers that were refurbished prior to and during RF09 including a listing of parts installed.

Documentation satisfies requirements of Code Case N-5D08-1 as allowed by Refief Request RR-C4.

CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this Relacement conforms to the rules of the ASME Code, Section Xi. repai or replacement Type Code Symbol Stamp Orioinal Code Data Reports to be suolemnented by owners Section Xl Proaram No.02-008.

Certificate of Authodz~tion NoW NA Expiration Date N/A Signed e QL=o GoS g

• Date .20 03 Own or Owner's Designee, Tie CERTIFICATE OF INSERVICE INSPECTION I,the undersigned, holding avalid 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 descnbed inthis Owner's Report during the period Ap7 - O/ r R to z , Z c 3 . and state that to the best of my knowledge and belief, the Owner has performed examinations antaken corrective measures described inthis Owier's Report inaccordance 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 inthis Owner's ReporL Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this inspection.

Commissions _ _ _ _ _ _ _ _ _

Inspector's Signature National Board, State, Province, and Endorsements Dalce of 20 03 (12(82)

For complete work package, see Work Request A4980301 00 A5190301 00

Mechanical Snubbers Replaced with Rebuilt Spares .- Iap Hanger Number Old Serial New Serial B21-2174-G25A 13116 13152 B21-2174-G25B 13151 8496 321-2589-G02 8990 12809 B21-2590-G04 9855 7016 B21-2593-G07 9856 - 4708 321-2595-G07 9016 10340 B21-7195-GOIA 12742 19925 B21-7195-GOIB 22414 22419 B21-E213-SSA1 4705 9861 B21-E213-SSA3 9877 7018 B21-E213-SSC2 8982 10348 B21-E213-SSC5 11283 8731 B21-E213-SSD1 8716 4713 B31-5064-G24 13163 13204 B31-5065-G39B1 12690 22337 331-5065-G40 11466 12709 B31-5065-G41 22344 12694 B31-5239-GO2B 22367 19932 B31-5239-G16 13144 8478 B31-E215-SSB8 4710 9850 C41-2340-G08 6828 13155 C41-2340-G12 13126 13138 C41-2340-G16A 13193 8469 El1-3146-G33 - 4706 9848 El1-3152-G33 12444 15286 Ell-3154-G17 8997 9006 El1-3179-G05 8482 13134 E11-3184-G45 20982 12435 E11-3185-G32A 6187 10345 El1-3519-G144 20974 12447 E11-4004-GOIS 12692 22347 El1-4004-GO2A 12697 22412 E21-2199-G04 13132 6828 E21-3147-G26 8357 8959 E41-5256-G02 22372 22349 E41-5256-G20SA 12696 19923 E41-5256-G20SB 12677 22458 E41-5256-G20SC 13183 13108 E41-5256-G21 8480 13165 E41-5256-G22S 13133 8474 E51-3174-GO9A 8714 9857 G33-3244-G39 12436 15290 G51-4059-G20 23169 18658 N21-3131-G33 8328 9017 N21-3131-G38 9005 9011 N21-3536-G29B 12821 8342 N21-3536-G37 10332 10354 N21-3536-G38A 12798 8985 N21-3536-G38B 12800 8999 N21-3537-G26B 9897 7021 N21-3537-G31 10352 10351

Mechanical Snubbers Replaced with Rebuilt Spares 3d2 Hanger Number Old Serial New Serial N21-3537-G34 -11272 8708 N21-3537-G38A 12810 9019 N21-3537-G38B 8984 8961 N30-2186-G03 22401 19934 N30-2186-G04 19940 22357 N30-2186-G05 22342 22341 N30-2186-G07 13142 13169 N30-2186-G09 13112 8501 N30-2186-GlO 19919 22436 N30-2186-G11 12739 19917 N30-2186-G15 8491 8470 N30-2186-G16 13129 13180 N30-2186-G17 22395 27916 N30-2186-G18 13128 8497 N30-3259-G29 8710 9847 N30-3259-G49 1589 1588 N30-3259-G55 8723 12792 N30-3259-G57 8747 11281 N30-3259-G76 9889 8748 N30-3259-G81 7019 9843 N30-3526-G46 -13170 8495 N30-3526-G48 12993 12750 N30-3526-G54 16235 13195 N30-3526-G55 13141 13157 N30-3526-G57 8493 8486 N30-3526-G58 13175 13184 Pi1-3156-GO5 12684 12715 P11-3566-G 1 13143 8510 P34-7405-G02 12741 22372 P34-7405-G07 13195 13109 P42-4357-G22B 12691 22406 P50-2163-G13 22365 12677 P50-2163-G14 12672 12712 P50-3579-G25 22426 19907 T23-12837-36-G32 22422 22499 T23-12837-36-G33 22380 22400 T23-12837-36-G45 22434 12746 T23-12837-36-G56 22374 12722 T23-12837-36-G58 22357 22429 T23-12837-36-G75 11974 12707 T23-12837-36-G96B 12689 19933 T23-12837-40-GO2A 12712 12738 T23-12837-40-GO2B 12763 22455 T23-12837-40-G08 18641 21954 T23-12837-40-GO9A 8481 13187 T23-12837-40-GO9B 12757 19898 T23-12837-41-GO5A 13157 8465 T23-12837-41-GO5B 13196 13116 T23-12837-41-GlOA 13130 8466 T23-12837-41-G17 8487 13181 T23-12837-42-G03 12771 12733

t,31S-12 .

Mechanical Snubbers Replaced with Rebuilt Spares A- cfz--Cooo Hanger Number Old Serial New Serial

- 4 op(,,,

T23-12837-42-G12B 8486 16224 T23-12837-42-G14B 22335 12730 T23-12837-42-G22 22347 19921 T23-12837-42-G24 8492 13156 T23-12837-42-G28 13181 13173 T23-12837-42-G41 22428 12741 T23-12837-42-G50 13173 13135 T23-12837-42-G54 12749 22370 T23-12837-43-G45 8484 8509 T23-12837-43-G49 12740 12760 T23-12837-45-GO2B 13202 13163 T23-12837-45-GllA 8508 13131 T23-t2837-45-G12A 13185 13166 T23-12837-46-G100 13158 13154 T23-12837-46-G102 22355 12685 T23-12837-46-GI7A 12714 22417 T23-12837-46-G22 12988 12977 T23-12837-46-G54 13204 13190 T23-12837-46-G70 13178 13147 T23-12837-46-G94D 19918 12764 T23-12837-48-G12 13111 8468 T23-f2837-51-G141 22411 12743 T23-12837-51-G142 13108 8506 T23-12837-51-G144 22439 12725 T23-12837-51-G19 19911 22459 T23-12837-51.-G28 12715 12768 T23-12837-51-G29 22386 12724 T23-12837-51-G33 22403 12751 T23-12837-51-G61 13201 13153 T23-12837-51-G62 22375 22340 T48-4061-G08 19577 21950 T48-4062-GO5B1 22413 19928 T48-5314-G02 22435 22424 T48-5314-G03 13187 8498 T48-5314-G06 12711 12701 T49-5325-G58 13167 8507 T50-7431-G02 12727 22360 T71-12837-62-G35 12747 22353 T71-12837-62-G57 22445 12692 T71-12837-63-G32 13159 13133 T71-12837-64-G50 22451 22391 T71-12837-64-G51 13134 8493

5OjSL Mechanical Snubbers Rebuilt with New Parts Serial -Snubber Location Size - Description JWork Package 22412 El1-4004-GO2A 1/4 Ring, Retaining A498030100

__--_-___- Washer 8509 T23-12837-43-G45 1/2 Torque Carriers & Shaft Assembly A498030100

~Ring, Retaining

________ - =Rod

_ __________________ & Bearing Assembly 22419 B21-7195-G01B- 1/4 Assy, Rod & Bearing A498030100 Ring, Retaining

-___--_______=_______-_

__________ Washer 12701 T48-5314-G06 1/4 - Ring, Retaining A498030100

-___________-_____-____ Washer 12750 N30-3526-G48 1/4 Ring, Retaining A498030100 9011 N-21-3131-G38 10- Ring, Retaining A49803010t

-_________ _ ______________________ eW ashe r 9017 N21-3131-G33 10 Ring, Retaining A498030100

- Washer

_______-_ Assy, Bearing =_ = _-

9012 SPARE 10 Ring, Retaininc A498030100 13154 T23-12837-46-GlOO 1/2 Ring, Retaining A49803010t

__-_-___- W asher 1588 N30-3259-G49 100 Pin, Cotter A498030100 Washer

-_________Washer, Locking 9857 E51-3174-GO9A 35 Ball, 0.622 in. A498030100 Ball, 0.624 in.

Pin, Cotter

_ - - Washer, Locking 12792 N30-3259-G55 35- Ball, 0.622 in. A498030100 Ball, 0.624 in.

Pin, Cotter

-__ _Washer, Locking 13147 T23-12837-46-G70 1/2 Ring, Retaining A498030100 8507 T49-5325-G58 1/2 Ring, Retaining A498030100

________'__'__.-_ W asher .

8495 N30-3526-G46 1J2 Ring, Retaining A498030100

_ - _ W asher -

22424 T48-5314-G02 1/4 Ring, Retaining A498030100

_ '_____ W a she r .

22340 T23-12837-51-G62 1/4 Ring, Retaining A498030100

_ _ _ _ _ _ _ _W a sher 12707 T23-12837-36-G75 1/4 Ring, Retalning A498030100 22436 N30-2186-G1O 1/4 Ring, Retaining A498030100 Anti-Rotation Key

_ ___ -__ W ashe r 12733 T23-12837-42-G03 1/4 Ring, Retaining A498030100]

i-Oz-wv' Mechanical Snubbers Rebuilt with New Parts (0,cc-(e ISenal Snubber Location lSize - Description -Work Package 19934 N30-2186-G03 114 Torque Carriers & Shaft Assembly A498030100 Ring, Retaining

__W _____ _____ _____ _____ asher 12809 - B21-2589-G02 10 Ring, Retaining A498030100 Retainer, Nut

-_______ _Bearing Assy 20972 SPARE 3 Thrust Bearing Kit A519030100 12450 SPARE 3 Thrust Bearing Kit A519030100

_________ :___________________ Bearing Screw Assembly 4710 SPARE 35 Ball, 0.622 in. A519030100 (Unsat Functional Test).. Ball, 0.624 In.

Pin, Cotter 13190 T23-12837-46-G54 1/2 Retaining Ring A519030100 19921 T23-12837-42-G22 1/4 Washer A519030100 23166 SPARE - Washer A519030100 8469 C41-2340-G16A 1/2 Retaining Ring A519030100 8470 N30-2186-G15 1/2 Retaining Ring A519030100 8985 N21-3536-G38A 10 Load Pin 0963030328 Stock Code 482-5682

__________________ _ PO 245779 8342 N21-3536-G29B 10 Load Pin 0963030328

From N21-3536-G38A :_  :

12750 N30-3526-G48 Load Pin 0963030328 Stock Code 482-5679 PO 245776 13147 T23-12837-46-G70 14 Load Pin 0963030328 Stock Code 482-5679 PO 245776 113195 N30-3526-G54 / Load Pin 0963030328 Stock Code 482-56791 PO 2457761 I -i' . I . -- .-

1, . ..-- w- v -

02-009 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl

1. Owner Detroit Edison Company Date - :  : May 14,2003 - -

-Name 6400 North Dixie Highway, Newport Ml 48166 Sheet 1 of I Address Z Plart Fermi 2Nuclear Power Plant Unit 2 Name 6400 North Dixie Highway, Newport MI 48166' DECo Maintenance Address - ReparOrganizanP.O.No.,JobNo etc.

3. Work Performed by Detroit Edison Company Type Code Symbol Stamp N/A Name Authorization No. NWA 6400 North DWe Highway, Newport Ml 48166 Expiration Date NIA Address

4. Identification of System- Various Component Supports (Hydraulic Snubbers)

ANSI 831.7: 19 69 Articles 1-720&1-721'

5. (a) Applicable Construction Code ANSI B31.1 19 67 Article 121 -_

(b) Applicable Edition of Section Xi Utilized for Repairs or Repiacements 1992-Yf92

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 Bult or Replacement Stamped (yes

_____ _____ _ _ _ __._ __._ _ _ ._ or Nol PLANT HYDRAULC Power Various NA NONE Various REPLACEMENTS N SNUBBERS Piping _

7, Description of Work Refurbish Hydraulic Snubbers during testing activities and for future installation

8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure a Other 0 Pressure - psi -TestTemp. -F Fuictional test & visual inspection Note: Supplemental sheets Inform of lists, sketches, or drawings may be'used provided (1)size Is8 1/2 in.X 11 in., (2) information Initems I through 6 on this report Isincluded on each sheet, and (3)each sheet is numbered and the number of sheets isrecorded at the top of this form. " - : :I I (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E 47th St., New York N.Y. 10017

Form NIS-2 (Back)

9. Remarks Attached are listings of Hydraulic Snubbers that were refurbished and changed out during testing activities during RF09.

Applicable Manufacturers Data Reports to be attached Note the listing of the Hydraulic Snubbers that were refurbished prior to and during RF09 including a listing of parts installed.

Documentation satisfies requirements of Code Case N-5081 as allowed by Relief Request RR-C4.

CERTIFICATE OF COMPUANCE We certify that the statements made inthe report are correct and this Reflacement conforms to the rules of the ASME Code, Section Xl. repair or replacement Type Code Symbol Stamp Original Code Data Reports to be supplemented by owners Section Xl Program No.02-009.

CertificateuthorziNo. WA Expiration Date NIA Sgned W CAS Dat e 5 .20 03 Owner or Owner's Designee, Tite CERTIFICATE OF INSERVICE INSPECTION I,the undersigned, holding avalid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT d1 One State Street Hartford, CT 06102 ___ihave inspected the components described inthisOwner'sReportduringtheperiod 09- o@-°> to o%-Z9-OR .andstatethat to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis Owner's Report inaccordance 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 inthis Ownee's Report Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this inspection.

Commissions A-(U P(,O Inspector's Signature National Board, State, Province, and Endorsements Date d 9- 20°3 (1282)

For complete work package, see Work Request A497030100 A514030100

Hydraulic Snubbers Replaced with Rebuilt Spares

-+ oz-00RcI Hanger Number Old Serial New Serial z1 or-71 N21-3109-G77B 820250 810060 E11-3152-G24 820187 810222 El 1-3158-G29 820251 820220 El1-3158-G30 810228 810220 E111-3158-G34 810027 810016 Ell-3161-GlO 810150 820227 EII-3177-G25 820072 810168 E21-3145-G23 820165 810164 E21-3147-G27 810008 810049 E41-3162-G17 820054 820202 E41-3162-G23 - 820106 820112 E51-3174-G33 810064 810167 E51-3174-G39 - 810019 820079 E51-3174-G40 810166 830019 E51-3175-G12 820093 820076 E51-3176-G17 810152 810138 G33-3244-G36A 820129 820083 G33-3244-G36B 810178 820078 G51-4059-G15 820151 810031 T46-3093-GI8B 830035 830040 EII-3177-G09 830037 820054

Hydraulic Snubbers Rebuilt and Re-installed

~Al zro Hanger Number Serial Number N21-3109-G72B 810159 N21-3109-G63A 830033 N21-3109-G63B -820196 N21 -3103-G20A 820014 N21-3109-G72A 810092 E11-3184-G15A 810211 EII-3160-G13 820135 EI1-3146-G16 830028 E51-3175-G13 820183 E21-3144-G32 820171

fl kcZ.7W Hydraulic Snubbers Rebuilt with New-Parts

Serial lSnubber Number size lDescription Work Packagel 810090 N21-3109-G77B 4x5 Kit, Seal - A497030100 Ring, Piston

__=_ __ 0-GRings -_ __-_ _

830004 T46-3093-GI8B 4x5 Kit, Seal A497030100 Ring. Piston 0-Rings Bar, Flat 1/4' x 2-Angle, I x i x 1J4

- - Connector, Male Bearing, Rod Nut Ferrule, Back Ferrule, Front Tubing, 114-820202 E41-3162-G17 - 4x5 Kit, Seal A497030100 Ring, Piston

________ -__ O-R ings -_ _ _ _ _ _ _

820220 El 1-3158-G29 4x5 Kit, Seal A497030100 0-Rings-

_________ _______ R ing, Piston 810222 El1-3152-G24 2-112x 5 Hex Bolt, 1/4x20x1 A497030100 Hex Nut, 114"x20 Pipe Nipple Angle Iron Ilxl -xl-/40 Flat Bar 3/8"xl Kit, Seal Ring, Piston 0-Rings 810049 E21-3147-G27 2x5 Kit, Seal A497030100 Ring, Piston.

O-Rings Tube, Cylinder 2-810138 E51-3176-G17 2x5 Bearing, Rod A497030100 Ring, Piston Kit, Seal O-Rings Angle Iron lVxlx114' 810151 SPARE 2x5 Kit, Seal A497030100 Ring, Piston O-Ring Elbow 1/4*

Angle Iron 1xlwxl/4" 820112 E41-3162-G23 2x5 ORings - A497030100 Ring, Piston Kit, Seal I  : - -e -

" ... . - . 1:-j .. '-I-% -- --

j . -1 q 11 -1 ' , -

I.

iI

-I

Hydraulic SnubbersRebuilt.wt e at ISerial ISnubber Number Size IDescription Wrk Package 820227 EII-3161-GlO 2X5 KIt, Seat A497030100 Ring, Piston

___ _ ___ ____ ___ ___ ___ __ -Rings 810167 E51-3174-G33 1-112 X 5 0-Rings A9000 Ring, Piston

_ __ __ __ __ __ __ __ __ _ _ _ _ _ _ _ _ _ _ Kit, Seal 810164 E21-3145-G323 1-1/2 X5 Kit, Seal A497030100 Ring, Piston

_ ______ ___ _____ _____0 -Ring s 810031 G351-4059-G315 1-1/2* x5 Kit, Seal A4970301 00 0-RiUngs

• ~~Ring, Piston 820066 SPARE 1-112" x 5 0-Rings A4970301 00 Ring, Piston Kit, Seal 820079 E51-3174-G39 1-1/2 x 5 Kit, Seal A4970301 00 Ring, Piston

_ _ _ _ _ _ _ _ _ _________ 0~-Rings _ _ _ _ _ _ _ _

830019 E51-3174-G40 1-112 X 5 Kit, Seal A4970301 00 Ring, Piston

__________ __________ 0-Rings _ _ _ _ _ _ _ _

810016 El1I-3158-G334 2-1/2 X 5 Kit, Seal A497030100 Ring, Piston

_______ _______ 0~~~-Rings 810220 El 1-3158-G30 2-112 X5 Hex Bolt 1/4"xl. A497030100 Hex Nut 1/4" Angle Iron 1xlx1/4 FRat Bar 114x2 SS Tubing 114" SS Nut (Tubing) 1/4" SS Front Ferrule 114" SS Back Furrule 114" Pipe Nipple, Kit, Seat Ring, Piston 0-Rings 820078 G33-3244-ZG36B 1-1/2 x 5 0-Rings *A4970301 00 Ring, Piston Kit, Seal.

_________ _________ ~~Valve Block (SN#820164) 820083 G33-3244-G36A 1-1/2"x 5 Kit, Seal A4970301 00 Ring, Piston

_ _ _ _ __ _ _ _ __ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -Ring s 810168 Ell-3177-G325 1-1/2 x5 Kit, Seal A90100 Ring, Piston

_ _ __ _ __ _ _ _ _ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -Rin gs _ _ _ _ _ _ _ _

. - .. . , 1: , - -"

N i-?- F1 Hydraulic Snubbers Rebuilt with New Parts

[(-0-?7--

lSerial lSnubber Number Size :Description -Work Packagee 820082 - -: SPARE 2x5 O-Rings A497030100 Ring, Piston

Kit, Seal-- -

810159 N21-3109-G72B 4x5 Kit, Seal A514030100 Ring, Piston:

0-Rings Sight Glass Assembly 820196 N21-3109-G63B 4x5 Kit, Seal A514030100 Rings, Piston 0-rings 820014 N21-3103-G20A 4x5 Kit, Seal A514030100 Rings, Piston 0-rings 810092 N21-3109-G72A 4x5 Kit, Seal A514030100 Rings, Piston

- O-rings 830037 SPARE 4x5 Kit, Seal A514030100 Rings, Piston

_____- __ 0-rings -_-_ _

820076 E51-3175-G12 1-1/2 x 5 Kit, Seal A514030100 Rings, Piston

-______ O-rings _ _-

810211 E11-3184-G15A 2x5 HexBolt, 1/4"x20x1 A514030100 Hex Nut, 1I4"x20 Pipe Nipple Angle Iron 1'x1"x1/4-Flat Bar 318"x1" Kit, Seal Ring, Piston

______ _ _ -_____O -R ings 820135 EI1-3160-G13 2x5 Kit, Seal A514030100 Ring, Piston

_______ _ O-Rings 830028 E11-3146-G16 5x5 Kit, Seal A514030100 Ring, Piston O-Rings

_ Angle Iron % x1i/4"x9_

820183 E51-3175-G13 2x5 Kit, Seal A514030100 Ring, Piston

_ O-R ings -

820171 E21-3144-G32 1-112'x5 Kit, Seal A514030100 Ring, Piston 0-Rings

-830033 N21-3109-G63A 4x5 Kit, Seal A514030100 Ring, Piston O-Rings _ _-

--- z . .

e -%- -

.fuz-Hydraulic Snubbers Rebuilt with New Parts k,02--OCR i . I of--

lSerial lSnubber Number -Size -Description Work Package 820054 El 1-3177-G09 4x5 Hex Bolt, 1/4wx2Oxl A514030100 Hex Nut, 1/4"x20 Angle Iron l"xl"xl/4" Flat Bar 3/8nxl:

Kit, Seal Ring, Piston'

_ _ __ __ _ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -R in g s _ _ _ _ _ _ _ _

..- 11 I - z.02-010 FORM NtI-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS i As Required by the Provisions of the ASME Code Section X!

1. Owner Detroit Edison Company Date 2-15-2003 Name 6400 North Dixie Highway, Newport Ml 48166 Sheet 1of 2 Address

2. Plant Fermi 2 Nuclear Power Plant IUnit 2 Name -

6400 North DIDde Highway, Newport Ml 48166 I .I -~ Deco Maintenance Address . - Repair Organization P.O. No., Job No, e.

3. Work Performed by Type Code Symbol Stamp NIA 1

Detroit Edison Company

1. - Name -' Authorization No.

. I N1A Expiration Date -

6400 North Dixie Highway, Newport, Ml 48166 NWA Address

4. Identification Iof System T & B N5-5 Diesel Generator Service Water - Division 1 (EDG -11)'

5 (a) Applicable Construction Code ASME III,,

Class3 19 71' Edition W'71 Addenda, N/A - Code Case (b) Applicable EditionlAddenda of Section Xl Utilized for Repairs or 1992-W '92 Replacements Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Nameof Name of Manufacturer Serial National Other Year Repaired, ASME Manufacturer No Board Identification Buit Replaced, Code Compohent No. - 0 ;0  ;-f f - 0" 0 or Replacement Stamped (Yes.

or No)

W . 66171-8 - N/A ' V1S-2096 1976 Replacement Yes

'R3000F142A -

Powell - i_-_i_- _

I ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ -

Description

7. of Work Installed a replacement Stainless Steel Alloy Disc in Check Valve R3000F142A.

B. Tests Conducted: Hydrostatic [ I Pneumatic [I I Nominal Operating Pressure [XI Other[ I Pressure _ _ _' psi Test Temp. OF Note: Supplemental sheets inform of lists, sketches, or drawings may be used provided (1)size is81/2 in.X 11 In., (2)Informa-ton inRems 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 Disc procurred per Purchase Order Number 350277, SA 217- Gr. CAI 5, Serial No. CM8990B.

Applrcable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this relacement conforms to the rules of theASME Code, Section Xl.

Type Code Symbol Stamp Original Code Data report N5-5 rT & B)to be supolemented bW OwnersSection XI Program Plan 02-010 and Work reguest #00OZO21705.

Certificate of Authorization No. WA Expiration Date WA Signed R.M. Hambleton LWad ISI Engineer \kc& ~-, Date 3 '< I .20 03 Owner or Owner's Designee, Tmi CERTIFICATE OF INSERVICE INSPECTION I,the undersigned, holding avalid 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 inthis Owners Report during the per o2Z-O.. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective rVeasures described inthis 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 inthis Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this inspection.

2~ .i ~' Commissions ZI G o Inspector's Signature National Board, State, Province, and Endorsements Date C/ 6 200)

(10/4)

7 T- 7 7 ,

0 : 7T - S FORM N-2 NPT CERTIFICATE HOLDERS' DATA REPORT-FOR.NUCtEARPiARtsAPJ APAA4 TcNg4CE` O0Z-0 As Required by the Provisions of the ASME Code Rules,Section III, Div. 1 N

- 1. (a!stanufacturedby Th Wm. Powell Company, 3233 Colerain Avenue, Cincinnati, -OH 45225

. N- t - - - = , I(Name end address of NPT Certi;cate Holwer; Ib)Manufactured for__etro itEdison, 6400 Dixie Nepot MI- 48166 Detroit_ 00DiieHighway!_ew ot,4_6

("I (Name and *ddies of NCertificate Holder for completed nuclear component)

2. ldentification-Ceriificate Holder's Serw! No. Purt CM 8990B Nat'l Bd. No N/A CRN No. N/A (a)Constructed According to Drawing No. P/N 2 6 - 0 8 5 5 2 4 -15 0 0 2 -OODrawing Prepared by The Wim. Powell Co.

Ib! Description of Part Inspected 1 - Disc for 8" Figure 3061 Check Valve (c: Applicable ASME Code: Section II[. Edition 1971 Addenda daltinter 71 Case No. N/A Class 3

3. Remarks: - - -

-8rie description of service for which component was oes;gned ) -

I 4..;

Item 4-8 inclusive to be completed for single wall vessels, jackets of jacketed vessels, or shells of heat exchangers .

4. Shell: Material T. - Nom. Thk..jn. Corr. Allowvin. Diam..ft..in. Leng-.._It_in.

tKind &SpeC. No.l t~id &Spe. N.I (Mm.

A i of. range specifiedi 5 Seams: Long H. T' R.T. _ Efficiency S

- Girth H.T.' R.T. No. of Courses S. Heads: (a) Material T.S. _fb Material T.S. _ _-

Location (too. Crown Knuckle Elliptical Conical Hemispherical Flat S.oe so pressure

-bottom, ends! Thickness *Redius Radius --Ratio Apex Angle Radius Diem. lcon ex or concave)

.- a{

) - '-_

lb) - - _

if removable, bolts used - Other fastening (Material SDec. No.. T.S. Size, Number) =. (Describe or attach sketcil

7. Jacket Closure:

IDescribe as ogee end weld, bar. etc.- If bar, give dimensions, if bolted, describe or sketchl

8. (a! Design Pressure' _ _ psi at

• F lb) Min. Pressure-Test Temp. F Items 9 and 10 to be completed for tube sections'.

9. Tube Sheets: Stationary: Material_ _ _ Diem. in. Thk. in. Attachment (Kind Spec. No.) ISubject to pres.) (Weided. bolted!

Floating: Material Diem in.Thk. in. Attachment

10. Tubes: Material O.D. in. Thk. In. or gage Number Type (Straight or VI Items 11-14 inclusive to be completed for inner chambers of jacketed vessels or channels of eat exchangers.

11. Shell: Material T.S. Nom.Thk-in. Corr. Allow. Jn. Diam. ft.-_n. Length-ft. in.

(Kind &Spec. No.1 IMn. of range specifIed)

12. Seams: Long H.T. - R.T.; Efficiencyr  %

Girth _ H.T.' R.T.' No. of Courses

13. Heads: (a! Material TS.______________-_T.S.

Crown Knuckle Elliptical Conical Hemispherical Flat Side to Pressure Location Thickness Radius Radius Ratio Apex Angle Radius Diem. (convex or concave!

(al Top, bottom, nds Ibl Channel If removable, bolts used (a) _- lb) (ci Other fastening

- -(- IDescribe or attach sketch!

14. (a Design Pressure' _ psi at _F fbl Min. Pressure-Test Ternp. F If poslweld heat-treated. 'Llst other Internal or external pressures with coincident temperature when applicable.

• Supplemental sheets In form of lists sketches or drawIngs may be useo provided: 1) tile I sl In x 11 In.: (2) Information in items I and 2 of this Data Report is Included on each sheet. and (31 each sheet Is numbered and number of sheets Is recorded in item 3. Remarki.

112/80) This form (E0040) may be obtained from the Order Dept.. ASME. 345 E. 47th St., New York, N.Y. 1001 7

- -. - i. . ; .  : .. ' :  ;.I r-' - ,

• . . - 1I **

• FORM,

. .. I FORM N-2 (Back)

Items below to be completed for all vessels where applicable.

15. Safety Valve Outlets: Number Size Location_

16. Nozzles:

Purpose (inlet. Rit;nforcernent outlet, drain) Number Diam. or Size Type Meterial Thickness Materal Hog, Attached

17. Inspection Manholes: No. Size Location g "

Openings: Handholes: No. Size Location -' . . sx4' Threaded: No. Size - Location

18. Supports: Skirt Lugs Legs Other_ Attached _

IYes or no) (Number) lNumber). (Descriial (Where &ho . i We certify that the statements made 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 11L (The applicable Design Specification and Design Report are not the responsibility of the NPT Certificate Holder for parts. An NPT Certificate Holder for appurtenances is responsible for furnishing a separate Design Specification and Design Report if the appwute-nance is not included in the component Design Specification and Design Report.)

Dt.- March 21 j3 2002 Sianed The WiM. Powell Co. _ __ __ _

(NPT Certificate Holder)

Certificate of Authorization Expires 12/13/03 Ceirtificate of Authorization No. N1579 CERTIFICATION OF DESIGN FOR APPURTENANCE (when applicable)

Design information on file at Stress analysis report on file at Design specifications certified by Prof. Eng. State Reg. No.

Stress analysis report certified by Prof. Eng. State Reg. No.

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 Ohio andemployedby H.S.B.C.T.

of_ Hartford, CT have inspected the part of a pressure vessel described in this Partial Dati Report on 3 7a E ntk-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 11.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the part de-scribed in this Partial 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 5. 24 8 g JZ-

~ctorssrgnatur Commissions OWED CA dnd.

National Board. State. Province and No.02-012 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS IAs Required by the Provislons ofthe ASMSECode Section Xa

1. Owner Detroit Edison Company Fate July 25, 2003 Name 6400 North Dixie H~ighway, Newport Ml 48166 Sheet I of 3 Address

2. -Plant Fermi 2 Nuclear Power Plant Unit 2

. Name 6400 North Dixie Highway, Newport Ml 48166 Deco Maintenance Address. Repair Organization P.O. No, Job No., etc.

3. Work Performed by Detioit Edison Company I Type Code Symbol N WA stamp I Name I I IAufthrization No. I IN/A 6400 North Dixie Kighway, Newport, Ml 48166 I Expiration Date IN/A Address

4. Identification N5.020 (T&B) Diesel Generator Service water System of System

5. (a) Applicable Consticton Code ASMEIII, Class 3 19 71 EdItion '71 Addenda N/WA 'Code Case (b) Applicable EditionlAddenda of Section XI Utilized for Repairs or Replacements 1992-92 Addenda

6. Identification of Components Repaired or Replaced and Replacement Components; Name of Manufacturer Serial National Other Year Repaired, ASMVE Namedo Manufacturer No Board Identification Builft Replaced, Code Component No. or Replacement Stamped (yes or No)

Win. Powell 66171-7 N/A V15-2078 1.976, Replacement Y R300OF142D

- Description

7. of Work Install replacement Stainless Steel Alloy Disc incheck valve to minimize wear of drisc oost B. Tests Conducted: Hydrostatic [ I Pnieumatic [I Nominal Operating PressureI XJI Other (1I Pressure ____ psi ~I .Test Temp. .

Note: Supplemental sheets Inform of Ists, sketches, or drawings may be used provided (1)size is8 12 in.Xli In., (2)Informa-Eion Initems 1through 6on this report isindluded on each sheet, and (3)each sheet isnumbered and the number of sheets is recorded at the top of this form.

(1OM4)

Form NIS-2 (Back)

9. Remarks: Replacement Plug/Stem assembly procured per PO#357727-1, Serial No. CM 9037B . Disc was repaired by manufacturer prior lo installation due to defective threads. (Reports Attached ).

Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this Redacement conforms to the rules of theASME Code, Section Xl.

Type Code Symbol Stamp Original Code data report N5.020 (T&B) suoolemented by Owners Section Xl Prooram 02.012 Certificate of Authorization No. NWA -Expiration Date N/A Signed R.M. Hambleton Lead Si Encineer Date B ILA = . 0 _

Owner or Owner's Designee, Tite CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or

'Province of Michigan and employed by HSB CT of One State Street, Hartford. CT 06102 have inspected the components described inthis Ownees Report during the period^9ki7 to0S , O0d. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken correcrve measures described inthis 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 inthis Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions A 0 Inspector's Signature National Board, State, Province, and Endorsements Date 3° (10/g4)

For complete work package, see Work Request R303020100

- - -  : 0 --  : ~~~-__:  : __  : -. C~8 t6 jZ;

~oAX~7oa.-OIZ.

FORM N-2 CERnTIFICATE HOLDERS' DATA REPORT FOR IDENTICAL NUCLEAR PARTS AND APPURTENANCES*

As Required by the Provisions of the ASME Code,Section III Not to Exceed One Day's Production Pg. 1 of 2

1. Manufacturedandcertifiedby The Wm-. Powell Company, 3233 Colerain Avenue, Cincinnati, OH 45225 (name and address at NPT Ceoniftc Holder)

2. Manufacturedfor Detroit Edison, P.O. Box 1659, Detroit, MI 48231 n

- (name end eddres of prchaser)

3. Locationofinstallation EF 2 Site, 6400 Dixie Hfighway, Newport, MI 48166

-Imme and address)

4. Type 26-085524-15002-00 ASME SA217 CA15 111.6 NIA -: 2002 (drawingr J imamLspec, no. tenalestrengthC) (year built

5. ASME Code. Section i1, Division 1: 1971 Winter 1971 3 N/A l*dithion) - addenda data) Idas.) (Code Case o)

6. Fabricated in accordance with Const. Spec. (Div. 2 only) Revision _ _ _ _ Date

7. Remarise Valve Tag V15-2071 .

8. Nom. thickness (In.) Min. design thickness (in.) Dia. ID (ft &in.) Length overall (ft & in.l

9. When applicable. Certificate Holders' Data Reports are attached for each Item of this report National National Part or Appurtenance Board No. or Appurtenance tPat Board No.

Serial Num ber In Numerical Order Serial Number In Numerical Order CM 9037B N/A (26)

12) (27)

13) (28)

(4) 129)

(5) ¶30)

(6) (31)

17) 132)

(8) 133)

(9) (34)

(10) (35) 136) 137)

(13) 138) *_ _ __

(14) 139)

(40)

(41)

(17) (42)

(18)_ 143)

(19)_ 144) 120), (45)

(21) 46_)

(22)_ (47)

(23) (48)

(24) -_ (49)

US5)' (50)

10. Design pressure psi. Temp. *F. Hydro. test pressure at temp. OF

-~e aPPlicabel Supplemental information in the form of lists, sketches, or dravAngs may be used provided (11 si Is 8sWx 11, 2)Information In items 2 and 3 on this Data Report Is Included on each sheet (3)each shet is numbered and henumber of shets Is recorded at the top of this form.

(7W98) This form IE00040) may be obtained from the Order Dept.. ASME, 22 Law Drive. Box 2300. Fairfield, NJ 07007-2300.

FORM N-2 (Back - Pg 2 of 2L Certificate Holder's Serial Nos. through CERTIFICATION OF DESIGN Design specifications certified by 1when appicablel P.E. State Reg. no.

Design report* certified by I bl P.E.-State Fleg. no.

CERTIFICATE OF COMPLIANCE We certify that the statements made in this report are correct and that this (these) disc conforms to the rules of construction of the ASMECode, Section I1,Division 1.

NPT Certificate of Authorization No. N1579 Expires 12/13/03 Date 10/10/02 Name The Wi-; Powell Co.. Plant 2 Signed(__iu__on (NPT Certificate Holderl raut 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 Ohio and employed by H. S. B. C. T. .4 of Hartford, CT have inspected these items described in this Data Report on , '/ ,and state that to the best of my knowledge and belief, the Certificate Holder has fabricated these parts or appurtenances in actordance with the ASME Code,Section III, Division 1. Each part listed has been authorized for stamping on the date shown above.

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 loss of any kind arising from or connec)a with thi/inspTion.

Date Signed _

f Nu-dear Aujthorized inspector)

_ Commissions t '&6(iO/

W~ad.ad.(end.

A)

A) endoxiernebtit and no.]

and state or prov.

FORM NR-1 REPORT OF REPAIR 0: MODIFICATION 0. OR INSTALLATION-OF REPLACEMENT(S) 0 TO NUCLEAR COMPONENTS AND SYSTEMS IN NUCLEAR POWER PLANTS

1. Work performed by The Wit.-Powell Company

• oPowell Order 814222 cIoarne) (repair organization's P.o. no,. job no., etc.) ,

3233 Colerain Avenue Cincinnati,~OH 45225 faddres) 2."NR" Certificate no- N1579 Expiration date. 12 /13/03 Owner Detroit Edison 2000 Second Avenue Detroit, Hi 48226 (address)

4. Name and Identification of nuclear power plant Enrico Fermi 2

5. Address of nuclear power plant 6400 Dixie Highway 'Newport, MI 48166

6. Identification of system

7. a: Identification of component repaired, modified or replaced I Disc for 8" 'Figure 3061 Check Valve b: Name of manufacturer The Wmn. Powell Company c: Identifying nos. CM 9037B K/AN/A *'N/A 2002 infr.'s serial no.) (Nai'L. ad. no.) (iuriadictional no.) (other) &W built)

8. Applicable section(s) I of ASME Code, 1L...Led tio Wne 1 addenda -N/A Code Case Class 3

9. Design responsibilities The Win. Powell C6ompany

10. Tests conducted: hydrostatic 03 pneumatic Q .. design pressure 0 pressure.- --.. psi-

11. Description of work Welded up and machined threads to correct dimensional problems (use of additional sheet(s) or keleihes) is acceptable If properly Identifiedi

12. Remarks:

CERTIFICATE OF. COMPLIANCE We certify that the statements made In this report are correct and that all design, material and workmanship on this repair Confo heap cap(ction of the ASME Code. (repair, modtification or rsplacement) sig..oc~~!J ( A&~.-, Gerald Grove- Quality Manager ___

(a uthoutzed representative of repair organization) -. (titlle) (date)

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 prov-Ince of, Ohio by E. S. B.CT of Hartford, CT have Inspected the repair, modification or repiacement described In this report oh. 1ZI 7 ..W.WIand state that to the best of my knowledge and belief, this repair, modification or replacement has been ma~e or constructed In accordance with the ap-plicable section of the ASME Code. By signing this certficlate, neither the Inspector nor his empioyer makes any warranty, expressed or im-plied, concerning the repair. modificatto9 or replacement described in this report. Futhermore, neither the inspector nor his employer shall be liable In any jnnner for any o n ~prope yJ damage or a lo3S of any kind arising from or connected with this Inspection.

M.lr_~ Sioned 1

~~~(Authorized Inspector) I I0,Z'7 (1state or province. National Bo"d

-j -( . r This form may be obtaIned from The National Board of Boiler and Pressure Vessel Inspectors, 1055 Crupper Ave., Cal's., OH 43229 Rev. 3

P°, 35?77-7 02-014 FORM tUS..2 OWNER'S REWORT. FOR REPAIRS OR REPLACEMENTS As Required by the Provisldns of the ASME Code Section Y-

1. Owner Detroit Edison Company Date October3,2002

- Name

-64D0 North Dixe lighwa, Newport MJ 48166 Sheet 1 of 2 Address

2. Plat Fermi 2 Nuclear Power Pant WnI 2 Name 6400 North Diie Highway, Newport MI 48166 I I -. Deco Maintenance I ~ Address .,I T RepatOrganimfaf PD,No.Job No. et S. Work Perormed by.. Detroi EdisonCompany - Type Code SSmbol I/A I SlaWsp I-Nlame Authorizatlon No. .. NA 6400 North Dbde Mahwa, Newport. Ml 481665 Exraton Date . NWA Arf&rmi ' I T&Nwad2 I I

4. denttficalfon I &81N554 and 21 - Bngrrognft futlpent SErvice Waer fvteM Dh ison I

.f System

5. (a) Applicable Construction Code ASME :M-; Winter  :

G-ass3 19 71 Edition 1571 Addenda,  : /A Code-Case (b) Applicable Edliw/Addenda of Secflon Xl Utled for flepalrs or, 199202Addenda Replacements

6. Identiflctin od CoWpents Repaired or Reptaced And p8amnt CoMpOns

• : 4.

4 -

Nameof . Nameo ManufachuerSefial Natnal Oer. Yar Repard, ASME Componerd Manufaclurer . No '

• 0Boa~rd - ldergicafot Mgi Replaced, Code

.N. or Replacement Stamped I.

(Yes P45F400 Target Rflk I WA a _

2000 230.I033 Replaced

_ orY Nor P45F400 Target Mck 4 I/A VSD-1276 2002 1ep1menL Y _

____ _.. I I I I - -

- Docsipton

=__ _L_I=-

7, ofQWok RemoVe existi valve for tesng and nstall replacement vahe Insystem. Send valve off she for testing.

B. Tests Conducted: Hydrostatic ( : Pnewnatic [1 - - Nominal Operatg Plessure P9-Other [I - Pressure - ps, Test Temp. °F Notet Supplemental sheets Inform of sats, sketches, or drawings may be used provided (1)size Is8 12 In.X I1In., (2) forma-lion initems 1 hough on this reportiIsInuded on each sheet, aWd (3)each sheet is numbered and the number of sheets Is fetordedatihe tpo!isform.

(1Ol4)

Form NIS-2 (Back)

9. Remarks: Replacement Valve procurred per P.O. #371566, Serial No. 4.

Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE We certfy that the statements made inthe report are correct and this Replacement conforms to the rules of theASME Code, Section Xi.

Type Code Symbol Stamp Oridinal Code Data rewrti4 (2I to be sunlemented Owners Section Xi Program #02.04 Certificate of Authorization No. N/A Expiration Date NVA SIgned R.M. Hambleton Lead Si Enaineer L Date,____

Owner or Owners Des~gneaTif CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid comnmisslon 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 Inthis Owner's Report during the petod8 /c -- - 02 . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described Inthis Owner's Report In accordance with the requirements of the ASME Code,Section X.

By stgning thIs cerfficate neither the Inspector nor his employer makes any warranty, expressed or Implied, concerning the examinations and corrective measures described Inthis Owner's Report Furthermore, neither the Inspector nor his employer shall be liable Inany manner for any personat Injury or property damage or a loss of any kind arising from or connected with this Inspection.

tt/ LA ffi Commissions /f/&$- A 4ZF J/' A'Z Inspector's Signature

• National Board, State, Province, and Endorsements Dale C For complete work package, see Work Request 000ZD11314

.3 . ~FORIM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS OR VALVE=S*

As Required by the Provisions 9tthe ASME Code,Section III, Division 1

• lof 2

~~~~~~~~~Pg.

1, Manufactured and certied by Tarpet Ptocic 1966E Broadhollow Road: E~ Farmingdale. NY 11735 -

(name and address of N Certficate Holder)

Manufactured for Detroit Edison; 6400 North Dbde HLWy New~ort, MI 4i (name and address of I-urchaseiq

3. Location of installation E9ndlo, Ferml 2 640 Nort Dixie H.. Newpoot Ml (name an adrss

4. Model No., Series No., or Type 99Z510-001 'Drawving 9 Z10-001 Rev. _j CR14 N/

S. ASME Code,Section III, Divsion 1:- 1989Nn3 None-(editio~n (addenfda. ae) (class) (Code Case no.)

S. Pump or valve Valve Nominal inlet size 2 Outlet size3

7. Matesiak Body 'SA1O5 Cap. SA10S Disc SA564 830 Blng N/A (a) 1~)()(d)()

CerL NMI ~~~~Body Cap Disc Holder's Board $~itSenial Serial' Serial No. NO. No! NO. No.

3 NWA ~ :114 -54 4 5.

) .113 .4 W/A... -WA~ WA NWA Supplemental infotmation Intomn-of lists, sketches, ordaig may be used provided ()sIzIs8i1.()norato in tms I Through .4 on WhlData Report IsIncluded on each sheKt (3)each sheet Isnumbered and the number of shets Is reconled at the top of ti~s foan.

(12/88) This form (E00037) may be obtained from the Order Dog1, ASME, 22 Law Drive Box 2300, Fairfleld. NJ 07007-2300 REPRINT 6/113~~~~~~~~~~~~~~~~~~~~~~~'

P:

FORM NPV-1 (BACK - Pg. 2 of 2)

' eslg. Certificate Holders Serial No. 3 &4 Designconditions 175 psl 125 *F or valve pressure class NIA (t)

(pressure) (temperature)

Cold working pressure 285 psi at 100 -F

10. Hydrostatic test 450 psi. Disc differential test pressure N/A psi

11. Rarnaft:

CERTIFICATION OF DESIGN Design Specification certified by Lawrence D. Burr P.E. State Ml Reg. No. 33999 Design Report certified by Not A2plicable P.E. State - Reg. No. _

CERTIFICATE OF COMPUANCE We certfy that the statements made in this report are correct and that this pump orvalve conforms to the rules for construotron of the ASME Code,Section III, Division 1.

N Certificate of Authorization No. N-1947 Expires 12112/2004 Date '7 ftKI2 Nama TacetRock Signe s=-

(N Gert~eate Holder)

• Rv£. Glazlef, QA Manager (N Ce*tificate Holder) . (authorized representative) )

CERTIFICATE OF INSPECTION 1,the undersigned, holding a vaUd commission issued bythe National Board of Boler and Pressure Vessel Inspectors and the State of Province of New York and employed by OneBeacon AmedIcalIs. Co.

of Boston. MA have tnspected te pump, or valve, described in this Data Report on 1 2 and state that to the best of my knowledge and beiief, the Cefrtilcate Holder has constructed this pip. o valye,-in accordance with the ASME Code, Section 111, Division 1.

By signing this certificate, neither the inspector nor his employer makes any warranty, expressed or impried, conceming the component described in this Data Report. Furtherrnore, neitherthe inspector nor his employer shall be liable In any manner for any inJury or property damage or a loss of any kind arising from or connected a[prsoqa with this ins-pction. (21f.

Date 1TJiZ Sig ed G Commissions 07 AM 6 ,C g3

. ~(Nafl. 8d. (inc. endorsements) and state or prov. and-no.)

(1) For manually operated valves only.

I

02-01 5 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl

1. Owner Detroit Edison Company Date I - -:  : 2-11-2003

'Name 6400 North Dixe Highway, Newport Ml 48166 Sheet of

-- -< Address II -

I 7

2. Plant Fermi 2 Nuclear Power Plant Unit 2 Name 6400 North Dixde Highway, Newport Ml 48166 I -- IAddress Deco Maintenance  :

3. Work Performed by

- Repa Oranization P.O. No., Job No, etar

.. Type Code Symbol Detroit Edison Company Stamp Name IN/A Authorization No.

N/A Expiration Date 6400 North Dixie Highway, Newport, Ml 48166 Address- N/AW

4. Identification of System (N5-J120-N5-1) Control Dod Drive System

i. (a) Applicable Construction Code ASME liI, Winter Class I 19 71- Edition 1971 Addenda, (b) Applicable Edition/Addenda of Section Xl Utilized for Repairs or N/A Code Case

- 1992- W '92 -

Replacements Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer Serial National - Other Year -Repaired, Component Manufacturer' No ASME Board identification Bu-lt Replaced, Code No. or Replacement Stamped

__'_._-_ __. L-.

(Yes

-Conitrol Rod Drive X  :

General Various N/A Ct102D@

orNo)

Mechanisms Variou Replacement Yes

'Electric __-_- s Description

7. of Work Refurbish Control Rod Drive Mechanisms for installation in RF09.

8. Tests Conducted: Hydrostatic [I - Pneurnatic l[ Nominal Operating Pressure I I Other (XI Pressure .I'_- psi Test Temp.

Note: Supplemental sheets Inform of Usts, sketches, or drawings may be used provided (1)size is 8 112 in.X 11in., (2)informa-tion InItems 1through 6 on this report isIncluded on each sheet, and (3)each sheet Isnumbered and the number of sheets recorded at the top of this form. is (10194)

,1

Form NIS-2 (Back)

9. Remarks Refurbished Control Rod Drive Mechanisms for Installation in RF-09. Replacement parts were procured per various Purchase Orders as detailed on attached sheets. Copies of available Code Data Reports are attached.

Applicable Manufactureres Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this replacement conforms to the nules of theASME Code, Section Xl.

Type Code Symbol Stamp Original Code Data Reports for each Control Rod Drive will be suoplemented by OwnersSection XI PrograM Plan 02-015 and various work requests as listed on attached Sheet 2. For tracking purposes CRDM information will be maintained inN5-J120-N5-1 Certificate of Authorization No. NWA I _Expiration Date_ NWA Signed R.M. Hambleton Lead ISI Engineer Date_ ViZIWAA 1;~.20092)

Owner or Owner's Designee, Titl CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding avalid 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 inthis Owners Report during the period8-8 .. L0&to CZ-.S °3 . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis 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 Inthis Owners Report Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this inspection.

1 14I&R'e'lg C.

~~~~~~~~~~Commissions

.- Y Inspectoes Signature National Board, State, Province, and Endorsements DntA I . /5 Jeo?

(10i4)

NIS-2 For Section XI Program 02-015S I VIX Sheet 2 of .2 --f)

Serial No. Rebuild WR (1) Cylinder.Tube/ Piston Tube X__________

__ Flange (480-8571) Other ASME Parts 4558 00OZ991677 #5545, PO#,266443 (482-5312) -

- =:

1. 1641,PO#314467 None 4524 00OZ991706 ~ ~~~(2) . ____-

4580 . #0363, PO# 287926

.00OZ991691 #6507, PO# 266443 None

___. ___ #1722, PO# 314467 None 3180 X - . . -. . . .(2) 00OZ991687 .

1. 3023, PO# 314467 None 3931 0OZ003983 #6180, PO# 266443 (2 ) . - . . .__

1. 1855, PO# 314467 None 4362 OOOZ991694 (2)

1. 5423, PO# 266443 #1410, PO# 314467 None 4508 00OZ003990 #5752, PO# 266443

-.-- :_______-______________ (2) __

-:7 4408 00OZ003997 #0307, PO# 287926 None

. . Ring Flange Cap 4512. 0OOZ991683 __-_. __ ._____ ._. Screws #480-9052 (3)

. #0333, PO# 287926

. 4006 00Z991696 None

#2877, PO# 314467 None 4307 00OZ003999 (2 ) _ _._

1. 6387, PO# 266443 #1380, PO# 314467

____(2 _ __ __ _ __ _ _ __ __ _) __ None 5950 000Z012225 _ _.--

3954 . 00OZ991700 ._._________one N

1. 5770, PO# 266443 #3062, PO# 314467

____ ____.__ _.__ _._ _ None 4092 00OZ955551 (2)

1. 6086, PO# 266443. #0637, PO#

4511 00OZO03987 295214 None

1. 6125, PO# 266443 #2074, PO# 314467

_ _________,_ __-_ _-_ None 4569 00OZ991679 (2 )

4526. #0378, PO# 287926 None 00OZ991681

-3152 00O0Z991704 None 4406 00OZ991689 '- None 3528 000Z003995 #5451, PO# 266443 None 6475 00OZ991702 - None 6412 OWZ991675 None 4590 00OZ991698 . None

, #1374, PO# 314467

_______._________ None 3339 000Z991685- (2) _______':_ ' ___' -

1. 1709, PO# 314467 None

_ .___ -__ _ _ _ _-__ _' _ ,_ (2) '_ _ _ _ _ __:_ _ _

Replacement Cylinder Tube/Flange assemblies Nuclear Station Control Rod Drive Mechanisms were utilized from Shoreham 266443. Product Quality Certifications that were procured per P.O.

were supplied, 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.

2) Piston Tube Stock No. 480-8699

3) Replaced Ring Flange Cap Screws with those Number 6261,PO# 266443. Also reference from Shoreham drive Serial CARD 02-14887:-

~4 X SX X ,,hee s3 oh e37 f 7

-of,ofH.'

2 w I,'~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~-

M

- m* - A;-m O heAt ~

B: 5 ~ ~ ~ ~ ~ ~~~~~~~~~P*

,JI*

PON Aw~~

I~~~~~~ 21.d1. f I:T

___ ___Tr -

he - .-: 0

• : ~~~~~~~~~~~~02-01.5 r:wg 4 tet-

~~~~~~~~~~~~,0 ir X - .2 3; X , '- -+f ,', ' - ' -  ; '

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I - .-I I _: - . I ..... . - II - I ... .-__

4 I. - -- 7, - I . - -- -_ -

W~iRiiCATfE HOLbRS;'

As required by the Pro'vLsouL DATA of the RE

1. PAIMzft -- taed L Certlfiled by :.iGMAW LSW--

.. . Elerxw_ 1~WM*CMAV (CNowmead Mddres of NK C~t NAnufactured for : _Fei 1rdI.9 II

£ =

Mmfekt £&diabW1 -48flM

- C l~~~~~ane d AMdmesa of N Cartfel~tae3.

!-1detification. - Certificate i*older's S/I of Part 1

4 Constructed.Accordi j to Drawing No: 7~D2~2Rv~b.Pvjie Cb)1Dscrition, of Part Inspected: ff=3r!TbtleA2sew*

(ct) Applicable ASIE Cods: Section III Edition, .1.L4 DMenck Date ~. ae

3. WtAM~: Sfte~1anfuiatkYM p& Reb.It&s a ~St11MW5i,! 47k.

Brief1s d~eacrpLLOU at sauvce £oM W1eb ecu was v 6eeep.o I

~~~~~~~~~~~t

.. i d

>t fc~ertify that the ttatents in this rert cfors to the rules of constructlon of r corroct and this vessel part o the ASf Code Section Ill. ( The applicable0e rS

eGprt are Wa the responsIbility

• -sresponsible for furnishing a separate of the IPT Certiffcate Holber for parts. An 1T Certl the Coonent Design Specification and Design aciffeation and Stress Rport If the a Stress Report).

late: M . . SgnedE a.

1,rffIcteof Authorization zt Wrs:Certif Expires: - j/1Z icationofpaztn Certificate so1AIS4%tt)i lb.:3CS Certification of DeSign for ppte Y

-Oesig infoiwtion an file at St'es Son .CgEw S arAtysis report an fie at G . SenJose. CA DCS253 Rev. 2 bisign SpocIficatlon certified by

. Prof. LEg. State

. .. &M. lo.

!.1 =tA6b54 KoIrI

kti-tta analysls report Certified by Ed&d~~h Prof. Eno. stute .Q . tog.

Certification of 8hop paspction

i. t. unersigned. hold a valid efsslio by the gatinal State or Province of .I up2 Insiected the nart of a Srensure wisiel and eqiyd by Pyvw off14Ag of Board of laIlter and Pressure td staite tht to the best oi myknowledge described In this Partial Data 9=*rt On

aawrdance with the ASHE Code Section and belief, the IPT Certificate Holder has coostru Rjysigning this certificate, neither 11f.

concerning the pert described in the Inspector nor his esloyer makes any warranty.

cqir shhall be liable in any manner for the Partial Data Report. Furtherwre, neither the Jnspector connected with this Inspection. any personal Injury or property damages or a lss of any k1 4: - /i' Date 1 petorsSignature

, NC 1231. 0kMaK ifati admi

• $up/} - nta :Peee~t ..in forM.. of.Zlsts stetche5-2ovi e1 (j) S1%e£ s 0-1/2" Re~ort t Includeon eaich shq et Z 11, 2f (n31 each he

s. a -Iio x nurrof sheets recorded in Item 3.n sn 6el : .

fr S" -

h .LW .

Ik V - I ,-

.lz!' , ,,

- ~~~~ g .. Wi -~*-~

tg 4 Incl. to be com1eted for single wall vessels Jackets Issls.or sMelseffit

. >- - EsInal Corrosi on

'. Sh-14: Material T.S. Thickness _ tn. Al ne i. ala. .

In._ ft. _

Long _______ _ Mi. _________ I.T. _______

__ __ __ __ __ _ H.T. __ __ __ __ __ _

( aterial M. (b)Nhtarial _-

Loatbal( Ton -- Cr-n Knuckle Elliptical Concial - otilerical 'iat

.., Sottn nds ) Thickness P ilus. Radius Itatic. Apex Angk radius remvbl bolts ud _Other fast

.7. Jacket Closure: (r

'L ~~~~~1250 ps t575 F at tm o~ ltiss1> 10 to be copleted for tube sections 3S Td.S ee>>ts Stationary. KItteria1 - Di. Thikes_

Floating. Muterial _ckness _ in.

l O,. Tub: Vatertal  ; O.D. In; Thickness - -

Itea 11 - 14- lc. to a uoVleted for Innerscimbers of Jacketed vessel, or chamiels of hat ezd kainal Corrosion l >k11 St}1l: aterial T.S - Thickness _ In. Al-Wance in . _ ft U. S00: Long - . H..t. It. T - 4

• S;:irth __________ H.T. - R.T. _

'Ne : ta) Xaterial _ T.S. _ _ (b) Iaterial Crown Knuckle Elliptifal Concial HIispherical F-at Location Thickness Radius Radius Latid 4- Angle :Laus a W ~b)CnueTa ptt-x - - __

remayable. bho "If e (a) 7--__T- V-itser fastening ___ ____

'1 4.O__gn pres__ psIat _ F at tUm lion below to be mpleted for all vessels where appllcable.

1S. .%afety Valve Outlets: lumber Size Location _A 16.- Xszzles: Ap.(tb",-

N s_

.InmiPstiOn Manhoes. #o. - Size - Location _

prings: HandPiole.,. lo. Size Location _A

-Mo. Size Location >

Threaded, t1. SjpotS Skirt ____- tugs . Legs ther _

I iav al

-L :d pmew.

-~adM'ut uth Qtim -VISd.

t... ,mn --.

1. U*~actured & Certified by -~WlAC*CMV 3901 C NswaeRol

~~~ -~I Cart Ificate Makder: S/M of Part.-a Con'stmated 4ccording to Drawing No: '828G12 Rev 35 gPraa.

th~J~Isrlpttan of Part lni.ected: Pisto TvA5 ri!

~ ~ ~~~~tonIIEiin17

.1~

t4Aplieahle ASM Code: Secto diinik.Iinda Al Utet ..

3. W=i~: %andwdmj&f~rusei*MReact.W~~ mftaWtstda (I:zLef d"Oarituma of garyactow wh iich caspoamut Wsd." d h*.

• X I 1iA4 4 AtWm1wes 4 df~miz.

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id- ~SAV3-850 OLrftx 13rcox1.W

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.to I . .- bE- Jim , } " ' I An:~~~~~~~~~~~~~~~~~~~~- uo 's i* 1 -: . i  ; .. L~_: I.M 7-%- I  !'C 02-015 Sheet 16 of 37-Li N4 MPT CERTFICTE HOLDERS' As required by the Prolsioon DATA REPORT FOR .WJLEAJI of theASXa Code f1stle

1. Kamufactured &Certified by:

-"b1 Faiufactuired for: 1 Fefmil- 2 NeWpoit and 54ddrsuo at Mlfbn4S1M (5~~~~~~~o CextLtcata Nides ~ Z.Sc~tficaionCertificaf cat iig Holder's 5/b of Part-: C=7 L (a) Constructed A.-cording to Drawing go: 7M= M28G12 Rev 35 OK. Prqparad by (I)5sasriptfan of Part Insgce: t&= tessmA C)Applicable ASWE- Code: Section III -Edition 197L.. Addenda Bate . case 50.. z t S.Lef devcrlption of sareswc for uhIcb .ampcont eas "4 jji.d S., .. - ~-' B- d.tIfy that the conftos to the rulesstatments in this of construction ofreport are correct and this vessel Report ar not the responsibility the AE C-Ia Section part or .a r Is responsible for furnishing of the lPT Certitf bate Hbider 111. CThe appvicle & a separate Design Specification for parts. An IPT the conent Design Specification and Stress Report and Stress Rqport if Certificat, the eppbt Date: 1 Signed - 1 AVy Cartificate of Authortzation Expires: x F PI Certification of rization S. Certification of Design DesignInformation on for pea i ., fIle at GECanp. San . C .I Stres analysis report on fIle el at GEC I 'h. Mnv. an kse. CAI 7 DC22MS 3 Rev. I Design specificatton certified by- -B. J. -Prof. Eng. State DCUzMSs4 Rev I leg. no. Strits anabysis report certified by YOWO 'rof. Eng. State Raeg. no. M

• t 0 . 'Certification of

.I1. the undera'gned, Shop Inspection State .r Province of va~d cc aold~g iss'on by the Itational Board '.spected the part of ai Cne n and mg Toyed by of Eoiler aande Pr s ssure I end state that to the best pressure vessel described In this L&Wr ef ftfe of oe0rtyof of my snowledge and belief, Partial Data Report on otcordance with the ASKE the XPT Certificate Holder yvsigning this certiffcate, Code Section III, has construeted I czncernhin the part described neither the Inspector nor his esnp1yer I I s.,ll be liable in any sanner -inthe Partial Data Repart. Furthermore. makes any warranty, express 0 .. t rnwanected with this inspection.for any personal njury or property neither the Inspector nor danages or a tOs of ny o p d kind . I 9

oo

6. a j ~ar*.C ,'A-A~

Date IZnspecter' Signature NC1231. ..IVs6s Natioal Board. State. frovlz k evehfntai sheets in fozm pro of lists -stetches - pp rteeIs 4) size is 8-1 9 -, nuEmber of sheet ncluded on each shee r11", () informat or in in 1 awgmdSI s recorded in Item 3. 3andg3) each sneet is numbI -.MARKS'. A 02-015 Sheet 17 of 37 ?O-r0X X-2 ; back)I i si-I Ire1. to be cchleted for single wall vessels. jackets

• vessels, or golls of

4. Shall: Katerial Knetnafnl -- Corrosion s

T.S. Thickness {t~f:fL- Ite;d 1*. Alicuana _ In. Cie. _ &-I 44 -IwA ~irtiv______________ .T. __________ T.- ~:. (a) Mterial _ _ _ _ Y.S. _ _ _ _ _ _ _ _ (b ) $a - ttin (rp - crown . Ends ) Thickness Knuckle Elliptical Radius Radius Ratio Apex Angle WiQ' .If weovabIt.- bolts used________ utner 7rtagIn

7. Jaet Closure:

ID--N- ft W"A.r rawswIu ~~b. f bdw ' h n pressure 1250 psi at P5 F at t; -JW=9 und 1 to be cbmpleted for tube sectimns -. rbi Sbiets: Stationary. r4.. Material Floating. -lfd&Ipc.O.) (t (tmlpmmm Thcknss. Material __:_Db. __ -_Thcb_ Tpbes: Ikterial_ i 0.D . Thickness rh0aki iI . Jt tt l - 14 ncI. to 'comleted for inner chambers of Packeted vessels. or carls of I

• 11. shell: paterial :MonIa& Corrosion  :

T.S. Thickness _: n. Allowance In. .Ala_.

~~~~* I (W ft.

A.;!~I .. C .;t--.A I Ltongl _ _ _ _ _ _:__ &:CI N.Y.T. x Bir - -  : t _______th - It .T. T. . X .~13* i1A*: (S)Material I. . - .~~ -_- r.s; -s>- (b) geterial .__ ,**^, -:: Crown Knuckle Le . ..tifn -Thickness Elliptical bowcaI If'oEttce'a Radius Radius Ratio lHsptrfca1 ls_ ed - Apex Angle Radius J -f~rmable. . iwolts gsed (a)___ _ rte?fini N7 k s !Fpressure psi At'

Item b*ew to be corpleted F at for all vessels where applicable.

15. Safety Valve Outlets:. Number Size ICX'sa Ies: Ptw~mIwo.I Location' W04 Offib I M~i~ O.kM airow l.

i-I_,0 IhW'_bwaa Insoction Ra. ehnholes. ~ rakft~ !i 47. atfn Ko_. T;, Z Openigs: Iles, No. _holes,_ Size  : Location _ Size_ .f* _ ..B Supports: Threaded. Skirt- -_-- lo. LUS _ Size LouatIon Location -_ S (Y.oea -(tri" 1 Oter__- -- tIr 1 - I tF1"tWW *tm1,.d*& -: iiio' U CUV.Lg&&W IJ E -VWF'Nnufa T Ctiwed & cerified by Ga eE c M .and ' Ldr&aa 1 C~1~ad ~~ ~i~) Rumnfactigred for: 2 GD~ JdA 88 - ~~~CJM"mand Addraas of IW~ ia. ie o te Wdent Ificatiton - Cart ificate Holder's SIX of Part.: - (a1 Conutructed Accordtnr to Drawing o:. MMM)28012 R~3 Dwg. rid (b) escrptin ofPart inspectd ionTesem/ CZ) ApplfcAk AMI Code:: Section III . Edition IE9... £Mdeoda Dat* (SBrief dsscriptica of sarvic, for which opoqnoevat nu-ii -W AZ ~~P. ~ ~ 2. nu~d~mb

1. bV*DW5~O1"1(719E474)r M~1g-F"o 4  ?,#T*W~~*xZ875-F=

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~~J'1. Z tkx2WC% 02- 01 Sheet 19 of 37 _ 'D~~~~tAREPOT~~~~FORICUgr_

As re ired by the Provis of the Code t sl .

~ 3 Kuiacurd &Ceti te b:

(3m Ab Add"" of UW tc . Identif cation - Certffic-e olderis S/11 of part . _ _ _ 1t4) Constrcted Accorda, to Drawing la. ?M 228M712 RO M5 Dg. Prepared Iw (h) kecription of Part Inspetd Pbn ro -- Mm

• - jc) Applih] ASEaA Cie: Section 113

• Edition 1974 Adui~d fata A cdi8

'. Wi ";slS:@ I9*fRbhetrcsf~ PA4tA~~~ sia 1o -~~~~~~~ ,te _criptin or servc - Tis. : _-er _hc "uom ws k..' p g-. q itlfythat the Statoenets in this report Repior are sothe resoonsibility are corwet and this vessel part or ASC e . $ k~or amnottheresonsiiliy o tho the WCode Section III. ( The pplicae i fi responsile for furnishing a separate OP Cert~fcate Ho~lder for parts. An CT aifctol~ Design Si.cfficatfon and Stress Report If the conent Design Specificatici and Stress Report I. . the a qim l  ! ,>.-$. .ite: - Slgned (.o B cz crtrlct*5*&L)

• C; Cartificate of Authorization Expires:

6 Certification 1c horisatia, o . Certification 6t-Design for 4p e,, D.sign Infaretifn on fIle at tnc. GECOmim. SanJos. C ei l Stress am lysis report on file at

• G F:n Sa 7. Cbv OCUMJSI Lov. 2

$Oka specification certtf;edby Srdhr.

.M. Prof. Eng. State l eg. go.

Fs l analysis report car tified by Er Prof. Eng. State Cf Rag. Certification of Shop Insp tion n . the wmdersigned. loldirga valid celufss1on aSte or Province of .02r41 by the National Baird of Boa*r and Pressure 1 >, I Insp: dthe part of a pressure vessel and amployed by M described in this Partial Data Report on of - 'h .{X iL *t dccordance with the AS4iE Code Sertion A I[I. r sig-ing this certificate, neither the Inspector nor his ra~ployer makes any warranty. xrsd N l -concerning be l I3isable the part In any manner for described anyPartial in the personalData injury or property Report. Furthermore, damagesWeither or a loss thre Im tr'sly >; - ' - - -M/ @ / t - o- Cm. not* ; 4 D^> C7 Inspectors Satur r1U rd, S .*.S peritals( seet! or oin ists-s ^ oktt s n.Lclude4 on each sheet an (3) each etches- :r n rnukber of sheets is recorded in IteM 3. bE"MA~ '. sheet Is wis & S. . 01,_ ~~~~~~~~~~~~~~~~~-1 Set20 of 37 IIt44lnl. to be cowleted for single wall' 1esel. jackets vetuls, or shels of ia t KomInal Corrosion - 4. Stll: Kateriai t.s. T____ Thickness _ in. Allowance _ . te. ,$-T - tT= ~~ £~~irth _ _ _ _ _ .T__. __ _ __ _ _ __ _ T.

• 6. 4i~a(a)Ma eial __ _ _ _ _ _ _ _ _ _ TS _ _ _ _ _ (b) Material_ _ _ _ _ _ _ ---

~~'- itita CTop r~I own Knuckle* Elliptical- Concial Namtspharica1 . '.~. ~tt. Ends )Thickness 3dius Radius Ratio, Apex Angle Radius ~0' If bk , baitslused - _ _ _: Other fastening

7. Jaiet Clesure:

l ~* _m - ' ( q ~m' bat ,,, .- -, Fr. 2250 psi at S75 F i  ; ~t usand 10 to be copleted for tube sectiors -  :. lb 11l- 14 1nek. to be :=0pted for inn:er hamerg of Jacketed vsetsel. or damsel of het . bel tc: tatony.aterial Hoag:Flatingmatterial____T___. T.. Ths in. Via. Allance _______ ___ . Ala. ft.___ f t Tois:. [onte Its~~~~irth 1- m. hickness to sw~td fr inner c

00. i rst o jac Apckexs Anagssl. t ItT.

vessel:,oRadruuseRadiu l oa ~r A -ble wed = Noinal 7 C rbi -M) 7 I3__ psi at _ F _ tts bkw to be cpkleted for a1 vessels where ppicable

15. Safety Valve Outlets: lumber Size _________________ Location

_______ _____ ________t ____ ______ _ _____ - E'. ~ 17.lnspcion anholes. N _______ Size _______Location 431ARPog: ffandfices. go. _______Size .- ________Locatio km Threaded. Io. - size Location , upperts::- Skirt _ Lu - Legs --- Other  : . . S.... m -~~~~~~~~~(W1d)To 2-2. _~ t~~ - ~ r~w glwMa pr~i ua0g0~di O0flM i p; f;~S t aU the Provtulon of the

1. Ufactured &Certified by

• 'mfectured

-WW for: . - 2C m C em. ad Address of I Cer tsteatd cdr ttfficatian - Certificate Itldirts S/X if Part 6. . . # (Al Constructed Accordinr to Drawing No: 70 1 Rev 3 Dug. afrjj (h) Description of Part inspected: Piston Ts---- al-(c) Applicable AN Code: Section III. Edition 19SL Adkends Date W75. Ci

3. IBM=: Stndnrtc~flM r tef with Reecf. Mdnfo A3 tet 16s Mt C trief descripti of sarylas for hich cpat was E ., ..,  : -tk1.:A0tA .r  ;' ' t- ' e 4-  ;. £ tf~mtzIbess

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I JFQS~d ".d-ft ufIo fdI.( M w= 31:1 y-ZOk'4:: 02-015: Sheet 33 of 37 I. mai~actured a cert if ied by GrWExt 3901 QW4MO Road, K*CW50oii. A mzfactured for: FONW;. 2 Nemo-t ff~tv- 491 CeriflateHolder's S/K of Part 07 (at -tamncedAccording to Drawng No: 9D2G1 ReV 35 Awg.Prepred~ esrpt1dn of Part Inwp -%=i. .ad: PLbton TijeAssen;WA (C) -AplIcable ASKE Codei Section III* Edition .lL Addenda Date A~ ae '3. RERAMi3: Mga~~for Lee ioYb Reacw,.P~s~kAtet1t12m n

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j V :$ 5~~~~~~~~~9I S s4-vrf X - w) f ; t S -- f As L~~~~~~*M W0-*l P- = Wg is .f j - was -F- .:.. - ..02-016 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl

1. Ownrr -Detroit Edison Company  :  : -Date May 3,, 2003 Name 6400 NorthDixie Highway, Newport MI 481668  :. --.-- Sheet I 1of 1 Address

2. Plant Fermi 2 Nuclear Power Plant'  ;-; 0 Unit 2 Name 6400 North Dixie Highway, Newport Ml 48166

- Deco Maintenance _ - Address  : I RepakOrganizatmo P.O. No Job No, etc,

3. Work Performed by Detroit Edison Company Type Code Symbol NJA Stamp I

-I 0 Name Authorization No. N/A 6400 North Dxe Highway, Newport, Ml 48168 Expiration Date N/A Address

4. Identification Main Steam Line Drain Pipe Supoort N30-2186-GI8 of System

5. (a) ApplicablbConsbtrctionCode AISC8'andr NWA Edition - _: Edition - Addenda, NIA Code Case (b) Appricable Edition/Addenda of Secton a Ubtlized for Repairs or 1992-92 Addenda Replacements :__-_--; -___-_

8. Identification of Components Repaired or Replaced and Replacement Components Name of -Name of Manufacturer Serial National Other Year Repaired, ASME Component No Bard oManufacturerIdentificaton Buillt Replaced, Code No. or Replacement Stamped (yes

__ _ __ __ _ __ __ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ~~~~No)~~~~or N30-2186-G18 Wismer& N/A N/A N/A 1984 Replaced N B ecker __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

7. Description Repiace existing pipe support clam for suDnort N30-2186-1 8 with a nine attachment designed of Work ner ERE-3 1931 to preventfrestrict namg rotation on pipe.

8. Tests Conducted. Hydrostatic[l FPneu matic [ - Nominal Operating Pressure (1 OtherfXI Pressure psi I TestTemp. I Note: Supplemental sheets Inform of Ilsts, sketches, or drawings may be used provided (1)size is 81/2 in.X I in., (2)informa-tion initems 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 lop of this form.

(10 4) Form NIS 2 (Back)

9. Remarks: New baselne inspection performed. Material utilized W'plate A36, HtI U1192139A PO 385500-01, (2)24 U-Bolts- Ht I 791 OA, PO# 380087.

Applicable Manufacturees Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made Inthe report ar correct and this Replacement conforms to the rules of theASME Code, Sedion Xi. Type Code Symbol Stamp Orlianal Construction records forN30-2186G1 to be sucolemented byvOwners Section Xl Proararn 2-016' Certificate of Autwization No. WA Expiration Date NIA Signed R.M. Hambleton Lead ISI Engineer ,My 0 Owner or Owners Designee Ttl CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding avalid 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 OneStateStreet Hartford.CT06102 haveinspectedthe components described Inthis Ownees Report during the peod,8 -O to 5-S. ° and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis Ownees Report in accordance with the requirements of the ASME Code, Section XU. By signing this cerilicate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described Inthis Owners Report Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this Inspection. A 2 f i = ~Commissions MvTe Inspectors Signature Nation~roard, State, Province, and Endorsements Date Zt4V -o 20 0 (10194) For complete work package, see Work Request 0OOZ021044 I? , ' I 02-017 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS: I . As Required by the Provisions of the ASME Code Section Xi

1. Owner .Detroit Edison Company ':' -I II Date July 25, 2003 Name 6400 North Dixie Highway, Newport Ml 48166 Sheet lof2:

_ 2 Address

2. Plant' Fermi 2 Nuclear Power Plant Unit 2 Name 6400 North Dixie Highway, Newport Ml 48166

• Deco Maintenance

. Address .- - Repair Organiaton P.O. No, Job No, etrc

8. Work Performed by Detroit Edison Company .- Type Code Symbol. WA Stamp .- _ _ _ ' _ _ _

, - ~, Name I T- Authorization No. WA 6400 North Dixie Highway, Newport, Ml 48166 Expiration Date N/A .Address - . I II 4.; Identification N5-0246 &'0307 Residual Heat Removal System Division 2 of System :

5. (a) Applicable Construction Code ASME HI,

'Class2 1 19 71 Edition S72 Addenda NWA Code Case (b) Applicable Edition/Addenda of Section Y Ublized for Repairs or - - Replacements 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 Idenfification' BIt Replaced,. Code No. or Replacerent Stanped

-__ (yes El 10OF025B Crosby _-_:_ _._-_._ _-: _ :- or No) N57381-00-002 NWA V22-2041 1978 Replacement Y Description

7. of Work Install replacement disc inrelief vahv due to kientified pitting of disc seatina surface.

8. Tests Conducted: Hydrostatic [ Pineumatic[I : - Nominal Operating Pressure [X I Other[XJ Pressure - psi 0: TestTemp.

Note: Supplemental sheets inform of lists, sketches, or drawings may be used provided (1)size is81/2 in.X I in., (2)Informa-tion initems I through 6 on this report IsIncluded on each sheet, and (3)each sheet isnumbered and the number of sheets is recorded at the lop of this form. (10i4) i. Form NIS-2 (Back)

9. Remarks: Replacement Disc assembly procuffed per239415-01, Serial No. N90574-42.0017 (Report Attached). Valve returned to stock as atested spare for future replacement. *Valve refurbishment completed per PO# 371508 0 NWS.

Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made Inthe report are coned and this Reolacement conforms to the rules of theASME Code, Section . Type Code Symbol Stmp Orional Code data renort N5-0246 and -307 to be suoolemented by Owners Section Xl Program 02-017 Certificate olAuthorizationNo. NIA r . :Expiration Date WA Siged R.M. Harnbleton Lead ISI Engineer Daat SoL Z .2 0 Owner or Ownehs Desoes, Tite CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding avalid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Pwrvince of Michb an and employed by HSBJ crqof One'State Street. Hartford. CT 06102 have inspected the components described this Ownars Report during the pedod 09 -cO >7-2 8- and sn state that b the best of my knowledge and belef, the Owner has performed examinations and taken corre measures described inthis 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 imnplied, concerring the examinations and correcive measures described Inthis Owner's Report Furthermore, neither the Inspector nor hs employer shall be liable inany manner for any personal Injury or property damage or aloss of any kind arising from or connected with this inspection. Cornmissions t ° Inspector's Signature National Board, State, Province, and Endorsements Date2 (10194) For complete work package, reference PO #371508 -: S - -2 eit I 1 . 'a* Zl7-1.; 1Sqdzop2

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2. X Deerol 0t Edi:son Compa~n* .Aeitglt Mrl w-

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Il::: (la)~~~~~~~~~~~~~~~~~~ ox F. I L '~ i ~ ~ _WSZ - S: Ps z p. -y *-t. 1'. .v. frt;est :esw*rA tb: Jjj: .cEDERt rzt 1-2 Fo~j--i* -F2 (back)  ! I-,ft s.:i AL. r. N9057C-42-003L.7 . x90574-A2-003 -11, I.A. CERZIFCAIION OF DESIMI1 II ~~~~ ~~Rot! J4Tht p.?. MI its. so. 28412 cp~c-CU= . t-1C'.Mi d by. Dea~~~a by :pa4 ~~~ .. ,. #.L a~~~tate Reg r I T 7~~~~~~I7'.~~~~- . . I - an aOMLm-iq, W. caztigy that the srat aemts made La tUSta :Patt 'are tOrrted aad hthiChae DscIer ?.ehea catto sca c amo the JleCot cmC M. M? cogt1lieate of Autha:imatiaa no. 9/30/92 CERIEIFZA+/- H P TIqsPECTICOr .4.

1. the Ro hoiLtur a va~d co=,SaL= of Roller amd ft asuZ0 VagnaL.

3ztedb*=tai.R ZThiCz-;ac-,!h~d the Stat. cv ptav~aca ofHs~b2GZ a a~~d# *See Below *' * .. ar . MlA I&-zv61tpetad tbase 1tmm'~dsittlCZEd 13athi-S data .:ePartci -- l '"' s state that. Z* -I* bext at.M7. knxwiefte. am&beif..ti1~iaCbs bafh~aa a.ptaa appmteamato is accordttcs, with the AMC Czda. Soejz !Eac pod listed.-Mis bed-htkea aaf

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02-01 9 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl Detroit Edison Company Date January 7, 2003

1. Owner Name Sheet 1 1o

.6400 North Dixie Highway, Newport Ml 48166 Address Fermi 2 Nuclear Power Plant Unit - 2

2. Plant Name 6400 North Dixe Highway, Newport MI 48166 Deco Maintenance Address~ Repalr Organtm n P.D. No., Job No., et.

Address , Detroit Edison Company  : Type Code Symbol IUA

3. Work Performed by

. Stamp Name Aiho izaion No. Expiration Date NIA 6400 North Dixie Highway, Newport Ml 48166 - Address I - - II  : -I -.

4. Identification RCIC Turbine Exhaust Dne Pipe Support E51-3174G07 of System

5. (a) Applicable Construction Code AJSC 6and i WA 19 NA Edition - Addenda NWA Code Case Edition (b) Applicable EditioniAddenda of Section Xt Ublized for Repairs or 1992-92 Addenda Replacements

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

. or No) - NIA N-A WA 1984 Replaced Y E51-3174-G07 Wismer _______________ -___ Becker Description

7. of Work Modify existing oiPe suoort structural steel to allow installation of a new motor on valve E5150Fi001 oer

8. Tests Conducted: Hydrostatc I j Pneumaticf - Nominal Operating Pressure [ -

Other [X] Pressure - psi Test Temp. - OF in. X 1i In., (2)Informa-Note: Supplemental sheets inform of lists, sketches, or drawings may be used provided (1)size is 8 i/2 on each sheet, and (3)each sheet Is numbered and the number of sheets Is tion Intems 1 through 6 on this report isIncluded recorded atthe top of this form. (10/94) Form NIS-2 (Back)

9. Remarks New baseline Inspection performed. New 4x4 tube steel, Ht # 966772, procurred per PO# 318436, and 'Aplate, HOI 1704470, procurred per PO t335189.

Applcable Manufacturer's Data Reports to be attached CERTIFiCATE OF COMPUANCE We certify that the statements made inthe report are correct and tis Ieacemel conforms to therulesofthOASME Code, Section XL Type Code Symbol Stamp Original Construction recore for E51-3174-G07 to be suoclemented by Owners Section Xl Program #02-019 Certificate of Authorization No. NWA Expiration Date NWA Signed R.M. Hambleton Lead ISI Engineer Date .20 03 ' ' Owner or Owner's Designee. TMe CERTIFICATE OF INSERVICE INSPECTION I,the undersigned, holding avaid commission issued by the National Board of Boiler and Pressure Vessel Irspectors and the State or Province of Michiosn and employed by ItSLCTod One State Street. Hartford. CT 06102 have inspected the components described inthis Owner's Report during the periodL fS- ',to-Q07-°Z34.-, and state that to the best of my knowiedge and belief, the Owner has performed examinations and taken corrective measures described Inthis 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, conceming the examinations and corrective measures described Inthis Owner's Report Furthermore, neither the Inspector nor his employer shal be liable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this inspection. Commissions -1/5-cc^4z IG O Inspector's Signature National Board, State, Province, and Endorsements Date -xep 720O (10/94) For complete work package, see Work Request 000Z023784 03-G001 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS m As Required by the Provisions of the ASME Code Section )a

1. Owner Detroit Edison Company -- - Date May 23, 2003

- - Name 6400 North Dixie Highway, Newport MI 48166 Sheet 1of 2 -, - Address

2. Plant Fermi 2 Nuclear Power Plant - Unit 2

- Name 6400 North Dixie Highway, Newport Ml 48166 Deco Maintenance Address Repar Orgnization P.O. No, Job No, eair

3. Work Perforned by Detroit Edison Company - - Type Code Symbol N--/A  :

Stamp Name DAuthorization No. WA 6400 North Dixie Highway, Newport, Ml 48166 Expiration Date NWA - I Address

4. Identification (N54120-N5-11 Control Rod Drive System 0 of System

5. (a). Applicable Construction Code ASME Ill,- - 7 ____Aft Class 1 19 1_ Edition 71 Addenda WNA Code Case (b) Applicable Edition/Addenda of Section Xa Ulized for Repairs or Replacements 1992-92 Addenda

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

___________ ____________ ~~~~~~~~~~~ NO) CRD Housing Bolting RCI N54J120-N5-11 N/A See Matrix 1975 Replacement N Control Rod Drive General See Matrix WNA See Matrix 1975 Replacement Y Mechanisms Electric . _ _. Description

7. of Work Replaced Control Rod Drve Mechanisms at various locations and installed replacement Cap Screws on each mechanism to facilitate drive installation. Al removed boltino was inspected and stored for future installation.

8. Tests Conducted: Hydrostatic [ ] _Pneumatic [lI Nominal Operating Pressure [ X l Other[XI Pressure psi; TestTemp.  : °F Note: Supplemental sheets inform of lists, sketches or drawings may be used provided (1)size is8 1/2 in.X II in., (2)informa-tion in tems 1 through6 onthis repor is includedon each'sheet, and (3)each sheet isnumbered andthe numberof sheets Is recordedatthetoppfthisform.  : 2 -

(1094) Form NIS-2 (Back)

9. Replacement bolfinnCap Screws procured per PO # 363782, 362633 and 363784.

Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPUANCE We certifythat the statements made inthe report are correct andthis Replacement conforms to the rules of theASME Code, Section Xl. Type Code Symbol Stamp Original Code data reoort N5-J120-N5-1 to be supplemented by Owners Section Xl Program 03-001 Certificate of Authorlzation No. N \ Expiration Date NWA Signed R.M. Hambleton Lead ISI Engineer Date VA ta .200 Owner orOwner's Designee, Tile CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by fts CTof One State Street. Hartford. CT 06102 have inspected the components described inthis Ownees Report during the period ds 10.c2 s . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described Inthis 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 inthis Owner's Report Furthermore, neither the Inspector nor his employer shal be liable inany manner for any personal Injury or property damage or a loss of any Kind arising from or connected with this inspection. Commission ,V s 5.9 ecp 2VAIf L o inspectoes Signature National Board, State, Province, and Endorsements Date 200 (1094) For complete work packages, see Work Requests listed on attached matrix. NIS-2 03-001 Sheet 2 of 2 Nis-2 Attsachment for Section XI ProEram No. 03-001- RF09 CRDM Exchange

• Replacement bolting (Cap Screws) were replaced on each drive mechanism installed (8 per drive). Replacement Cap Screws were procurred per PO # 363782,HT Code 14761, PO # 362633, HT Code 84587/F280, and PO #

36378, HT Code 8995873. ASME m - Class 1, SA193 Grade B7, 1"-8UNC-2A x 5-112"

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

CRDM Serial No. New Serial Exchange WR NewCap Screws . _________ -____No. _ PO# - Ht #-Qty) 14-55 6397 6086 00OZ020645 362633- ._ ._._._.._:_-:_: 845871F280 06-27 3410 4512 00OZ021058 362633- . -.:  : -______ 84587AF280 10-27 4189 4006  : OOZ021060 362633- _._.._. -_____  : 84587/F280 14-51 4584 6475 00OZ021062 -362633- . -  : .____-_._: 84587fF280 30-39 4488 6387 000Z021048 362633- .____________ . .84587/F280 14-11 -4459 6507 00OZ021064 363784-8995873(6) 363782- 14761(1) .362633- -___ ._ 84587/F280(1) 26-11 4523 4408 ODOZ021066 363782-14761 22-15 3608 6180 00OZ021068 363782-14761 06-31 -6541 5545 00OZ021070 362633- ___ _._._._._84587/F280 30-31 3326 3152 00OZ021050 362633- .__.__.__.__.__. _ 84587/F280 58-19 3623 5752 00OZ021072 363782-14761 54-27 4286 4406 00OZO21074 363782- 14761 30-59 -5655 3339 00OZ021089 362633-84587/F280 . 42-55 4436 6172 OOOZ021052 362633- _____________- 84587/F280 34-47 4315 6125 -OOZ021091 362633- .. __._.__:_-:__. 84587/F280 38-47 4391 5950 00OZ021093 362633- -___________ _ X 84587/F280 42-35 3521 3180 00OZ021095 363782-14761 58-23 4330 6412 OOZ021097 363782-14761 38-07 -000 4312 4590 00OZ021054 363782-14761(6) 362633-:

_________ : __ .________. 84587/F280(2) 50-19 3999 5451 00OZ021099 363782-14761 54-43 4309 5423 00OZ021101 363782-14761 58-35 4340 4524 00OZ021103 363782-14761 34-15 7019 5770 00OZ021056 363782-14761.03-002 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl

1. Owner Detroit Edison Company Date Apnl 15,2003 Name

- 6400 North Dixie Highway, Newport Ml 48166 Sheet 1of 3 Address

2. Plant Fermi 2 Nuclear Power Plant Unit ' 2 Name 6400 North Dixie Highway, Newport MI 48166

- Deco Maintenance -Address Repak Oganmation P.O. No., Job No., etc.

3. Work Performed by Detroit Edison Company ~ -' I Type Code Symbol N/A Stamp .

I Name I . Authorization No. NWA 6400 North Dixie Highway, Newport, Ml 48166 : Expiration Date NWA Addre

4. Identification Fueal PnnI Cnnfinn andr O~pan-tn In RI4R Rptiim L[nA ,

of System

5. (a) Applicable Construction Code ASME III, 92 92 (Valve)

Class 3 19 71 Edition '71 Addenda NWA 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 N o) G4100F231 Wksmer & D133T-1-1 N/A V30-1237 2001 Replacement Y ____ ____ ____ Becker __ _ _ _ _ _ ___ _ _ _ _ __ _ _ _ _ Description

7. of Work Modify existing Diping system by installing a new throttle valve par EDP - 30467

8. Tests Conducted: Hydrostatic [ x I Pneumatic [I Nominal Operating Pressure ( I Other I1 Pressure 24831570 psi : I. TestTemp. - 83.1 OF Note: Supplemental sheets inform of'lists, sketches,. or drawings may be used provided (1)size Is8 1/2 In.X 11 in., (2)informa-tion initems I through 6 on this report Isincfuded on each sheet and (3)each sheet Isnumbered and the number of sheets is recorded at the top of this form.

(10/94) iI, Form NIS-2 (Back)

9. Remarks: Replacement valve procurred per PO 351078 and was supplied complete with Er x 6' Schedule 40 welded reducers on both

• pirts.

Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPUANCE We certify that the statements made inthe report are correct and this Re.lacement -iconfrms to the rules of theASME Code, Section Xl Type Code Symbol Stamp Orldnal Code data reoort to be suOplemented by Owners Section Xl Program 03-002 Certificate of Authorization No. NWA Expiration Date NWA Signed R.M. Hambleton Lead ISI Enaineer Owner or Owners Desgnee, Mte G oAk Date G i _ _2 _ CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Miigan and employed by HB CT od One State Street Hartford. CT 06102 have inspected the components described inthis Owner's Report during the period! s-O.toj2e S-Zoo,5 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken comective measures described inthis 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 inthis Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Commissions AAK' 9 4" AWAI'W4' Af -r 0 Inspectors Signature National Board, State, Province, and Endorsements Date ,4°.z / /-5: 20_ _ (1W4) For complete work package, see Work Request 000Z002161 f OR VALVESftflatM. FORM NPV-1 CERTIFICATE HOLDERS' DATA REPORT FOR NUCLEAR PUMPS 0 -. As Required by the Provisions of the ASME Code. Section III. Division 1

• - : - . ; - -.L - --. - Xpg. 1 of 2 --

Flowserve Corporation PA 17701 1.. Manufactured and certified by 701 First Street, Williamsport, (name and address of N Cerdtficate Holderl A

2. Manufactured for Detroit Edison P.O. Box 1659. Detroit, MI -48231

-name and addrvs of Furchaser-

3. Location of Installation Enrico Fermi- Unit 2, 6400 Dixie Highway, Newport, KI 48l6F > .0 (name and address).

Globe Drawing -6231 ev. B C

4. ModeSNoSeries No. orType MoeN .- , _______ . ..94-163 Rev. B ,C Division 1: 1992 1992 3 N62-4

5. ASME Code. Section 111, (addenda datel (class) MCode Case no.)

leditionl

6. Pump or valve -V 1 v0 Nominal Inlet siz. An Outlet size SA696-.C Disk A582-416T Boing Studs: SA193-B7

7. Material: Body SA216-WCB Bonnet

- uts: SA194-2E (b) Ic) Idl (e) Cert. Nat'l Body ) J Bonnet Disk Board Serial Serial Serial Holder s No. No. No. Serial No. D133T-1-1 N/A :o1 - Trace Code:B534 L t.ID: VMR (1) size is EK x 11. 121 information inhitems 1 through 4

• Supplemental information in form of lists., sketches. or drawings may be used provided of sheets Is recorded at the top of this form.

on this Data Report is included on each sheet 13) each sheet is numbered and the number ASME 22 Law Drive Box 2300 Firfiekt. NJ 07007-Z300 REPRINT 613 t12188) This form tE000371 may be obtained Irom the Order Dept FORM NPV-1 (Back- Pg. 2 of2 1 .

• Certificate Holder's Serial No. D133T-I-Žl1`r2

8. Design conditions 707 Psi 150 . F or valve pressure class 300 Ipressurel Itemperaturel .

9. Cold working pressure 740 pi at 10 0.

Il0. Hydrostatic test 1125 psi. Disk differential test pressure 815 . I 1. Remarks: Material: Bonnet Retainer SA516-70 (Et. ID: VLM) - ~* . F CERTIFICATlON OF DE:SIGN **-4f;. Design Specification certified by Of_ Lawrence D. Burr P.E. State MI Reg.no. 33999 . X/A I Design Report certified by - P.R.State Reg. no. CERTIFICATE OF COMPLUANCE I-. ,. _' 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 Cerdfl c a of Authorization No N1712 4/1S/01 Date .2111 LName Flowserve Corporatior IN 14M.,A .I Signed ~ a-w'w wsvJ .9 CERTIFICATE OF INSPECTION I. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State EmmaCI of Viannr' c n ia and employed byea 2 I rrti 41ni Trig en of Amcitin Maq__ have inspected the pump. or valve, described in this Data Aeport on r 3A Iow;2:Q czar ,a-4 = 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 1I1.Division 1. By signing ths 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 an for any personal Injury or proper aor loss of any kind arising from or connected with this inspection. ( I! Dat43>0/ Sig - X j j Commissions  ! 9nnylThn4 2932 cAuth c INat'L 3d. (ind. endorsements) and uats or prov. and no.1 =-.

11) For manually operated valves only.

to' - 0 FORM NPP-1 CERTIFICATE EPP-1 HOLDERS' DATA RPORT FOR FABRICATED NUCLEAR PIPING SUBASSEMBLIES- . As Required by the Provisions of the ASME Code.Section III, Division-1 g. 1 of .. L

1. Fabricatedand ertified Flowserve Corporation, 701 First St., Williamsport, PA 17707

-1name and address of NFT Cenificate Holderl

2. Fbritedfor Detroit Edison, P.O. Box 1659, Detroit, MI .48231 , ". -: -

(name and addressl

3. Location ofinstallation Enrico Fermi Unit 2,,

6400 Dixie Highway, = Newport, MI 48166 Aname and address ofPurvhased A Tvn. .D133T-1-lA N/A '94-16231. R/B .N/A 2001 7'TV. IGar) Holdera ariano.1 ICRNI -drawing no.1 (Natl. ad. no.) (year buil

5. ASME Code,Section III, Division 1: 1992 1992 3 N/A editloni - - bddende dm6l fblass (Code Case no.)

6. Shop hydrostatic test 1125 ---- I ~~V31at Ambient *F Of performed) l-e-rintin nf .inlnn 8Rx6' Schedule 40 Concentric Reducers 7.

Material: SA234-I9PB (Et. #52435) S. Certificate Holders' Data Reports properly ide. -/d5 snd signed by commnissioned Inspectors have been fumnished for the following items of this feot'Valve-SIN: D133T-1-1 (60-300 dClobe Control Valve) -~ 9 Remarh 'Welded 81x6" Sch. 40 Conc. Reducers to hoth Valve ports ..  :

9. Remrks CERTIFICATE OF SHOP COM PUANCE We certify that the statements made In this report are correct'and that the fabricati on of the described piping subassembly conforms to the rules for construction cf the ASME Code. Section lIl. Division 1.

NPT Certificate of Authorization No. N1713 Expires 4/5/ )1 C Date 1 5f 4 Name Flowserve Corpbration INPT Cerificate Hoideri Signed - iutorxeq ' represeftativel %' I 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 Pennsylvania andemployedby Commercial Union Insurance CO. _ Bf Eoston, Mass. :have inspected the -piping subassembly described in this Data Report onii ! I2fInd state that to the best of my knowledge and belief, the Certificate Holder has fabricated this piping subassembly in accordance with the ASME Code,Section II, Division 1. By signing this certificate neither the inspector nor hs employer makes any warranty. expressed or implied, concerning the piping subassembly 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 conC ad with this inspection , , -/ Date At -. Signe ' Commissions Pennsylvania 2392 Chafles Yo? - Net5. find. I2a'edltoi endorsement) and ate r prov. 5nC no.l

• Supplemental information In form of lists, kecher drawin may be used provided (11 size Is 8X x 11, 12 information in items 1 through 4 on this Dats Report is Included on each sheet. 131each sheet is numberfd and th mber of sheets Isrecorded at the top of this form.

(121 882 This form IE00062) may be obtained from the Order Dept.. ASME. 22 Law Drive. Box 2300 Fairfield NJ 07007-2300. 67 ' '  : . ~t0 , ,. ,0 /,,, . , . X,.0 , < ,0 , ,. Xs 20 , , ; f .' 6 . 5, .,E..;. , . ., .= 03-003 FORM NIS-2 OWNERS REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section Xl-

1. Owner Detroit Edison Company Date 2-15-2003 Name 6400 North Dixie Highway, Newport MI 48166 Sheet 0 -' ' 1 of I lo E I:.:.

Address

2. Plant Fermi 2 Nuclear Power Plant Unit .. . .~~

-Name 6400 North Dixe Highway, Newport Ml 48166 -Deco Maintenance Address Repair Orgaaton P.O. No.,Job No, etr:

3. Work Performed by Type Code Sy 'mbol Detroit Edison Company  : Stamp, -NA.

Name - Authorization INo.;: N/A -Expiration Date - 6400 North Dbixe Highway, Newport, Ml 48166 NIA Address I -4. Identification of System Hanger Support El1-3185-G51- Dinson 1RHRSW

5. (a) Applicable Construction Code el AISC 19 7th Edition NIA Add(mnda1

• N/A Code Case (b) Applicable EditiornAddenda of Section Xi Utilized for Repairs or 1992- W '92 Replacements - 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 Replacemen[ Stamped (Yes _____________________ _____________ ~~~~~~~~~~~ No) El1-3185-G51 Wismar & 810087 N/A El 185GO51 81 Replacement No 'Becker -_______ Description

7. of Work Replaced lealing HYdraurc Snubber with atested spare.

8. Tests Conducted: Hydrostatic [I Pneumatic [I Nominal Operating Pressure I 1 Other[X] Pressure psI psi_' -TestTemp. F Note: Supplemental sheets inform of lists, sketches, or drawings may be used provided (1)size is81/2 In.X 11 In., (2)informa-

-ion initems I through 6 on this report Isincluded on each sheet, and (3)each sheet is numbered and the number of sheets is recorded at the top of this form. --L I- S: . " OM(10/94) I '- Form NIS-2 (Back)

9. Remarks Replaced snubber with a tested spare that was refurbished per WR# 000Z984276.

Applicable Mariufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this relacement conforms to the rules of theASME Code,Section XI. Type Code Symbol Stamp Orliinal Construction Records for El1-3185-G51 will be suoolemented by OwnersSection XI Proaram Plan 03-003 and Work reauest 000z023688. Certificate of Authorization No. I A Expiration Date WA Signed R.M. Harnbleton Lead 1SI Engineer -S Dat  % M OP X VS .20 Owner or Owner's Designee, Tidl . CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the Naflonal Board of Boiler and Pressure Vessel Inspectors and the State or-Province of MNichgan and employid by HSB CTofOne State Steet. Hartford. CT 06102 have inspected the components described inthis Owner's Report during the peodS to and state that to the best o my knowledge and belief, the Owner has performed examinations aofd taken feredve mrsures described inthis 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 Inthis Owne's Report. Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or a loss of any kind arising from orconnected with this Inspection. misions AgZZ? / O Inspector's Signature National Board, State, Province, and Endorsements Date1 (10/9)03-011 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section X)

1. Owner Detroit Edison Company Date -May21, 2003 Name 6400 North DWeix Highway, Newport Ml 48166 Sheet - Of 1 Address

2. Plant Fermi 2 Nuclear Power Plant Unit - .:

Name 6400 North Dwxe Highway, Newport Ml 48166 Deco Maintenance Address-  : - . I . Repair Organkabn PD. No, Job No., etc. -3. Work Performed by Type Code Symbol - Detroit Edison Company Stamp _  : I- .N/A I i Name Authorization No. NWA 6400 North Dide Highway, Newport, Ml 48166 Expiration Date

NA Address - - -

4. Identification N5-0522 Primary Contalinant Pneumatic Supply System I of System NS-008 Nitrogen Inerting System - - - -

5. (a) Applicable Construction Code - ASME Ill, -- - I-. Winter I Class 2 19 71 Edition 1971 Addenda, NWA Code Case (b) Applicable Erion/Addenda of Sedion Xl UiTized for Repairs or Replacements 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 I - No Board Identification Built Replaced, Code No. or Replacement Stamped

• (Yes

_ _ _ _ _ _ _ _ _ __ _ __ _ _ __ __ _ __ __ _ __ ~orNO) T230OF400D GPE Controls 7206-0327/4 NVA V21-2004 1974 Replacement _ Description 7., of Work Install Replacement Flange Bolt I . I II II

8. Tests Conducted: Hydrostatic fi Pneumatic [1 Nominal Operating Pressure [I Other[XX Pressure - _- psi TestTerrip. F Note: Supplemental sheets Inform of lists, sketches, or drawings may be used provided (1)size is 8 1/2 in.X 11 In., (2)informa-tion initems 1 through 6 on this report is Included on each sheet, and (3)each sheet isnumbered and the number of sheets is recordedatthetopofthisform. -

(10194) Form NIS-2 (Back)

9. Remarks I Replacement Bolt procured per PO# 361906, %'-lO UNC-2A x 2-112", SA 193 Grade B7. HT # B130 Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this Replacement conforms to the rules of theASME Code, Section Xi.

Type Code Symbol Stamp Oriolnal Code Data resort N5-522 and N5-608 to be supplemented by OwnersSection XI Programr 03-011 Certificate of Authorization No. - 4I l Expiration Date WA Signed R.M.IHambleton LeadISI Enineer MA' Z 2 Owner or Owner's Designee, Te CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michian and employed by &SLC of One State Street Hartford. CT 06102 haveinspected the components described inthis Owner's Report during the perod- 8-°3 to .3- cO and statethat to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis Owner's Report in accordance with the requirements d 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 descnbed inthis Owner's Report. Furthermore, neither the Inspector nor his employer shaD be fable inany manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. !--21A CommissionsA rn~ Ae/ 886 . ,V of A Inspector's Signature National Board, State, Province, and Endorsements Date 7e _ 20°3 (10194) For complete work package, see Work Request Y664030100

03-012 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS 03-02 As Required by the Provisions of the ASME Code Section --

1. Owner Detroit Edison Company Date - - IMay 21,2003 Name 6400 North DWe Highway, Newport Ml 48166 Sheet 1of I Address

2. Plant Ferni 2 Nuclear Power Plant Unit .. 2 Name 6400 North Dixie Highway, Newport Ml 48166

-1 I Deco Maintenance Address ..- - 1 I RepaOrganizaton P.O. No, Job No., et.

3. Work Performned by - Type Code Symbol

- Detroit Edison Company Stamp Name Authorization No. . - . I .- - I 6400 North Dbxe Highway, Newport, Ml 48166  : Expiration Date .WA ---N/A-Address

4. Identification N5-0214 Feedwater Loop B,RWCU Return to Vessel 0 I

- of System

5. (a) Applicable Construction Code ASME'ill, Winter

- -I . Class1 19 71 EdItion 1971 Addenda,' NA W Code Case (b) Applicable Edition/Addenda of Section Xi UiTzed for Repairs or Replacements 1992-92 Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Manulacturer Serial -Natonal Other Year Repaired, ASME Component Manufacturer No Board. Identification Built Replaced, .Code 0No. or Replacement Stamped (Yes

______________ _________ ~~~~~~~~~~~~ G330OF120 Anchor Darling E 3062-2-1 NWA V8-4615 1983 Replacement Y Description

7. of Work Installed Replacement Bolting material and installed replacemant bonnet retainer/ cover plate.

8. Tests Conducted: Hydrostatc [ 1 Pneumatic [I Nominal Operating Pressure [XI - -

Other( I Pressure -  : psi PSI Test Temp. F Note: Supplemental sheets Inform of lsts, sketches, or drawings may be used provided (1)size is81 In.X 11 In., (2)inforna-tion inItems 1through 6on this report isIncluded on each sheet, and (3)each sheet isnumbered and the number of sheets Is recorded atthe top of this form. (10/94) Form NIS-2 (Back)

9. Remarks Replacement Bolting material procured per the following Purchase orders:

(4) Y2" -13 UNC x 2-114", SA 193 Gr. B7, PO# 886964 (4) Y'"-13 UNC Nuts, SA-194 Gr. 2H. PO# 890771, (1) Bonnet Cover/Retainer Plate, A516 Gr. 70, PO# 357114 Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this Redacement conforms to the rules of theASME Code, Section Xi. Type Code Symbol Stamp Original Code Data report N5-0214 to be supolemented by Owners Section Xl Proeram #03-012 and 03-028 Certificate of Authorization No. NWA iExpiration Date N/A SiWed R.M.Hambleton LeadlSIEngineer PAAA tt 03Dae .20Qs Owner or Owners Designee, Tiat CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding avalid commission Issued by the National Board of Boier 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 inthisowner's Reportdudng the pedodS/f j3to.-E/Lo s . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis 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, conceming the examinations and corrective measures described Inthis Owner's ReporL Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or a loss of any ldnd arising from or connected with this Inspection. A-a - Commissions AV1< 4 j'> AeZzV,,V-Inspector's Signature National Board, State, Province, and Endorsements Date It/ Y 3o 20 ° (10/94) For complete work package, see Work Requests P521030100 and 00OZ031881 03-013 03-014 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - . . As Required by the Provisions of the ASME Code Section Xl 03-023 1.- Owner Detroit Edison Company - . Date May 14,2003 Name -, .. 6400 North Dixe Highway, Newport Ml 48166 -  : -* Sheet 1Of 1 -- -- - ----- :- ~~ Address - Fermi 2 Nuclear Power Plant Unit 2

2. Plant I Name -

6400 North Dixie Highway, Newport Ml 48166 Deco Maintenance I Repai Organrkation P.O. No., Job No., er. Address

3. Work Performed by Detrolt Edison Company Type Code Symbold N/A tStamp Name .I Authorization No. NWA

~ .::

Expiration Date N/A 6400 North Dixie Highway, Newport, Ml 48166 Address . - . . I . - I  : I

4. Identification T&B N5-3 RHR Service Water (RHRSW1 PumDs EI151COOlA and E11510001C) of System:

5. (a) Applicable Construction Code ASME III, .92 92 (Valve) 19 71 Edition 71 - -Addenda WA Code Case Class 3 (b) Applicable Edition/Addenda of Section Xl)Uiifzed for Repairs or -

Replacements 1992-92 Addenda

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

' Name of ManiufactureSerial National ' Other Year Repaired, ASME Name of Manufacturer No Board Identification Buflt Replaced, Code Component 0- 00 0 -= ' -- ; - No. or Replacement Stamped (Yes ~~~~~~~or.No) N301213-1 NWA WNA 1975 Replacement Y E1151CO01A - Goulds Pumps N301213-13 N/A N/A 1975 Replacement Y E1151C001C Goulds Pumps - Description

7. of Work Installed Replacement Bolting.

8. Tests Conducted: Hydrostatic [I Pneumatic [jI - Nominal Operating Pressure [ X ] '

Other ]J Pressure -_ :' Ipsi Test Temp.- OF in., (2)informa-Note: Supplemental sheets Inform of lIsts, sketches, or drawings may be used provided (1)size is 8 112 in.X 11 Isincluded on each sheet, and (3) each sheet Isnumbered and the number of sheets is tion Initems 1 through 6 on this report recorded at the top of this form. -(10194) Form NIS-2 (Back)

9. Remarks: Quantities identified for the Replacement Fasteners procured on the following Purchase Orders were replaced inboth E1151C001A and E1 51C001C.

60 718"- 9 X 7(P.O. 3885451HT. CodaeF921) /120 Nuts 7/8r-9 (P.O. 851Q61HT. Cod3 MTX forE1151C001C) and 120Nuts (P.O. 388545 HT. Code OJS for El 151 C0OIA) 1B -10X2-W %(P.O.388546/HT.CodeF925) 32 314'-10X 1-7/8 (P.O.388546/HTCodeF925) 12 7/8 - 9 X 5 (P.O. 388545 / HT. Code F922) and 12 Nuts 7/8- 9 (P.O. 388548! HT. Code F939) These additional Fasteners were installed on El 151C001C and not on El 151C001A. Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this Repacement conforms to the nules of the ASME Code, Section Xi. Type Code Symbol Stamp Ondrnal Code data rewort T&B N5-3 to be supplemented by Owners Section Xl Prooram 03-023 and BolWno Replacement Proarams 03.013 (E1151C001C) and03014 E1151CO0IA. Certificate of Authorization No. Expiion Date A Signed R.M. Hambleton Lead ISI Enaineer VV t A*( .'( .20 _ 0 _ Owner or Owners Designee, Tibt CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a vald 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 descnbed Inthis Owner's Report during the period 9- V-03to5-20-2. and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis Owner's Report In accordance with the requirements of the ASME Code, Section Xl. By signing this certificate neither the Inspector nor his ermployer makes any warranty, expressed or implied, concernig the examinations and corrective measures described inthis Owner's Report. Furthermore, neither the Inspector nor his employer shal be liable inany manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 4/-~2).~A------.--. Commissionslf9Aa AXvvo Inspecto's Signature National Board, State, Province, and Endorsements Date 6 0 2aO. (10194) For complete work package, see Work Request 000Z031277, 000Z031288, 000Z031597, and 000Z031478. 03-01 6 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS - As Required by the Provisions of the ASME Code Section )a 1.:- Owner Detroit Edison Company Date I.I .~ May 14, 2003 Name I OfI -. I 6400 North Dxie Highway, Newport Ml 481B6- Sheet

-I 1 .o f1 1 -:2 Address Unit - n2.-  :

2. Plant Fermi 2 Nuclear Power Plant Name..

-6400 North Dixia Highway, Newport Ml 48165 -: f ~Deco Maintenance Address I :- - I - Repair Organization P.O. No., Job No., et.

3. Work Performed by : I Detroit Edison Company TypI aCode Symbol - . . N/A Stamp

Name - - Authorization No. N/A 6400 North Dixie Highway, Newport, Ml 48166 , - -- .~

--: .: Expiration Date  : WN/A - : Address:-  : ~ .

4. Identification N-5 T&B N5-20 (Emergency Diesel Generator (EDG) Number 13 and 14 Service Water Pumps)

. of System 92 (Valve)

5. (a) Applicable Construction Code ASME III. 92 I 92 -- (V/ahe)

Class 3 - 19 71 Edition '71;: Addenda N/A  ; Code Case (b) Applicable EditionlAddenda of Section XAUtilized for Repairs or Replacements 1992-92 Addenda S. Identification of Components Repaired or Replaced and Replacement Components Nameof Name of ManiuacturerSerial National Other Yea Repaired, ASME Manufacturer No Board. Identification Built Replaced, Code Component No. or Replacement Stamped (Yes _______ ._ . -_ _  : - :ora  :: -:. No) R3001C007 Goulds Pumps TCN N0007-3 NWA N/A 1977 Replacement Y Goulds Pumps TCN N00074 NWA NIA 1977 Replacement Y R3001C008 Description

7. of Work Installed Redlacement Boltina. -

S. Tests Conducted: Hydrostatic [1 - PneumaticI I - Nominal Operating Pressure [ X ] ' : Other ( I Pressure I - psi- Test Temp. = F Note: Supplemnentalsheets inform of lists, sketches, or drawings may be used provided (1)size is B 112 in.X 11 in., (2)informna-tion in items 1through 6 on this report is included on each sheet, and (3)each sheet isnumbered and the number of sheets is recorded at the top of this form. (10194) A.h.ih.i Form NIS-2 (Back)

9. Remarks: Quantifies identified for the Replacement Fasteners procured on the following Purchase Orders were replaced inboth R3001 C007 and R3001C0008.

40 W - f0 X 2- % (P.O. 3843011 HT. Code F984) 8 11 XZ (P.O. 384301 HT. Code F985) 16 5 - 11 X1-3/4' (P.O. 84301 HT Code F986) Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made Inthe report are correct and thise to the rules of the ASME Code, Section XL Type Code Symbol Stamp Original Code data reMrt T&B NS-20 to be suDplemented by OwnersSection XI Prograrn 03-016. Certificate of Authorization No. N/A Expiration Date WA Signed R.M. Hambleton LeadlSIEngineer k 1 JL .Date.i .. 03. Owner or Owners Desiee%Tide CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by Ho CTof One State Street Hartford. CT 06102 have inspected the components described inthis Owner's Report during the pe odOsf/-'3 to Sic5- OA and state that to the best of my knowledge and belief, the Owner has perlormed examinations and taken corrective measures described inthis Ownets Report in accordance with the requirements of the ASME Code, Section XL. ByB-signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described inthis Owner's Reporn Furthermore, neither the Inspector nor his employer shal be liable inany manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. 4A ~ z ~ commissions/1& 4G1o 'j Inspectors Signature National Board, State, Province, and Endorsements Date -° da (10/94) For complete work package, see Work Request 000Z031322 and 000Z031323.

03-01 7 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section -.

1. Owner Detroit Edison Company -Date May 14,2003 Name 6400 North Dbxe Highway, Newport Ml 48166 Sheet fof t Address

2. Ptant Fermi 2 Nuclear Power Plant Unit 2 North Name 6400 North Dixie Highway, Newport Ml 48166

' Deco Maintenance Address I Repai rOrganization P.O. No., Job No., etc. Detroit Edison Company' Type Code Symbol WNIA & Work Performed by Stamp Name Authorization No. N/WA Expiraflon Date ' .NIA I 6400 North Dude Highway, Newportl Ml 48166 Address  : - - , . - . I .:. .

4. Identification T&B N-5-21 Emergency Eduioment Service Water (EESW) Pump P4500C002B) of System

5. (a) Applicable Construction Code ASME III, 92 92 - (Valve) 19 71 Edition 71 - Addenda tVA Code Case Class 3 (b) Applicable Edib'on/Addenda of Section Xl tiled for Repairs or Replacernents 1992-92 Addenda

6. Idenb'ficaffon o Componens Repaired or Replaced and Replacement Components-Manufacturer Sedl National Other Year Repaired, ASME Name of Name of No Board Identification Built Replaced, Code Component Manufacturer

. . . . . :i . - No.: - or Replacement Stamped (Yes -_ _-_._._._._._-_._:_. ._ _._. _. ._._.:_._._._. or No) TCN N0006-2 NWA N/A 1977 Repairl Y P4500C002B Goulds Pumps ._-_._-_._._-_._._.;_. Replacem ent . : Description,

7. of Work Installed Replacement Boltina and Weld Repair per the fonlowina approved WPCS 00OZ031 324-.

Hydrostatic II  : Pneumatic lI Nominal Operating Pressure f X ] -

8. Tests Conducted:

Other[ I -Pressure  : ps! p TestTemp. . . °F in.X I in., (2)Informa-Note: Supplemental sheets inform of lists, sketches, or drawings may be used provided (1)size Is 81/2 on each sheet,.and (3)each sheet is numbered and the number of sheets Is tion h items 1 through 6on this report Is included recorded at the top of this form. - . - (10194) Form NIS-2 (Back)

9. Remarks: Quantities identified for the Replacement Fasteners procured on the following Purchase Orders were replaced inP4500C002B.

43 at -10 X2 - W (P.O. 384301 HT. Code F984) 3/4 - 10 X 2 -114' (P.0. 384301 HT. Code F988) 16 3/4- 10X 2' (P.O. 384301 HTCode F989 (Qty. 14) &F990 (Cty. 2). Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made inthe report are correct and this Regair/Replacernent conforms to the rules of the ASME Code, Section Xl. Type Code Symbol Stamp Original Code data report T&B N-21to be supplemented by Owners Section Xl Program 03-017. Certificate of Authorization NO. W_ \E__ration Date WA Signed R.M. Hambleton Lead ISI Engineer D0 20 Owner or Owner's Designee, Titl CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of - Michiban and employed by HSB CT of One State Street. Hartford. CT 06102 have inspected the components described inthis Ownees Report during the period /Z to 50 ' . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis Owner's Report in accordanc 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 inthis Owners Report Furthermnore, neither the Inspector nor his employer shaD be liable inany manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspeclion. Inspector's Signature National Board, State, Province, and Endorsements Date______________ (10/94) For complete work package, see Work Request 000Z031324. . 03-01.8 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS . As Required by the Provisions of the ASME Code Section )a 1., Owner Detroit Edison Company Date May 14. 2003-Name 6400 North Dixie Highway, Newport Ml 48166 Sheet iof A1 l1_. Address 2., Plant Fermi 2Nuclear Power Plant Unift 2 Name 6400 North Dixie Highway, Newport Ml 48166 .Deco Maintenance Address II IRepair Organizflon P.O. No., Job No, etc

3. Work Performed by Detroit Edison Company Type Code Symbol A N/~

Stamp .Name ,. Authorization No. N/A 6400 North Dixie Highway, Newport, MI 48166 Expiration Date W/A Address - 4. Identification T & B NS-22 (RHR Service Water (RHRSWI Pump1s El I5l C0O1B and El 151 C001D). . of System

5. (a) Applicable Construction Code ASME III, 92 92 (Valve),

Class 3 119_71 EdIfion '71 -Addenda NWA 'Code Case (b) Applicable Edition/Addenda of Section )a Utilized for Repairs or Replacerrents -1 92-92 Addenda -:

6. Idenrification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer Serial National Other Yea Repaired, ASME.

Component Manufacturer NO-' Board Identification Bwilt Replaced, Code NO. or Replacement Stamped (Yes ________ N~~~~~~~~~o ~~~~ o), E1151COO1B Goulds Pumps -N301213-2 N/A N/WA 1975 Replacement Y E1151COOlD Goulds Pumps N301213-14 N/A N/A 1975 Replacement Y Descripfion

7. _of Work Installed Reolacement Bolting and performned acoroved Weld Regairs on El 151 CDO1 B per WPCS 0D0Z031466.

B. Tests Conducted: Hydrostatic [JI Pneumatic [I Nominal Operating Pressure I XI Other [ I Pressure ______ psi Test Temp. O Note: Supplemental sheets inform of llsts, sketches, or drawings may be used provided (1)size is81/2 inX 1 in, (2)Informa-tion inHems I through~6on this report isincluded on each sheet, and (3)each sheet isnumbered and the number of sheets is recorded at the top of this formn. (10194) Form NIS-2 (Back)

9. Remarks: Quantities identified for the Replacement Fasteners procured on the following Purchase Orders were replaced inboth E1151CO01B and E1151C001D.

60 7r- 9 X7 (P.O. 388548/HT. Code F944) and 120 Nuts (P.O. 968438 HT. Code QJS) 186 -10X2- W (P.O. 384300/HT. Code F982) 32 34'-10X 1-718 (P.O.384300iHTCodsF983) CARD 03-17716 was written to document that a Sample Plan was used by QA for performing heat Number verification on the Column to Column bolts on both Pumps. This condition was found acceptable per the site Corrective Action Program. Appricable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPUANCE We certify that the statements made inthe report are correct and this Recair/Reolacement conforms to the rules of the ASME Code, Section Xl. Type Code Symbol Stamp Original Code data report to be supolemented by Owners Section Xl Program 03-018. Certificate of Authorization No. NWA t Expiration Date NWA Signed R.M. Hambleton Lead ISI Enaineer S- Date .20 a Owner or Owners Designee, Imte CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB CT of One State Strt Hartford. CT 06102 have Inspected the conponents described inthis Owners Repor during the period . and state that to the best ot my knowledge and belief, the Owner has performed examinations and takerr orrective measures descnbed inthis Owners Report in accordance with the requirements of the ASME Code, Section )a. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described inthis Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable inany manner for ary personal injury or property damage or a loss of any kind arising from or connected with this inspection. £ 2 ~- Commission 4 9,4,^ f-Inspectors Signature National Board, State, Province, and Endorsements Date JLA' O 20, - (10 94) For complete work package, see Work Request 000Z031320, 000Z031 321, and 000Z031466. 019 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS: - As Required by the Provisions of the ASME Code Section X)

1. Owrir  : Detroit Edison Company -Date May 3, 2003

' '- -Name 6400 North Dixie Highway, Newport Ml 48166 -Sheet 1Of t I - : Address

2. Plant Fermi 2 Nuclear Power Plant Unit 2

. Name . , , 6400 North Dixie Highway, Newport Ml 48166 ' I ~ - Deco Maintenance_ Address Address -. RepairOnkation P.O. No., Job No., etr.

3. Work Performed by Detroit Edison Company' Type Code Symbol ' N/A

. Stamp  : ' Name Authorization No. N/~A 6400 North Dixie Highway, Newport, Ml 48166 ' Expiration Date hVA Address coIe si -- 0

4. Identification - Hydrwoen Recombiner/ICombustible Gas System (N5-6021 of System

5. (a) Applicable Construction Code, ASME III,

- - - - '.' ' ' Class 3 19 71 Edition '71 Addenda NWA Code Case

-b) Applicable EditionlAddenda of Section XI WUlzed for Repairs or Replacements 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 Bult Replaced, Code No. orReplacemert Stamped (yes

_ _ _ _ _ _ _ _ _ _ _ _ __ __ __ _ _ __ __ __ __ ___ __ _ _ _ _ __ ____ __ __ _ _ _ __ __ _ __ __ _ __ ~~~or N o) T4804F603A Wismer& NC73110-010 ' NWA V4-2144 1983 Replacement Y Becker _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - Description

7. Of Work Replaced bolt that was damaged during removal of spooo Diece for valve trfurbishment.

8. Tests Conducted: Hydrostatic I ] Pneumatic [I - Nominal Operating Pressure [ X Otherl 1 Pressure ps TestTemp. '

Note: Supplemental sheets inform of lists, sketches, ordrawings may be used provided (1)size isl812 in.X 11 in., (2)informa-tion InItems 1 through 6 on this report is iricluded on each sheet, and (3)each sheet Isnumbered and the number of sheets is recorded at the top of this forn. - (10/94) Formn NIS2 (Back)

9. Remarks: Replacement bolt procurred per POt362048, (1)5/-11 x T, SA-1 93,.Grade B7, -Heat Code US Y06420 (C323).

Appricable Manufacturers Data Reports to be attached CERTIFICATE OF COMPUANCE We certify that the statements made inthe report are correct and his Relacement conforms to the rules of IheASME Code, Section Xl. Type Code Symbol Stamp Original Code data reon to be suMolemented by Owners Section Xl Prworam 03-019 Certficate of Authorization No. WA \ Expiration Date WA Signed R.M. Hambleton Lead ISI Engineer 3 D Owner or Owners Designee, Title CERTIiCATE OF INSERYICE INSPECTION 1,the undersigned, holding avalid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by HSB C1 of One State Street. Hartford. CT 06102 have Inspected the components described inthis Owner's Report during the period- to S - 4=t3 . and state that to the best of my J-? knowledge and belief, the Owner has pedornmed examinations and taken corrective measures described inthis Owner's Report in accordance with the requirements of the ASME Code, Section )(. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied. concemring the examinations and corrective measures described inthis Owners Report. Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this inspection. ga ~~~~~~~Commissions"11041Y6 t>,> f;z Inspector's Signature National Board, State, Province, and Endorsements Date ° (104) For complete work package, see Work Request 000Z031253 t .03-020 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 Date May 21, 2003 Name 6400 North Dixie Highway, Newport Ml 48166 Sheet 1 of 2 - -

Address

2. Plant Fermi 2 Nuclear Power Plant Unit 2 Name 6400 North Dixie Highway, Newport Ml 48166

Deco Maintenance Address - -- Repair Oganation P.O. No., Job No, et.

3. Work Performed by Detroit Edison Company -Type Code Symbol ' I N/A Stamp I . Name Authorization No. NIA 6400 North Dixie Highway, Newport, Ml 48166 `r Expiration Date WA Address

4. Identification N5-307 Residual Heat Removal System (Division 2 i of System

5. (a) Applicable Construction Code ASME 1II, 19 71 Edition '71 Addenda NWA -Code Case Class 2 (b) Applicable Ediflon/Addenda of Section Xl Wlized for Repairs or 1992.92 Addenda Replacements

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Manufacturer Serid Nallonal Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced,

• Code No. or Replacement Stamped (Yes

____________ ___________ ~~~~~~~~~~~~ No) E1100F031 B Wm. Powell 63872-2 ' NA VB-2104 1975 Replacement Y Description

7. of Work Installed Replacement Disc in check valve. Existing disc had evidence of pitting on seating surface and valve has had a history of seat leakage.

8. Tests Conducted Hydrostatic I l Pneumatic [I Nominal Operating Pressure [ X l Other [ ] Pressure ' - '_ psi I Test Temp. OF Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1)size is 8 12 In.X 1 in., (2)informa-tlion initems 1 through 6 on this report Isincluded on each sheet, and (3)each sheet isnumbered and the number of sheets is recorded at the top of this form.

(10/94) Form NIS-2 (Back)

9. Replacement Disc was procured per PO 243229-01, A216 Grade WCB,-Heat Code CM7475B

-. Applicable Manufacturers Data Reports to be attached CERTIFICATE OF COMPUANCE We certify that the statements made inthe report are correct and this Reolacement conforms to the rules of the ASME Code, Section XA. Type Code Symbol Stamp Original Code data report (NS-3071 to be suR2lemented by Owners Section Xl Prooram 03-020. Certificate of Authorization No. WA A Expiration Date NWA Signed R.M. Hambleton Lead iSI Engineer hit L DsytIaAM Owner or Ownefs Designee, Too CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding avalid 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 inthis Owner's Report during the period y -O o- to ( -#-/ 3 . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis Ownees 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 Inthis Owners Report. Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this inspection. ' 4'A~ I Comrnisslons--~< A/;'zt J~O inspector's Signature National Board, State, Province, and Endorsements Date 94 20 .3 (10lg4) For complete work package, see Work Request 000Z023952. i II > T f z f~~~~~= ~~~~~ ~~s srn ~-ert'-'<Ohi 2- .4 1 ilsu

..d tatsmGISAdPTCvtdiatse. 441trt}.-

t . g I~~~~~~~~~~~~~4ff~n V:x lli > Ada" MYl.7n

R

,0 Nt~~~~Derolt EdlsXon- cen mat~io ttwel~e~d Povear tca- Zt- ' ,<s~~~~~~s>>( a,*r and >:Ivnt aedd I:, CPh  :-Vcxo g ~. er-o!No. art CM 7Z.7 -3 u_4j.- gd No Wmx. 15ovell o-Inni~~c~~if~edesel' Fh~Zb D.^dwP+,edApace No.Plto Ale_,.,3-20;1<l Achin {A Cass I-W~e~ .Adderdadaeeinte. 71NZs I_ Seclson~~~~~~~~IE~to"~;?~ ! ~ ~~~~~-tvc ~ ~~~~~~~~~~ 04 o_ fa WOOia =; l rse~rn ~~. +  : - ~~~ (lil;tese id tsac e wtecagn wl esk ~k,;* aktdveslWseto B_~~~~~~~~ttstrs~i > sa67! - H.T.8 _~~~~~~~~~~~~R.T._- ~~Croon-t*ee looo Co'"cat Hemoetsctl Folz S~qto Peen e, 0- - * ~~~~~~~~ -EMtliie toorsCltseorlC 0oach~ :s-e:,ch). s t. . 0 {M^%~t~altval $T C. NDT S .X20S) .- r @} it bottbe. dcrfi. 9- Of Skech 'iW.Par etc It  ; ew.*;V sed--*-es ior; ~~~~~~~~~~~~~~~~~~-a --- *b F Tema._-_.- '. '-: -_*0fIIb-lU.nPressue-Test _ _p~int__ W &ssure__-. ._ . Attachmen~t .......... "i~w;_n: Thk . -Q%-' ' i *Ftaticonr. Maseriaf-t ~ ........ irpttue*0 ofsa Number -T-O.D.__it. l chafltes ofheat exchangem-.f j elis* W t at (tner"tcharntws . *§t9,oj~~~~~to 1sCarrpleed Lenlgth tt._.W on. Orl. Yh_ on. U~~~~~~~~~~~orr. Cool.Alilw. 3 T5F_ ¢-

• 3 ¢iv ?] .

AL *^ Efficiency R.T.= - j - _ ~~~~~~~~~~~~.T.- No. of CCUses _ ___RT.t._ Z__. H. T.

• t tbi Mitelal_

T5S. ...... Ftr S  ;

• to Ft~e 2, UberiS __ Cer;c81 #40oisp~herical

- - C ~~~~~~~~~~~~~~~n ttl:r t feiliatical D canirtzei orcoc -Aven Angle - -aldius Thickness Radius Red a, -Italic i stise v tvtison F . vf* tt . t~. .......... :t;.fS endsuc . ttt;m I Anr I or, tVtin. it 11 in. (2) nfnotostion In ftems gwnrbe used fovidied: ISI sial Is t jitst, sketchet of dtrvvinqr 9 tiutietntt Shees In oren f Shet is foro~dI ite 3- Renak 1-- eac th t nu brdadnme .- tEki, pt 1001t--$Icue an each set.'and

34. 4 -h -te Yok N.Y 1001 obandf.l th Ore Dep., .SE

.TIA fomE040mae f g~~~~~~~~~~~~-V g ~ ~ ~ - -;- - -.- -~~~~~ ,,N o~~~~~  ;~a .7Z, ;', Locd'-J' f~*& o aqp Is ha Inenmwm Ae: &re IN cs~ in5 besig S~peCjfior d Oetign Rep ) .- ~~. ; 19 9 n S;9ned-7heOPT Car% Catc ol fi dtat~~~r Xxputn_ _ _ ~~tt.l.icale of Authorization No _ 1,? .- v; CERTIFICATION 6F dEmm-FOR PUT AC he Siat_ gisrfileat *- * ~....... ............ rf.. E4; &4 _ pll

• E C RE.

I F SHOP ,NSPECTIO .', g _ , cooma~~~~~~~~~~~~~~~~~~iry their i~~~~~~~~~~~~~~~s.~ w4 mu tect. to the bettof-wj-~ i6 t. C~ Wm Hoe ha os ?k.t s craewvtite S-EC8_MO I _ noi;hi~sim C~~~~~~~~~~~~Ispecr tlowb le atv8ianwybi ~ 6*tv~ or ~ ~ .... conce .n thsiseto. *q W="; w-L  !,., ...Co missions '~~~~~~~~~~~~~~~~~~~Ntoa 5"m ' .t ',..c anwd- .r.03-021 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required bythe Provisions of the ASME Code Section Xl Detroit Edison Company Date  : May 14, 2003 -

1. Owner Name Sheet lIOf 1 6400 North Dixie Highway, Newport MI 48166 Address Z Plant Fermi 2 Nuclear Power Plant Unit 2 Name 6400 North Dixie Highway, Newport Ml 48166

- i Deco Maintenance Address Repair COlganizallon P.O. No., Job No., etc.- Detroit Edison Company Type Code Symbol  :=-- NA

3. Work Performed by Stamp -

I Name - I I Authorization No.  : N/A Expiration Date 0 NWA 6400 North Dbde Highway, Newport, Ml 48166 ' - Address -

4. IdentIfication T &B N5 -4 (Emergencv Eauipment Service Water (EESWI Pump P4500C002A) of System Applicable Construction Code ASME III, 92 92 (Valve)

5. (a) NWA Code Case Class " 19 71 Edition 71 Addenda

'(b) Applicable EditiornAddenda of Section Xl Utized fr Repairs or Replacements 1992-92 Addenda

6. ---Identification of Components Repaired or Replaced and Replacement Components ManufacturerSerial National Other Year Repaired, ASME Nameof Name of Code Manufacturer- 'No Board Identification Built Replaced, Component Stamped No. or Replacement (yes

.__ ______________ or No) W/A N/A 1977 Repair/ Y P4500C002A E Goulds Pumps TCN N0006-1 Replacement -__-_______L-__=______ Description 294-1.

7. of Work Installed Replacement Bolting and performed Weld Repairs per the following agDroved WPCS 00OZ031

8. Tests Conducted: Hydrostatic [I _ Pneumatic [1 Nominal Operating Pressure l X I Ps!'-psi Test Temp. - OF Other [I Pressure (1)size is81/2 in.X 11 in., (2)infoma-Note: Supplemental sheets inform of lists, sketches, or drawings may be used provided each sheet, and (3) each sheet is numbered and the number of sheets Is tion inItems 1through 6 on this report IsIncluded on recorded at the top of this form.

(1104), -- -..- ..,I 1- I --z - 7 ,.. .: - '7' - -I'- -: - - i. ., I I-e siI . !.)'I.' I Form NIS-2 (Back)

9. Remarks: Quantities identified for the Replacement Fasteners procured on the following Purchase Orders were replaced inP4500C002A.

40 W-10 X 2 - W (P.O. 384301 / HT. Code F987) 8 3/4'-10 X 2 -1/4 (P.O. 384301 /HT. Code F988) 16 3/4'-1OX 2L (P.O.384301 HTCodeF990) Applcable Manufacturees Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made Inthe report are correct and this Reoair/Reolacement conforms to the rules of the ASME Code, Section Xl. Type Code Symbol Stamp Orignal Code data report {T&B N5L4) to be suoulemented by Owners Section Xl Proaram 03-021. Certificate of Authorization No. N/A Expiration Date NA Sined R.M. Hambleton Lead ISI EngIneera k Dat Oa Owner or Owner's Designee, Tie CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding avalid 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 inthis Owners Report during the peflodY-#/A 4to =-a2 /- a' , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described inthis 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, conceming the examinations and corretive measures described inthis Owner's Report. Furthermore, neither the Inspector nor his employer shag be lable inany manner for any personal injury or property damage or aloss of any kind arising from or connected with this inspection. CommissionsAV'R 9 Y86 4oz4z d ,v / Inspectors Signature National Board, State, Province, and Endorsements Date 0 3 (10/94) For complete work package, see Work Request 000Z031294, 000Z031597, and 000Z031 284. 022 FORM NIS-2 OWNERS REPORT FOR REPAIRS OR REPLACEMENTS

As Required by the Provisions of the ASME Code Section Xt(

1. Owner Detroit Edison Company Date May 14 2003 Name 6400 North Dbde Highway, Newport Ml 48166 =

ZSheet 1 of 1 Address

2. Plant Fermi 2 Nuclear Power Plant Unit -2 Name 6400.North Dixie Highway, Newport Ml 48166 Deco Maintenance Address . .Repaii Organizaion P.O. No., Job No., etb.

3. Work Performed by Detroit Edison Company

• IType Code Symbol I WA Stamp . - .

Name EAuthorization No. WA 6400 North Dixie Highway, Newport, Ml 48166 I Expiration Date - N/A Address

4. Identification N5 -5 (Emeroency Diesel Generator (EDG) Number 11 and 12 Service Water Pumps) of System

5. (a) Applicable Construction Code ASME III, :92 *92 . (Valve)-

Class3: 19 71 Edition 71 Addenda * . NA Code Case (b) Applicable Edition/Addenda of Section Xl Utilized for Repairs or Replacements 1592.92 Addenda

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Nafional Oter OthManufacturerSedal Year Repaired, ASME Component Manufacturer No: Board Identification Built Replaced, Code No.: or Replacement Stamped (Yes

._____ .__ . No) -.. - . . .. . .or R3001CO05 Goulds Pumps TCN N0007-1 N:A NIA 1977 Repair/ Y . '___________ :.i- =:. - RePlacement R3001C006 Goulds Pumps TCN N0007-2 N/A N/A W 197 Repairl Y .___________ .. .. Replacement Description -7. - of Work Installed Renlaernent Rrlfinri and nerformed Weld Renairs oer anorved VdP('-q MUM 90-1 and nM7(lql 9A.S .8. : Tests Conducted: Hydrostatic II Pneumatic [II Nominal Operating Pressure [X I  :- Other I Pressure - _ _  :- ps ' Test Temp. :O°F Note: 'Supplemental sheets Inform of lists, sketches, or drawings may be used provided (1)size is 8 1/2 in.X 11 In., (2)informa-tion InKtems 1through 6 on this report isIncluded on each sheet, and (3)each sheet isnumbered and the nurnber of sheets is recorded at the top of this form. (104) - i L lt r1 Form NIS-2 (Back)

9. Remarks: Quantities Identified for the Replacement Fasteners procured on the following Purchase Orders were replaced Inboth R3001 COOS and R3001 COO6. -

40 -10 X 2- W (P.O. 384301 1HT. Code F984) 8 W -11 X Z (P.O. 384301 /HT. Code F985) 16 5/W'-11 X13/4 (P.O. 384301 HTCode F986) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made Inthe report are correct and this Reoair/Reolacement conforms to the rules of the ASME Code, Section XL Type Code Symbol Stamp Original Code date report T&B N5-5 to be suocdemented by OwnersSection XI Program 03-2 Certificate of Authorization No. NWA Expiration Date N/A Signed R.M. Hambleton Lead ISI Engineer l %Dat I20 Owneror Owner's Designee, Tite CERTIFICATE OF INSER VICE INSPECTION 1,the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessal Inspectors and the State or Province of Michigan and employed by HSB CT oOnf State Street. Hartford CT 06102 have inspected the components described Inthis Owners Report during the period to OSIZC- ° .and state that to the best of my knowledge and belief, the Owner has performed examinations and taken coTecdve measures desonbed inthis 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, conceming the examinations and corrective measures described inthis Owner's Report Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. X ~~~~~~~~~Commissions^/9F' A'a gusto Inspector's Signature National Board, State, Province, and Endorsements Date G L -2 ° 20OC1 (1 G94) For complete work package, see Work Request 000Z031290, 000Z031293, and 000Z031597.03-025 FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

As Required by the Provislons of the ASME Code Section Xl

1. Owner Detroit EdisonCompany Date May21, 2003 Name 6400 North Dixie Highway, Newport Ml 48166 Sheet l of 2 Address

2. Plant Fermi 2 Nuclear Power Plant Unit 2

-.  : Name-6400 North Dixie Highway, Newport MI 48166 Deco Maintenance Address I  : . = .- I.I - . RepairOanizaton P.O. No., Job No., elc

3. Work Performed by Detroit Edison Company - I -Type Code Symbol W.-A S

Stamp Name Authorization No. N/A 6400 North Dixie Highway, Newport, Ml 48166 Expiration Date 1 N/A Address . I

4. Iderification N5"13 EECWSvstem Dinsion 1 -

of System

5. (a) Applicable Construction Code ASME Ill, Class 3 19 71 Edition 71 Addenda WA Code Case (b) Applicable EditionbAddenda of Section Xl Utilized for Repairs or Replacements 1992-92 Addenda

'6. Identificablon of Components Repaired or Replaced and Replacement Components Name of Nameof Manufacturer Serial National Other Year Repaired, ASME Component Manufacturer No Board Identification Built Replaced, - . Code No. or Replacement Stamped (Yes P44F402A ___________ ___-__-____'_ or No) Fisher Controls 5916391 WA VB-24 1974 Replacement Y Description -7. of Work Install replacement stem and pluo assembly and redlace additional intemal trim tems.

8. Tests Conducted. Hydrostatic ]I I Pneumatic [I Nominal Operating Pressure I X ]

Other[I Pressure psi Test Temp. Note: Supplemental sheets Inform of ists, sketches, or drawings may be used provided (1)size is81/2 in.X 11 in., (2)Informa-Son hI Hems 1through 6 on this report IsIncluded on each sheet, and (3)each sheet is numbered and the number of sheets is recorded at the top of this form. (1094) Form NIS2 (Back)

9. Remarks: Replacement Plug/Stemassembly procured par PO239515, Ser'al No. DC5919-2 (ReportAttached) Inaddition, othertrim replaced included the Cage, Seat Ring, and Seat Ring Adapter.

Appilcable Manufacture's Data Reports to be attached CERTIFICATE OF COMPLIANCE We cerify that the statements made inthe report are correct and this Redacement 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 ProaramM0025 Certificate of Authorization No. NtA Expiration Date NWA Signed R.M. Hambleton Lead ISI Engineer Date .20o3 Owner or Ownees Designee, Trie CERTIFICATE OF INSERVICE INSPECTION 1,the undersigned, holding avalid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of MWchigan and employed by HSB CT of One State Street Hartford. CT 06102 have inspected the components described inthis Ownees Report during the period Z-3to G °3 and state that to the best o my knowledge and belief, the Owner has performed examinations and taken correcive measures described inthis Owner's Report in accordance with the requirements of the ASIME Code, Section Xl. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or impied, conceming the examinations and corrective measures descrbed Inthis Owner's Report. Furthermore, neither the Inspector nor his employer shal be liable Inany manner for any personal Injury or property damage or aloss of any kind arising from or connected with this inspection. C' Commissions./g~?'9o 6 A~f A-2,O Inspector's Signature National Board, State, Province, and Endorsements Date97c -e 3 20Do 7 (104) For complete work package, see Work Request 000Z030591 V - I I- , _,-17".7-- ,Mt::L. . .1 - - -W g > 9k - - FORM N-2 CSMFICATE,*IQl NUCLEAR PR AsiRequkod bytePosI _____ __ ~'Not TO .ed by FISHER CONTROLS I Ailoit Edison Co. , Bor

• LcatonfiitalaionFermil II P.Over.- Plant. V Ki

• Tpe IOA61l' iedv. S-4179-316SS.T vjj s~aioc~.S. bII~' 1971.Wne Fr In ccordnce w'ifth Cows. Sped. (Div. 2 m

.= - ,K.-. r :' .. . -. ., . .I- - I . - - , ,.

8. Nomn. thiciness (in.) L/AL Min. design dtickn

9. sW~ena ieable Cerficate icate Hodtrs' Dit Reportsi

• wdim,

'"  ;**Ste

• 4..~~~~~4- I~

r- a j = *~~~*~~ti~~l N~umber-P - A; DC5i9.-2..

7) *.*7 **. . 4 3- _

,. (= - , '-. I I.-w (1-2) . ..fl 1~~ I, (49) (24) -25) f15f Rn psi. Temp. " F. H

10. Design pressure pvided II #size k 6

• Sup ments infornation in the fonn of fists. sketches. or drawin may eused ic recorded a te tnp of Js Included on each sheet. 131 each sheet Is numbered and the number of sheet (12186/ I - This farm VE000401 may be obtained from the Odr DePt ME 2~~~~~ . - .--

!r.S ok S. : . - I j~~~~~~~~~~~~~~ l >f ~~~~~~Sylvester H. i e ] l l ~~~~b..:. . + r n. i "n§ ~~~~~~mad In this report ar cortWthtti ~~~~~~ ^ l~ N FI SHER CONTJ li go1 W >M~~iO~iBCONX- ;ave irpected these. item~sdesbd inthitD.Ret Data E .gt~M Wp No'}e has Lcated &bese l dlertictHk EcpiJi& ba I=~ wu~d frsarnpft on the dthw abge.'l Aft'~~~~u4nnr. nithe thnVrnr ~~~~~~~~etir f, ispe trno hS m Y I i*AIii aopoe ... .. _ SX