ML020450608

Inservice Inspection (ISI) Summary Report Fall 2001 Inservice Inspection Period

ML020450608
Person / Time
Site:	Dresden
Issue date:	02/05/2002
From:	Swafford P Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PSLTR #02-0009
Download: ML020450608 (86)

Text

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Exelon Generation Company, LLC www.exeloncorp.com Nuclear Dresden Nuclear Power Station 6500 North Dresden Road 10 CFR 50.4 Morris, IL 60450-9765 10 CFR 50.55a February 5, 2002 PSLTR #02-0009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 2 Facility Operating License No. DPR-19 NRC Docket No. 50-237

Subject:

Inservice Inspection (ISI) Summary Report Fall 2001 Inservice Inspection Period Enclosed is the Dresden Nuclear Power Station (DNPS) Unit 2 Post-Outage (90 day)

Summary Report for ISI examinations and repair/replacement activities conducted from January 12, 2000 to January 21, 2002. Unit 2 completed its seventeenth refueling outage (D2R17) on November 7, 2001. This report has been submitted to you in accordance with the requirements of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components,"

Article IWA-6200.

Should you have any questions concerning this letter, please contact Mr. D. F. Ambler, Regulatory Assurance Manager, at (815) 416 - 2800.

espectfully, "Pres n Swafford Sit Vice President Dresden Nuclear Power Station Attachment cc:

Regional Administrator - Region III NRC Senior Resident Inspector, Dresden Station

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Table of Contents Introduction Form NIS-1 Owners Report for Inservice Inspections Scope of Inspection Abstract of ISI and Augmented Examinations Attachment A Summary of Vessel Interior Examinations Abstract of Corrective Measures III Abbreviations IV Repairs and Replacements Since the Preceding Summary Report V

Prepared By:

Roger H. Bauman ISI Coordinator Reviewed By:

J e--t Robert D. Geier Pressure Testing and IVVI Coordinator Reviewed By:

y John H. Young Containment ISI Coordinator Reviewed By:

Robert L. Testin Snubber Coordinator Approved By:

Mohammad Molaei Engineering Programs Supervisor 1

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section I Introduction The seventeenth Inservice Inspection (ISI) of Dresden Unit 2 was performed during the D2R17 outage which began on October 20, 2001 and was completed on November 7, 2001. This was the second of two scheduled refuel outages in the third inspection period of the unit's 3rd 10-year ISI Inspection Interval which commenced on March 1, 1992. The third inspection period commenced on October 1st, 1999 and is currently scheduled to end on January 19, 2003. In addition to examinations performed during D2R17, a large number of examinations were performed during on-line operation of Unit 2. This report contains all examinations completed during D2R17 and on line examinations which were not included in the previous Unit 2 Summary Report (dated January 19, 2000).

General Electric was contracted to perform the non-destructive examinations and reactor vessel visual examinations during the refuel outage. Dresden Engineering Programs Group performed the remaining visual and NDE examinations during D2R17 as well as the on line examinations.

The Authorized Nuclear Inservice Inspector's (ANII) services were provided by The Hartford Steam Boiler Inspection Insurance Company of Connecticut. The ANII reviewed procedures, personnel qualifications, instrument and material certifications, and examination results.

All examinations were performed in accordance with the Dresden Station ISI Program, Dresden Station Technical Requirements Manual, the ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition and 1998 Edition (implemented in accordance with Relief Request MCR-02 for Containment ISI), Generic Letter 88-01, BWRVIP-75, and In-Vessel Visual Examinations in accordance with BWRVIP Inspection and Evaluation Guidlines.

A list of abbreviations used throughout this report can be found in Section IV of this report.

2

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

1. Owner Exelon Nuclear, P.O. Box 805379, Chicago, IL 60680-5379 (Name and Address of Owner)

2. Plant Dresden Nuclear Power Station, 6500 N. Dresden Road, Morris, IL 60450 (Name and Address of Owner)

3. Plant Unit Two

5. Commercial Service Date 6-9-72

4. Owner Certificate of Authorization (if required)

6. National Board Number for Unit N/A N-137

7. Components Inspected See Section II of this report (report is 85 total pages).

Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/22 in. x 111/22 in., (2) information in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

3 Component or Manufacturer Manufacturer State or National Appurtenance Or Installer or Installer Province No.

Board No.

Serial No.

Reactor Vessel Babcock & Wilcox, 610-0098-51-52 B0082800 N-137 Barberton, Ohio Class I & 2 Systems General Electric-APED N/A N/A N/A Morris, IL I

1.

1.

1.

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FORM NIS-1 (Back)

8. Examination Dates:

9. Inspection Period Identification:

10. Inspection Interval Identification:

1/12/2000 to 1/21/2002 3 Period - From 10/1/1999 to 1/19/2003 3 rd Interval - From 3/1/1992 to 1/19/2003

11. Applicable Edition of Section XI 1989 Addenda N/A 1998*

Addenda N/A 1998 edition implemented in accordance with Relief Request MCR-02 for Containment Inservice Inspection.

12. Date/Revision of Inspection Plan:

6/1/2001 Rev.6

13. Abstract of Examination and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. See Attached Sections II and III.

14. Abstract of Results of Examinations and Tests. See Attached Sections II and III.

15. Abstract of Corrective Measures. See Attached Sections II and III.

We certify that a) the statement made in this report are correct, b) the examinations and tests meet Inspection Plan as required by the ASME Code,Section XI, and c) corrective measures taken conform to the ASME Code,Section XI.

Certificate of Authorization No. (if applicable)

Date I3

/ I 20 02 Signed By

,11Y4n-N/A Expiration Date N/A Exelon Nuclear Dresden Nuclear Power Station.

Dresden Station ISI Coordinator Owner CERTIFICATE OF INSERVICE INSPECTION I, the under signed, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois And employed by Hartford Steam Boiler of CT have inspected the components described in the Owner's Report during the period 1/12/2000 To 1/21/2002

, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, tests, and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

- JC ommissions NB7742NISB, IL932 Inspector's Signature National Board, State, Province, and Endorsements Date

,,- 4 20 02 4

Owner

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section II Scope of Inspection Abstract of ISI and Augmented Examinations ISI and Augmented Examinations Table A contains a list of components examined prior to, during and after the D2R1 7 refuel outage, to satisfy the requirements of the Dresden Station ISI Program, Dresden Station Technical Requirements Manual, the ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition and 1998 Edition (implemented in accordance with Relief Request MCR-02 for Containment ISI), Generic Letter 88-01 and BWRVIP-75. Those items which were examined and meet the acceptance standards of ASME Section XI or Generic Letter 88-01 are identified as "Acceptable" under the results column. Those items that required further evaluation are identified with "Section III" in the results column and are further discussed in Section III of this report.

Dresden Station requested deferal of thirty-three weld overlays which do not meet the requirements of Open Item 3.4 of BWRVIP-75 with regard to the number of inspections required prior to implementing BWRVIP-75 inspection frequencies. This deferal was approved by the NRC permitting deferal until October 2003 or until completion of the NRC staff review and approval of the BWRVIP-75 report, whichever comes first.

Snubber Examinations (Technical Requirements Manual 3.7.H)

All Section XI Class 1, 2 and 3 safety-related snubbers are visually (VT-3) examined in accordance with Dresden Technical Requirements Manual 3.7.H. A sample population of snubbers are functionally tested every outage. Table A includes all the snubbers functionally tested during D2R17 and any visual examined snubbers that required further evaluation.

Snubbers that required further evaluation are identified with "Section III" in the results column and are further discussed in Section III of this report.

Summary of Reactor Vessel Weld (Category B-A) Examinations The Unit 2 reactor vessel shell welds are examined as required by 1 OCFR50.55(a) and ASME Section XI. These welds are addressed under Examination Category B-A, Item numbers B1.11, Circumferential Shell Welds; Item B13.12, Longitudinal Sheel Welds; and Item B1.30, Head to Flange Weld. Two relief requests were associated with these inspections. First, relief was requested, and subsequently granted, from requirements to examine welds under item B1.11.

The technical basis for this request is established in BWRVIP-05. Second, a schedule exemption was requested, and subsequently approved, to allow performance of these inspections over an additional refueling outage. Otherwise, the entire inspection would have been required during D2R17, the last outage in the third inspection interval. The basis of this request was to allow the station to attempt to take advantage of a new inspection technology, the AIRIS 21 system, to achieve an increased coverage without significantly impacting the outage.

Summary of Vessel Interior Examinations Attachment A contains a summary of examinations performed to satisfy the requirements of ASME Section XI categories B-N-i, B-N-2, and various special examination requirements.

Details of the examinations, results, and corrective measures are included.

5

Exelon Nuclear P.O. Box 805379, Chicago, IL 60680-5379 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 October 2001 Inservice Inspection Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Section II Scope of Inspection Abstract of ISI and Augmented Examinations Current Interval Status As of the date of this report, the percentages listed in the table below represent the status of inspections for the 3rd inservice inspection interval. All remaining examinations, with the exception of reactor vessel shell welds are scheduled to be completed prior to the end of the inspection interval. The remaining reactor vessel shell welds (Examination Category B-A) are scheduled to be completed during refueling outage D2R1 8 at the start of the 4 th inservice inspection interval in accordance with an approved exemption request.

6 Examination Deferral is permissible in Inspected in accordance Category accordance with Table with Inspection Program B IWX-2500-1 B-A 73%

100%

B-D N/A 100%

B-E 100%

N/A B-G-1 80%

N/A B-G-2 100%1 100%

B-M-1 0%

N/A B-M-2 100%1 N/A B-N-1 N/A 100%

B-N-2 100%

N/A B-0 100%

N/A C-A N/A 50%

C-B N/A 83%2 C-C N/A 64%

D-B N/A 78%

F-A N/A 80%

R-A N/A 85°/o3

1.

Percentage represents components subject to inspection only when disassembled for maintenance, repair, or volumetric examination.

2.

Percentage does not include components subject to VT-2 examination each inspection period. VT-2 examinations during the 3rd inspection period are scheduled for completion prior to the end of the inspection interval.

3.

Percentage does not include socket welds subject to VT-2 examination each inspection period. VT-2 examinations during the 3rd inspection period are complete.

Exelon Nuclear P.O. Box 805379, Chicago, IL 60680-5379 October 2001 Inservice Inspection Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section II Scope of Inspection Abstract of ISI and Augmented Examinations Category Item-Augment yse Ln flnmnnAnt Tvoe Exam Credit iiesuits I

B-A B1.12 B-A B1.12 B-A 81.12 B-A B1.12 B-A B1.12 B-A B1.12 B-A B1.12 B-A B1.12 B-A B1.12 B-A B-1.12 B-A B1.12 B-A B1.12 B-A B1.12 B-A B1.12 B-A B1.30 B-A B1.30 B-A B-1.30 B-A B1.30 B-A B1.30 B-A B1.30 "B-D B3.100 B-D B3.100 B-D B3.100 B-D B3.100 B-D B3.100 B-D B3.100 B-D B3.100 B-D B3.100 B-D B3.90 B-D B3.90 B-D 83.90 B-D B3.90 8-D B3.90 B-D B3.90 B-D B3.90 B-D B3.90 B-D B3.90 B-G-1 B6.10 B-G-1 B6.20 B-G-1 86.50 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV UPP HD RPV UPP HD RPV UPP HD RPV LWR HD RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV SHELL RPV UPP HD RPV UPP HD RPV UPP HD 2-SCIA-VERT 2-SC1 B-VERT 2-SCi D-VERT 2-SC2D-VERT 2-SC3A-VERT 2-SC3B-VERT 2-SC3C-VERT 2-SC3D-VERT 2-SC3E-VERT 2-SC4A-VERT 2-SC4B-VERT 2-SC4C-VERT 2-SC4D-VERT 2-SC4E-VERT 2-SC4-FLGA 2-SC4-FLGB 2-SC4-FLGC 2-SC4-FLGD 2-SC4-FLGE 2-SC4-FLGF N3A-1 N3B-1 N3C-1 N3D-1 N5A-1 N18A-1 N18B-1 N8-1 N12-2 N3A-2 N3B-2 N3C-2 N3D-2 N5A-2 N18A-2 N188-2 N8-2 LONG LONG LONG LONG LONG LONG LONG LONG LONG LONG LONG LONG LONG LONG RPV-FLG RPV-FLG RPV-FLG RPV-FLG RPV-FLG RPV-FLG NIR NIR NIR NIR NIR NIR NIR NIR NOZ-RPV RPV-NOZ RPV-NOZ RPV-NOZ RPV-NOZ RPV-NOZ NOZ-RPV RPV-NOZ RPV-NOZ N/A RPV RPV UPP HD HD NUTS (92)

FLGBLT N/A RPV RPV UPP HD HD STUDS IN PLC (92)

FLGBLT N/A RPV RPV UPP HD WSHR/BSHG (92)

FLGBLT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT UT Xl Xl Xl Xl Xl Xl Xl Xl Xl Xl Xl Xl Xl Xl Xl X1 XI Xl Xl Xl Xl Xl Xl XI Xl Xl Xl Xl X1 Xl Xl Xl Xl Xl Xl XI Xl Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable VT-1 Xl UT XI VT-1 XI 7

Component Type Exam Credit Results

Exelon Nuclear P.O. Box 805379, Chicago, IL 60680-5379 October 2001 Inservice Inspection Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section II Scope of Inspection Abstract of ISI and Augmented Examinations Category Item Comnanent fl.v-,,

7 Accptbl B-G-2 B7.50 N/A B-G-2 B7.50 N/A B-G-2 B7.50 N/A B-G-2 B7.50 N/A B-G-2 B7.50 N/A B-G-2 B7.50 N/A B-G-2 B7.50 N/A B-G-2 B7.50 N/A B-M-2 B12.50 N/A B-N-1 B13.10 N/A B-N-2 B13.20 N/A B-N-2 B13.30 N/A B-N-2 B13.40 N/A B-0 B14.10 N/A B-P B15.XX N/A B-P B15.XX N/A C-B C2.21 N/A C-B C2.21 N/A C-B C2.21 N/A C-B C2.21 N/A C-B C2.31 N/A C-B C2.31 N/A C-C C3.20 N/A C-C C3.20 N/A C-C C3.20 N/A C-C C3.20 N/A C-C C3.20 N/A C-C C3.20 N/A C-C C3.20 N/A C-C C3.20 N/A MSA MSA MSC MSC MSC MSD MSD MSD 3001 A-6 3001 A-6 3001 C-6 3001 C-6 3001 C-6 3001 D-6 3001 D-6 3001 D-6 MSA 3001 A-6 RPV RPV SHELL RPV RPV SHELL RPV RPV SHELL RPV RPV SHELL RPV RPV LWR HD RR TEST BLOCK SBLC TEST BLOCK ISCOCR 1303A-8 ISCOCR 13038-8 ISCOSS 1302A-12 ISCOSS 1302-112 ECCS 1501-20 ECCS 1501-20 ECCS ECCS ECCS ECCS ECCS ECCS HPCI PD 1501-24 1501-24 1501-24 1501-24 1501-24 1501-24 2304-14 ISCOSS 1302-14 SV-2-203-4A SV-2-203-4B ERV-2-203-3C SV-2-203-4E SV-2-203-4F ERV-2-203-3D SV-2-203-4G SV-2-203-4H TRV-2-203-3A VESSEL INT IN-BELTLINE ATT OUT-BELTLINE AT CORE SUPPORT M2-4607 2RC01 2SC01 8-9 8-8 12-9 12-8 20-6 20-8 M-3202-01 M-3202-02 M-3202-09 M-3202-1 0 M-3202-11 M-3202-12 M-1151 D-10 M-1 163D-261 FLGBLT FLGBLT FLGBLT FLGBLT FLGBLT FLGBLT FLGBLT FLGBLT VT-1 X1 VT-1 Xl VT-1 XI VT-1 XI VT-1 XI VT-1 Xl VT-1 Xl VT-1 Xl Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable VLV VT-3 Xl Acceptable RPV VT-3 Xl See Attachment A IWA VT-1 Xl IWA VT-3 Xl IWA VT-3 Xl See Attachment A See Attachment A See Attachment A P-FLG PT Xl Acceptable N/A VT-2 XI See Section III N/A VT-2 XI Acceptable SHL-NOZ MT Xl UT SHL-NOZ MT Xl UT NOZ-SHL MT Xl UT NOZ-SHL MT Xl UT SDL-SHL MT XI SDL-SHL MT XI IWA IWA IWA IWA IWA IWA IWA IWA MT Xl MT Xl MT Xl MT Xl MT Xl MT XI MT Xl UT PT Xl Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable See Section III Acceptable 8

Type Exam Credit Results 31 :i&'i* -

Exelon Nuclear P.O. Box 805379, Chicago, IL 60680-5379 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section II Scope of Inspection Abstract of ISI and Augmented Examinations October 2001 Inservice Inspection Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72

.. a.tegor.

.tem.

Augment System Line Component Type Exam

-Credit Results C-H C7.ST N/A C-H C7.XX N/A C-H C7.XX N/A C-H C7.XX N/A C-H C7.XX N/A C-H C7.XX N/A C-H C7.XX N/A D-B D2.IA N/A D-B D2.IA N/A D-B D2.IA N/A D-B D2.IA N/A D-B D2.IA N/A D-B D2.XX N/A D-B D2.XX N/A E-A E1.11 N/A E-A E1.12 N/A E-A E1.12 N/A E-A E1.30 N/A F-A F1.10 N/A F-A F1.10 N/A F-A F1.10 N/A F-A F1.10 N/A F-A F1.10 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.20 N/A F-A F1.30 N/A HPCI TEST BLOCK HPCI TEST BLOCK RPV TEST BLOCK RR TEST BLOCK SBLC TEST BLOCK SBLC TEST BLOCK SBLC TEST BLOCK SRVDA 301 9A-12 SRVDB 3019B-12 SRVDC 3019C-12 SRVDD 3019D-12 SRVDE 3019E-12 ISCO TEST BLOCK MS TEST BLOCK CONT CONT CONT CONT N/A N/A N/A N/A MSC 3001 C -20 MSD 3001D-20 RHS 0304-2.5 RHS 0304-2.5 RHS 0304-2.5 CSBD 1404-12 ECCS 1501-24 ECCS 1501-24 ECCS 1501-24 ECCS 1501-24 HPCISS 2305-10 HPCISS 2305-10 HPCISS 2305-10 HPCISS 2305-10 HPCISS 2305-10 HPCISS 2305-10 HPCITE 2306-24 ISCOSS 1302B-12 LPCIAD 1504-16 LPCIBD 1509-18 LPCITR 1517-14 SRVDC 3019C-8 2HP03 2HP01 2NB01 2RC01 2SC01 2SC02 2SC03 M-1 177D-1 M-1 177D-4 M-1 177D-7 M-1 177D-1 0 M-1 177D-13 21C01 2MS01 DW 502 LINER TOR B10 SUB TOR B14 SUB DW BASE MBARR M-564G SHT 1 M-564H SHT 1 M-1 167D-1 M-1167D-2 M-1 167D-3 M-3209-20 (1/3)

M-3202-02 M-3202-09 M-3202-23 M-3202-26 2305-G-201 M-1 151 D-103 M-1 151 D-132 M-1151 D-277 M-1 151 D-292 M-1 151 D-294 M-3212-06 M-1 1 63D-82 M-3213-12 M-3214-06 M-3208-06 (2/2)

M-564G SHT 8 N/A N/A N/A N/A N/A N/A N/A IWA IWA IWA IWA IWA N/A N/A VT-2 Xl VT-2 Xl VT-2 XI VT-2 Xl VT-2 XI VT-2 XI VT-2 Xl VT-3 XI VT-3 XI VT-3 XI VT-3 XI VT-3 XI VT-2 Xl VT-2 XI DW LINER GV XI TOR LINER VT-1 BL TOR LINER VT-1 BL MBARR GV Xl CL 1 SNB F.TEST OTHR CL 1 SNB F.TEST OTHR CL 1 SUP VT-3 AD CL 1 SUP VT-3 Xl CL 1 SUP VT-3 AD CL2SNB F.TEST OTHR CL2SNB VT-3/4 XI CL2SNB VT-3/4 XI CL2SNB VT-3/4 Xl CL2SNB F.TEST OTHR CL 2 SUP VT-3 Xl CL 2 SUP VT-3 Xl CL 2 SUP VT-3 XI CL2SUP VT-3 XI CL2SUP VT-3 XI CL2SUP VT-3 Xl CL2SUP VT-3/4 XI CL2SUP VT-3 XI CL2SNB F.TEST OTHR CL2SUP VT-3 Xl CL2SNB F.TEST OTHR CL3SNB F.TEST OTHR Acceptable Acceptable Acceptable See Section III Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable See Section III See Section III See Section III See Section III Acceptable Acceptable See Section III See Section III See Section III Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable 9

Exelon Nuclear P.O. Box 805379, Chicago, IL 60680-5379 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section II Scope of Inspection Abstract of ISI and Augmented Examinations October 2001 Inservice Inspection Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Category Item Augment System Line-,

Component Type Exam,.

Credit -------

Resul.ts F-A F1.40 N/A F-A F1.40 N/A F-A F1.40 N/A F-A F1.40 N/A F-A F1.40 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.11 N/A R-A R1.20 GL88-01 A R-A R1.20 N/A R-A R1.20 N/A R-A R1.20 N/A R-A R1.20 GL88-01 A R-A R1.20 GL88-01 A R-A R1.20 N/A R-A R1.20 N/A R-A R1.20 N/A RPV RPV LWR HD RRAS RRAS RRBS RRBS PMP 2A-0202 PMP 2A-0202 PMP 2B-0202 PMP 2B-0202 FW 3204B-18 HPCI 2306-24 MS MS MS MS MS MS RPV RVBD SBLC SBLC SDC 3007-2 3007-2 3007-2 3007-2 3007-2 3007-2 UVLB 1265-2 1102-1.5 1102-1.5 1001A-16 SDC 1001B-16 HPCI MS 2305-14 3001 A-20 MS 3001 B-20 MS 3001 D-20 RR RR SBLC SBLC SBLC N/A N/A GL88-01 C ISCO N/A N/A GL88-01 C ISCO N/A N/A GL88-01 C ISCO N/A N/A GL88-01 C ISCO N/A N/A GL88-01 C ISCO N/A N/A GL88-01 C ISCO 0203A-4 0203A-4 1102-1.5 1102-1.5 1102-1.5 1302-14 1302-14 1302-14 1302-14 1302A-12 1302A-12 M-1 175D-5 M-1135 SHT 13 M-1 135 SHT 8 M-1135 SHT 10 M-1135 SHT 15 18-1 24-16 MSD2-1(A)

MSD2-14 MSD2-1 8 MSD2-24 MSD2-3(A)

MSD2-9(A)

UVLB2-2 2-10 SLC1.5-10 SLC1.5-11 16-21B 16-2B N5A-3 20-K6 20-K10 20-K10 SPM-45-25(A)

SPM-45-7(A)

SLC1.5-31 SLC1.5-32 SLC1.5-39 14-6 14-7 14-8 14-9 12-1 12-2 CL 1 SUP VT-3 Xl CL 1 SNB VT-3 OTHR CL 1 SNB FTEST OTHR CL 1 SNB F.TEST OTHR CL 1 SNB F.TEST OTHR VLV-TEE MT XI UT-E EL-P MT Xl UT-E SWR-SWT VT-2 XI SWV-P VT-2 Xl P-SWE VT-2 Xl P-SWV VT-2 XI SWT-P VT-2 Xl SWT-P VT-2 Xl P-SWR VT-2 Xl P-SWE VT-2 Xl SWT-P VT-2 Xl RED-SWT VT-2 Xl P-EL MT Xl UT-E P-P MT XI UT-E NOZ-SE UT-E XI EL-P MT Xl UT-E P-EL MT Xl UT-E P-EL MT Xl UT-E SWP-CAP UT-E Xl SWP-RED UT-E Xl SWE-P VT-2 XI P-SWE VT-2 XI SWE-P VT-2 XI P-P UT AG P-TEE UT AG TEE-RED UT AG TEE-RED UT AG RED-P UT AG P-P UT AG Acceptable See Section III Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable 10

Exelon Nuclear P.O. Box 805379, Chicago, IL 60680-5379 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 October 2001 Inservice Inspection Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Section II Scope of Inspection Abstract of ISI and Augmented Examinations Category Item Augment System Line Component Type Exam Credit Results N/A N/A GL88-01 C ISCO 1302A-12 N/A N/A GL88-01 C ISCO 1302A-12 N/A N/A GL88-01 C ISCO 1302A-12 N/A N/A GL88-01 C ISCO 1302A-12 N/A N/A GL88-01 C ISCO 1302A-12 N/A N/A GL88-01 C ISCO 1302A-12 N/A N/A GL88-01 C ISCO 1302B-12 N/A N/A GL88-01 C ISCO 1302B-12 N/A N/A GL88-01 C ISCO 1302B-12 N/A N/A GL88-01 C ISCO 1302B-12 N/A N/A GL88-01 C ISCO 1302B-12 N/A N/A GL88-01 C ISCO 1302B-12 N/A N/A GL88-01 C ISCO 1302B-12 N/A N/A GL88-01 F RR 0201A-28 N/A N/A GL88-01 F RR 0202B-28 12-3 P-EL 12-4 EL-P 12-4A P-P 12-5 P-EL 12-6 EL-P 12-7 P-SE 12-1 RED-P 12-2 P-EL 12-3 EL-P 12-3A P-P 12-4 P-EL 12-5 EL-P 12-6 P-SE PD1A-D14 EL-P PS2-TEE/202-4B TEE-VLV UT AG UT AG UT AG UT AG UT AG UT AG UT AG UT AG UT AG UT AG UT AG UT AG UT AG UT AG UT AG Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable 11

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section II Scope of Inspection Attachment A Summary of Vessel Interior Examinations Examination Category B-N-1 Item B13.10, reactor vessel interior surfaces, were VT-3 examined between the closure flange and the top of the shroud over 3600 of the reactor vessel circumference. This exam is required each period. A lower steam separator alignment guide rod at 2000 was found bent similar to what was identified during D3R16 at 200. All of the upper and lower guide rod sets were examined in this scope. No other recordable indications were noted.

Examination Category B-N-2 Item B13.20, "Interior Attachments within the Beltline", Accessible Welds, were VT-1 examined as required this interval. These examinations are required to be performed once each interval. All component attachments within the beltline were examined this outage and included the upper and lower vessel metal surveillance coupon mounting brackets at all six locations and the twenty Jet Pump riser brace attachments. No recordable indications were noted at the attachment points to the reactor vessel.

The upper leaf on the Jet Pump number nine side of the riser brace to Jet Pumps nine and ten was found cracked at the block end of the leaf. This indication is discussed later in this report.

Item B13.30, "Interior Attachments beyond the Beltline", Accessible welds, were VT-3 examined as required this interval. These examinations are required to be performed once each interval. Several were performed during the third interval in outages prior to D2R1 7. The locations examined this outage included all four Steam Dryer Wall Brackets, the upper two Moisture Separator guide rod mounting lugs, and the upper and lower (four) steam dryer guide rod lug attachments.

Item B133.40, "Core Support Structures", Accessible Welds, were VT-3 examined as required this interval.

These examinations are required to be performed once each interval. Several were performed during the third interval in outages prior to D2R1 7. The locations examined this outage included the shroud vertical welds beyond the beltline region. No recordable indications were noted.

Core Spray System Examinations The Core Spray piping internal to the reactor vessel was examined using ultrasonic or EVT-1 enhanced visual inspection in accordance with BWRVIP-18, "BWR Vessels and Internals Projects, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines" under WO# 99137500-01. Previously identified cracks on welds 1 P5, 2P8a, 3P4c, 3P4d, 3P4d, 3P8a, and 4P8a were sized ultrasonically and evaluated for flaw growth. These flaws were previously evaluated after D2R15 under Sargent & Lundy Flaw Analysis SL-5197 in accordance with ASME Section XI and BWRVIP-1 8. At that time, the flaws were deemed to be acceptable for two cycles. Since D2R15 there has been no increase in flaw length on welds with demonstrated ultrasonic techniques. However, there have been changes in flaw lengths associated with flaws on undemonstrated (P8a). Specifically, the flaw at 2P8a has grown from 5.36" to 5.8" and the flaw at 4P8a, which was never visually confirmed, has been determined to be free of flaws. The flaws were again evaluated this outage in General Electric report GENE-B13-02136-00 and determined to be acceptable for another two cycles of operation. The P8a locations are of minimal concern since they do not impact the ECCS LOCA leakage analysis.

12

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section II Scope of Inspection Attachment A Summary of Vessel Interior Examinations Also, in accordance with BWRVIP-1 8, the Core Spray sparger "target weld" set identified under part 3.2.3 was inspected. The sparger was baseline inspected during D2R15. The D2R17 scope consisted of an EVT-1 of all S-1, S-2 and S-4 welds and a VT-1 of 50% of the S-3 welds and was performed under WO#

99137499-01. No indications were identified on sparger welds.

Jet Pump Examinations The current six-year inspection cycle for Jet Pump component welds specified in BWRVIP-41 began during D2R15. During the D2R16 inspections of medium priority wall brace welds, the adjacent ASME Section XI B-N-2 vessel attachment welds were also inspected for eleven of the twenty attachments. No flaws were identified at those locations. This outage, the remaining nine locations were inspected to satisfy B-N-2 requirements. There were no flaws identified on the B-N-2 attachment welds. However, a fatigue crack was identified on an adjacent weld at one upper leaf on the Jet Pump number 9 side of the 9/10 riser brace leaf to block weld (BWRVIP weld designation RB-4b) at the toe of the weld across the leaf. The eleven braces previously examined during D2R16 were then re-examined so that all twenty locations were examined this outage. In addition, a review of D2R1 4 examination records for set screw clearances identified that a gap may exist at the restrainer gates of Jet Pumps 9 and 10 and at this location only. This was of particular interest to GE since wear at set-screws of BWR3 plants had not been thought to be a potential problem. Closer examination at this location confirmed that no actual gap existed.

GE prepared an evaluation of continued operation with a wall brace only partially intact. An important conclusion of this analysis is that the failure of a wall brace is not a safety issue, but is instead an asset preservation issue. This position has previously been accepted in an SER to the BWRVIP-28 report. The GE analysis addressed recirc pump vane pass frequency (VPF) induced leaf resonance and single loop operation (SLO) flow induced vibration. Prior to D2R17, studies had been performed to assess leaf resonance during increased pump speed at end-of-cycle Extended Power Uprate (EPU) conditions.

These studies concluded that operation above 100% rated speed would not result in resonance.

However, it was also concluded that resonance could occur at speeds much lower than expected, between 70 and 80%, and recommended that restrictions be imposed over this "exclusion zone". Also, a review of original start-up testing data revealed that increased flow in the operating loop during SLO would quickly accumulate fatigue usage of a partially intact wall brace in the exclusion zone.

Recommendations for maximum speed have been in place for SLO since 1970. This test data was reviewed to evaluate the affect of running pump speeds from full rated down through the exclusion zone.

Additional mock-up testing was also performed to predict wall brace resonance with one of the four leaves failed.

13

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section II Scope of Inspection Attachment A Summary of Vessel Interior Examinations Based on the recommendations of this report, an operability evaluation was prepared that implements a method for limiting and monitoring fatigue usage. Operating procedures have been revised to restrict plant operation in these regions.

All other high and medium priority Jet Pump riser welds as required have been inspected during previous outages in accordance with BWRVIP-41. Of these welds, a single RS-1 weld on the riser to Jet Pump pair 15/16 was identified to contain a 1.5" long flaw during D2R1 5. It was evaluated at that time to be acceptable for a two cycles of operation and therefore was examined again this outage under WO#

99241679-01. There was no change in the length of this flaw since D2R15.

14

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section III Abstract of Corrective Measures The findings and subsequent measures taken to correct the findings demonstrate that all components examined are functional and in compliance with the Dresden Station ISI Program, Dresden Station Technical Requirements Manual, the ASME Boiler and Pressure Vessel Code, Section X1, 1989 Edition and 1998 Edition (implemented in accordance with Relief Request MCR-02 for Containment ISI), Generic Letter 88-01, and BWRVIP-75.

The following is a summary of corrective measures taken as a result of examination findings.

15

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section III Abstract of Corrective Measures Category Item Augment System Linie Component

_Tpe7 B-P B15.XX RR TEST BLOCK 2RC01 N/A During the D2R17 system leakage test a small number of recordable indications were discovered. CR 84257 was initiated to document discrepancies. The following recordable indications were noted and addressed per the provisions of Relief Requests PR-1 8 and PR-20 or subsequent corrective maintenance: bonnet leaks on valves 2 0203-2A, 2-0203-2B, 2-0203-2C (corrective measures under WO 99124181-14); flange leaks on control rod drives C1 0, C11, J3, and K1i5 (corrective measures in accordance with relief request PR-20); bonnet leak on pump 2-0202B (corrective measures in accordance with WO 99124181-13).

C-C C3.20 HPCIPD 2304-14 M-1151D-10 IWA While performing a MT examination, two indications were observed adjacent to one of the shear lugs. The indications exceeded the acceptance criteria of ASME Section XI Table IWB-3512-1 for surface indications. Therefore, a supplemental UT examination was performed to characterize the indications by taking pre and post UT thickness readings while performing additional surface preparation on the area in order to evaluate the indications in accordance with IWC-31 00. Upon completion of the additional surface preparation the indications had been removed. Removal was verified by performance of an as left MT. The indications were very shallow and were contributed to processing during fabrication of the piping. In accordance with IWB-3514.2 the indications were evaluated against the flaw standards for volumetric examination. Based on this evaluation the indications were well within the acceptance standards of IWC-3000 (IWB-3514). Therefore, no repair or expansion was required.

C-H C7.XX RR TEST BLOCK 2RC01 N/A During the D2R1 7 system leakage test a small number of recordable indications were discovered. CRs 84257 and 80704 were initiated to document discrepancies. The following recordable indications were noted and addressed per the provisions of Relief Request PR-18 or subsequent corrective maintenance: bonnet leak on control rod drive hydraulic control unit valves 3-0305-101 (G7), 3-0305-102(B8), 3-0305-101 (F1 1), 3-0305-120/123(C5), 3-0305 120/123(F 10), 3-0305-127(G2), 3-0305-127(C3), 3-0305-101 (K12), 3-0305-101 (P12), 3-0305-102(M10), 3-0305 127(K1 5), 3-0305-102(M2), 3-0305-120(K9), 3-0305-120(K8), 3-0305-102(H6), 3-0305-112(K3), 3-0305-112(L1 0), 3 0305-112(K12). CRD corrective measures were performed under WOs 99124181-10, 11,375020-01,375117-01, and 375119-01.

E-A E1.11 CONT N/A DW 502 LINER DW LINER During the containment general visual examination, an area that varied from two to four inches wide encompassing almost 360 degrees around the DW shell adjacent to the basement floor immediately above the moisture barrier exhibited areas of missing coating and primer resulting in corrosion of the base metal. A detailed visual exam was performed and UT thickness readings were taken in the area of the basement floor/moisture barrier. UT thickness readings demonstrated that as found degradation was well within the corrosion allowance for the drywell liner, therefore this condition is considered acceptable. Work Order 00376342 was initiated to repair the coating in this area to prevent further long term degradation. Two other areas that exhibited coating separation and rusting were at penetrations X-1 03C and X-1 15A at their associated penetration sleeve adjacent to the DW shell. A detailed visual exam was performed which revealed surface corrosion was present but no wastage was detected visually. Based upon the additional observations, these areas were considered acceptable. The conditions had WOs initiated to apply Service Level 1 coating (ref. WOs 00377187 and 00377188) in order to prevent any long term degradation which would impact the structural integrity of the containment structure. The entire drywell liner was inspected during this inspection. Therefore, no areas exist in which additional examinations could be performed.

16

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section III Abstract of Corrective Measures Cate.gory

.. Ite.*m*.. Augment System Line Component Type E-A E1.12 CONT N/A TOR B10 SUB TOR LINER During visual inspection of underwater coating in the suppression pool, an area requiring repair at location 1-1 had an identified pit depth of 104 mils. This pit exceeded 10% of the torus bottom plate thickness which is 0.653" thick. The pitting was a result of isolated coating failures exposing the base metal to suppression pool water. An evaluation of the condition was performed and found to be acceptable without further repair. This area was buffed to a bright metal finish and repair coating applied to prevent further degradation. Each refuel outage the entire under water torus coating is examined resulting in identification of similar isolated coating failures allowing pits to develop in the base metal. Visual examination of the entire underwater surface each refuel outage has identified coating deficiencies prior to the occurrence of significant base metal degradation. Evaluation of any pitting is performed and coating is repaired to ensure the structural integrity of containment is maintained. Therefore, all of the components in which this type of degradation could occur have been inspected and evaluated, and no additional examinations were performed.

E-A E1.12 CONT N/A TOR B14 SUB TOR LINER During visual inspection of underwater coating in the suppression pool, an area requiring repair at location 4-3 had an identified pit depth of 68 mils. This pit exceeded 10% of the torus bottom plate thickness which is 0.653" thick. The pitting was a result of isolated coating failures exposing the base metal to suppression pool water. An evaluation of the condition was performed and found to be acceptable without further repair. This area was buffed to a bright metal finish and repair coating applied to prevent further degradation. Each refuel outage the entire under water torus coating is examined resulting in identification of similar isolated coating failures allowing pits to develop in the base metal. Visual examination of the entire underwater surface each refuel outage has identified coating deficiencies prior to the occurrence of significant base metal degradation. Evaluation of any pitting is performed and coating is repaired to ensure the structural integrity of containment is maintained. Therefore, all of the components in which this type of degradation could occur have been inspected and evaluated, and no additional examinations were performed.

E-A E1.30 CONT N/A DW BASE MBARR MBARR During performance of the containment general visual examination, the drywell basement moisture barrier was found severely degraded and completely missing in several areas. Base metal was exposed with areas of surface corrosion present. The condition of the existing moisture barrier was unacceptable (reference CR 0079639). The existing moisture barrier was replaced under WO 99211609-01 and a detailed visual inspection was performed prior to installation of the new moisture barrier material. In addition, another detailed visual inspection was also performed along with a supplemental UT to determine the extent of corrosion to the DW shell. UT thickness readings were taken at two areas that witnessed the greatest level of corrosion. The thinnest location was at approximate azimuth of 50 degrees measured 0.968". The second location was at approximate azimuth 225 degrees and was 1.001 ",

while the adjacent metal shell not affected by any corrosion was varied in thickness of 1.03" to 1.05". Both degraded areas are within the allowable corrosion tolerance of 1/4". A visual examination was performed on the newly installed moisture and found acceptable.

F-A F1.10 RHS 0304-2.5 M-1167D-1 CL 1 SUP During VT-3 examination, a loose lock nut on the strut was discovered. Initiated CR 79613 to document discrepancy.

All adjacent supports have been expanded to and no additional supports of the same type and function exist on the system. Therefore, no further expansion is required. Support is removed each refuel outage during reactor disassembly. Lock nuts were tightened during reactor reassembly, support reinspected and found acceptable.

F-A F1.10 RHS 0304-2.5 M-1167D-2 CL 1 SUP During VT-3 examination, a loose lock nut on the strut was discovered. Initiated CR 79613 to document discrepancy.

Expanded to adjacent supports M-1 1 67D-1 and M-1 167D-3. No additional supports of the same type and function exist on the system. Therefore, no further expansion is required. Support is removed each refuel outage during reactor disassembly. Lock nuts were tightened during reactor reassembly, support reinspected and found acceptable.

17

Exelon Nuclear P.O. Box 805379, Chicago, IL 60680-5379 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 October 2001 Inservice Inspection Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Section III Abstract of Corrective Measures Category Item Augment System Line Component Type F-A F1.10 RHS 0304-2.5 M-1 167D-3 CL 1 SUP During VT-3 examination, a loose lock nut on the strut was discovered. Initiated CR 79613 to document discrepancy.

All adjacent supports have been expanded to and no additional supports of the same type and function exist on the system. Therefore, no further expansion is required. Support is removed each refuel outage during reactor disassembly. Lock nuts were tightened during reactor reassembly, support reinspected and found acceptable.

F-A F1.40 RRAS PMP 2A-0202 M-1135 SHT 13 During the initial D2R17 100% snubber inspection it was discovered that a PSA Mechanical Snubber (EPN: 2A-0202

12) exterior was covered with an affixed foreign material with concern that this material may have entered the snubber interior working mechanisms, CR 079637 was written to disposition the conditions.

The PSA-35 snubber was cleaned/removed and tested during D2R1 7 under WO 0372768-01. The snubber passed the as-found testing, but was replaced with a new snubber to alleviate any potential that the material did work it's way to the insides causing a future test failure.

18 CL 1 SNB

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section IV Abbreviations Augment GL88-01 Generic Letter 88-01 Exam, Weld Category Exam MT Magnetic Particle PT Liquid Penetrant UT Ultrasonic UT-E Ultrasonic-Risk ISI Expanded Volume VT-1, 2, or 3 Visual Examination Exam Selection AD Additional Examination (expansion)

AG Augmented Requirement BL Baseline OTHR Other SU Successive Examination XI ASME Section XI Requirement System ECCS Emergency Core Cooling System Ring Header FW Feedwater HPCI High Pressure Coolant Injection HPCIPD High Pressure Coolant Injection, Pump Discharge HPCISS High Pressure Coolant Injection, Steam Supply ISCO Isolation Condenser ISCOCR Isolation Condenser, Condensate Return ISCOSS Isolation Condenser, Steam Supply LPCIBD Low Pressure Coolant Injection "B", Pump Discharge MS Main Steam MSA Main Steam "A" MSB Main Steam "B" MSC Main Steam "C" MSD Main Steam "D" RHS Reactor Head Spray RPV Reactor Pressure Vessel RR Reactor Recirculation RVBD Reactor Vessel Bottom Drain SBLC Standby Liquid Control SDC Shutdown Cooling 19

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section IV Abbreviations SRVDA Safety Relief Valve Discharge "A" SRVDB Safety Relief Valve Discharge "B" SRVDC Safety Relief Valve Discharge "C" SRVDD Safety Relief Valve Discharge "D" SRVDE Safety Relief Valve Discharge "E" Type BELLOW Bellows BLTCONN Bolted Connection BPC Branch Pipe Connection BPCS Branch Pipe Connection Saddle CAP Pipe Cap COND Condenser CRO Cross EL Elbow ELS Elbow Longitudinal Seam F

Flued Head FLG Flange FLGBLT Flange Bolt FLS Fitting Longitudinal Seam GASKET Gasket HTEX Heat Exchanger IWA Integral Welded Attachment MBARR Moisture Barrier NIR Nozzle Inner Radius NOZ Nozzle P

Pipe PG Penetration Guide PLS Piping Longitudinal Seam PMP Pump PMPBLT Pump Bolting RED Reducer REDE Reducing Elbow RPV Reactor Pressure Vessel SDL Saddle SE Safe-end SEAL Seal SHL Shell SURF Containment Surface SWC Socket Welded Coupling SWCP Socket Welded Pipe Cap SWE Socket Welded Elbow SWF Socket Welded Flange SWP Sweep-O-Let, Weld-O-Let, Etc.

SWR Socket Welded Reducer 20

Exelon Nuclear P.O. Box 805379, Chicago, IL 60680-5379 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 October 2001 Inservice Inspection Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Section IV Abbreviations Socket Welded Tee Socket Welded Valve Tubesheet Tee Vacuum Breaker Valve Valve Bolting SWT SWV TBSHT TEE VB VLV VLVBLT 21

Exelon Nuclear October 2001 Inservice Inspection P.O. Box 805379, Chicago, IL 60680-5379 Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section V Repairs and Replacements Since the Preceding Summary Report Several ASME Section X1 repairs and replacements have taken place at Dresden Unit 2 since the previous summary report was issued. A review of the Dresden Station Section XI Repair Program Log was conducted in order to identify the various repairs and replacements. Although not required per IWA 621 0(c), Class 3 repairs and replacements are also included in this report.

Copies of the NIS-2 forms associated with all of the Section XI repairs and replacements conducted since the previous summary report have been included in this section. The NIS-2 forms provide an abstract of the repairs and replacements and outline the examinations and tests performed in conjunction with them. Code Data Reports are not included in this report, but are available for review at Dresden Station.

A listing of NIS-2 forms is included in this section in order of repair/replacement plan number followed by the associated work request number.

22

October 2001 Inservice Inspection Exelon Nuclear Unit No. 2; National Board No. N-137 P.O. Box 805379, Chicago, IL 60680-5379 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section V Repairs and Replacements Since the Preceding Summary Report L

S-No.ork Request 2-00-003 990169728-01 2-00-005 990111436-01 2-00-006 990116325-01 2-00-007 990202253-01 2-01-001 990020585-01 2-01-002 990117771-01 2-01-003 99231860 2-01-008 990232288-01 2-01-009 990014750-01 2-01-014 970110711-01 2-01-015 970110713-01 2-01-016 990051247-01 2-01-017 990051249-01 2-01-018 990063638-01 2-01-019 990111436-03 2-01-020 990116325-03 2-01-021 990062741 2-01-022 990062742 2-01-023 990062743 2-01-024 990062744 2-01-025 990253002-01 2-01-026 990231572 2-01-027 990120951-01 2-01-029 99259544 2-01-031 970072186-01 2-01-032 990269493 2-01-033 99250494 2-01-036 321079 2-01-045 99102788, 91 2-01-046 990102788 2-01-047 99248274 2-01-048 PO 23108 2-01-049 99248723 2-01-053 99235806 2-01-060 99222115 2-01-061 99222112 2-01-062 372768 2-01-063 374695 2-01-064 99117771 2-01-065 99225126 2-01-066 381568-01 2-02-001 400429-01 2-99-002 970047223-01 23

Exelon Nuclear P.O. Box 805379, Chicago, IL 60680-5379 October 2001 Inservice Inspection Unit No. 2; National Board No. N-137 Commercial Service Date: 6-9-72 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section V Repairs and Replacements Since the Preceding Summary Report NIS-2 No.

Work Request 2-99-037 2-99-038 2-99-043 2-99-054 PO 367668 PO 000239 990004356-01 990053038-01 24

FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI CATEGORY 3 S1. Owner:

ComnEd Company (Name)

One First National Plaza, Chicago IL, 60690 (Address)

2. Plant:

Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL.. 60450 (Address)

3. Work Performed By:

Same as Above (Name)

WR 99014 Repair Organ Same as Above (Address)

4. Identification of System:

1500 CCSW 5.(a)

Construction Code USAS B31.1.0-1967 19 67 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 1989 Edition, NO Addenda, Code Cases N-416-I

6. Identification of Components Repaired or Replaced and Replacement Components Date:

6-27-2000 Sheet:

1 Of 1 Unit:

2 69728-01 (PLAN 2-00-003) izaion P.O. No., Job No. etc.

Name of Name of Manufacturer Mfrs.

Nat Other Yr

Repair, Code Component Serial No.

Brd ID Bit Replaced or Stamped No Replacement Yes/No 2D CCSW Pump Discharge Not Applicable N/A N/A Line 2-1514D-10"-D N/A Repair No Flange-to-Elbow Weld

7. Description of work:

Repaired pinhole leak in weldneck flange-to-elbow weld.

8. Test Conducted:

Hydrostatic [ ]

Pneumatic [

Nominal Operating Pressure [X Not Applicable []

Test Pressure 185 psig Test Temperature 95.6 OF

9. Remarks: VT-2 examination performed during CCSW Operating Surveillance DOS 1500-02 on 6/10/2000: No leakage observed.

Certificate of Compliance We certify tt the statements made in this report are correct and this REPAIR Conforms to Section XI of the ASME Code.

Signed:

(Ower o d 's ISI COORDINATOR (Tit17 2ooce (Owner or Owndts Designee) I (Tide)

(Date)

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 Ulinois, epployed by The Hartford Steam and Boiler Insurance and Inspection Co. of Hartford, Connecticut having inspected the REPAIR described in this report on 20._O and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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: 0 7ý Inspector:

eý Commissions:

1L932, NB7742NISB DAP 11-18 REVISION 08

=

I I

k*o--l or V-UUI[ 1, 0t~~l~

_-ad)

I v

I

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

Date:

11-02-2001 P.O. Box 805379. Chicago IL, 60680-5379 (Address)

Sheet:

1 Of 1

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL., 60450 (Address)

Unit:

2 "3.

Work Performed By:

G.N. Venture (Name)

WO 99111436-01 PLAN 2-00-005 Same as Above (Address)

Repair Organization P.O. No., Job No. etc.

4. Identification of System:

1500 (LPCI)

5. (a) Construction Code ASME Sect.III 1965 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section Xl used for Repair/Replacement 19 89. Edition, -NO Addenda, Code Cases N-41 6-1

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

-Nat-Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No 2A CCSW/LPCI Hx Tubes.

Unknown for the Unknown N/A EPN: 2-1503A N/A Repair/Replaced No tubes.

Tube Plugs for 34" tube X Thomas Wilson None identified N/A Cat ID-27487, UTC-N/A Installed to Repair No 15-22 Gauge Tube( 10 2402007,2003730.

plugs).

7. Description of work: Based upon eddy current results. repaired tubes by Plugging (10 tubes plugged). No tubes were replaced.

8. Test Conducted: Hydrostatic [ X ]

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [1 Test Pressure 375 psig Test Temperature 75.2 OF

9. Remarks: No leakage identified by VT-2 during pressurization on 10/31/01.

Certificate of Compliance We certify that the statements made'i this rport are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed: John H. Young ISI COORDINATOR

_____,Jan.15., 2002 (Owner or Owne s Desi nee)

(Title)

(Date)

Certificate of Inspection h

rf 1, the undersigned holding a valid commission issued by the National Board of Boiler and rressure vei.0

,1-'.'..

....l..,,

Illinois, employed by Hartford Steam Boiler of CT having inspected the REPA..IREPLACEMENT described in this report on and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this 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: /

,/'

)

Inspector: Robert T. Raine

-A.

Commissions:

1L932. NB7742N]SB (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

G.N. Venture (Name)

Same as Above (Addn

4. Identification of System:

1500 (LPCI)

5. (a) Construction Code ASME Sect.Ill (b) Edition of Section X1 used for Repair/Replacement WO) 99116325-01 Date:

11-2-2001 Sheet: 1 Of 1 Unit:

2 PLAN 2-00-006 Repair Organization P.O. No., Job No. etc.

1965 Edition, NO Addenda, Code Cases NONE 19 89 Edition, NO

Addenda, Code Cases N-416-1

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No 2B CCSW/LPCI Hx Tubes.

Unknown for the Unknown N/A EPN: 2-1503B N/A Repair/Replaced No tubes.

Tube Plugs for 3/*" tube X Thomas Wilson None identified N/A Cat ID-27487, UTC-N/A Installed to Repair No 15-22 Gauge Tube (50 2402007 plugs).

1 3/4-X 18 BWG ASME SB-Unknown None identified N/A Cat ID-42456, N/A Replacement No 111 Tubes ( 55 tubes ).

UTC's-2622489, 2622573

7. Description of worklBased upon eddy current results, repaired tubes by plugging (50 tubes plugged) or replaced tubes with new tubes (55 tubes replaced).

A hydro of the tube sheets was performed prior to reassembling the Hx with no leakage observed..

8. Test Conducted: Hydrostatic [ X ]

Pneumatic [ ]

Nominal Operating Pressure [

Not Applicable [1 Test Pressure 436 psig Test Temperature 84 OF

9. Remarks: No leakage identified by VT-2 during pressurization on 10/31/01.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section Xl of the ASME Code.

Signed:

SI COORDINATOR

_____Jan.12 2002 (Owner or O4ner's Dsignee)

(Title)

(Date)

Certificate of Inspectio c

I, the undersigned, holding a valid commission issued by the National Board of Boi r and Pressure Vessel inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance andnspection

. of Hartford, Connecticut having inspected the REPAIIR/EPLACEMENT described in this report on

/-

.20i.Zk'nd state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with ection Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any pe.onal injury or property damage or a loss of any kind arising from or connected with this inspection.

UdL

.*I...(

/9Ino toi~r:

/Z

-,-A~

I Commissions:

11-932.

NBT742NISB (State or Province, National Board)

LAIM:

V--

I

FORM NIS-2 OWNER'S REPORT OF REPAIR OR REPLACEMENT As Required by the Provisions of ASME Code Section XI CATEGORY 3

1. Owner:

ComnEd Company (Name)

One First National Plaza, Chicago IL, 60690 (Address)

2. Plant:

Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

1500 CCSW/LPCI 5.(a)

Construction Code ASME Section IM 19 65 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section XM used for Repair/Replacement 19"-8

Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components j _________________

I _____

I _________________

Date:

9-13-2000 Sheet:

1 Of 1 Unit:

2 WR 990202253-01(PLAN 2-00-007)

Repair Organization P.O. No., Job No. etc.

7. Description of work: Chemistry testing results discovered tube leak on 2B CCSW/LPCI heat exchanger. Heat exchanger was disassembled and tubes were pressure tested and select tubes were eddy current tested. Seven tubes were pluhged based on pressure test and eddy current results.

8. Test Conducted:

Hydrostatic [

Pneumatic [ I Nominal Operating Pressure [ ]

Not Applicable [X]

Test Pressure N/A psig Test Temperature N/A OF

9. Remarks: Exempt from hydrostatic testing per IWA-4700(b)(2). Maintenance pressure test was performed to verify no leakage at newly installed tubes (no leakage observed).

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR conforms to Section XI of the ASME Code.

Signed (Owner____

or Ow

_i COORDINATOR

-D13 wt0 (One o wnt' Dsgne)/(Title)

(Date)

DAP 11-18 REVISION 08 Name of Name of Manufacturer Mfrs.

Nat Other Yr

Repair, Code Component Serial No.

Brd ID BIt Replaced or Stamped No Replacement Yes/No 2B CCSW/LPCI Heat Not Identified Unknown N/A Inlet: 20-9,22-14 N/A Repair No Exchanger Tubes (Inlet Tube Numbers 20-9 and 22-14, Outlet: 2-24, 30-3, Outlet Tubes 2-24, 30-3, 16-16-25, 8-20, 17-10 25, 8-20, and 17-10) 14 Heat Exchanger Tube Unknown Unknown N/A Catalog ID 27487 N/A Replacement No Plugs j _____

I II I

I

.1.

I 4

4 t

T 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 III is, e nloed by T*Hartford Steam and Boiler Insurance and Inspection Co. of Hartford, Connecticut having inspected the REPAIR described in this report on.1 -Z/

20j!)nd state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section )U of the ASME Code. ely sig ghthis certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employe 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:

'/'

Inspector: ___

Commissions:

1L932, NB7742NISB

, ""(State or Province, National Board)

J1

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

1400 (Core Spray)

5. (a) Construction Code USAS B31.1-0/ASME Sect.VIII, (b)

Edition of Section XI used for Repair/Replacement WC* QQA~flFR*-nl1 Date:

10-22-2001 Sheet: 1 Of 1

Unit:

2 pl AN %fl-f1-1(l Repair Organization P.O. No., Job No. etc.

1967/65 Edition, NO Addenda, Code Cases NONE 1989 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Relief valve at EPN Consolidated 252336-1-EJ N/A None Unknown Replaced No 2-1402-28B Relief valve at EPN Consolidated-TC25708 N/A Cat ID-0041 80, Unknown Replacement No 2-1402-28B Dresser UTC-2066269, P/N:

191 OHC-1 -XMC368.

7. Description of work: Replace the flanged relief valve with a new/refurbished one.

8. Test Conducted: Hydrostatic [

Pneumatic [ ]

Nominal Operating Pressure [X ]

Not Applicable []

Test Pressure 390 psig Test Temperature 84 OF

9. Remarks: Satisfactory VT-2 performed.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIRIREPLACEMENT Conforms to Section XI of the ASME Code.

Signed:

ISI COORDINATOR Jan.11

, 2002 (Owner or-Wer's D ignee)

(Title)

(Date)

Certificate of Inspection,*/ *7 I, the undersigned, holding a valid commission issued by the National Board of Boil dressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insuranceai Inspection Co.of Hartford, Connecticut having inspected the..

REPAIR/REPLACEMENT described in this report on

/-

L, 20 e'2-and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or propery damage or a loss of any kind arising from or connected with this inspection.

Date:

i

/f

'*lnspector:

,*Z Commissions:

1L932, NB7742NISB 11 tz*Taie or Pr-roire, Nan u*

Dow ul

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

General Electric (Name)

Same as Above (Address)

4. Identification of System:

0200 Reactor Pressure Vessel IA(l 001 17771-ni1 Date:

11-4-2001 Sheet:

1 Of 1 Unit:

2 P1 AN 2-01-002

5. (a)

Construction Code ASME Sect.Ill 1965 Edition, NO Addenda, Code Cases 1335 (b)

Edition of Section XI used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Reactor Pressure Vessel Head Closure Studs (SA 320 Grade L42 and Code Case 1335, five total.

Reactor Pressure Vessel Head Closure Studs (SA 320 Grade L42 and Code Case 1335, five total.

ame ur kM,-.

TNI,tf flther T Year r

ReDair.

I Code ID Built Replaced or Stamped Manufacturer Serial No.

Brd KI, Replaced or Replacement I

I L.

Not recorded N/A Stud Position N/A Replaced Babcock and Wilcox Stud Position Numbers 68, 69, 70, 71, and 72.

I__

i 4 -

-t I

I I

F I

I N/A Cat ID-38457, WOs:

N/A Replacement No Babcock and Wilcox 61-111-68, 69, 70,71, & 72.

Cat ID-38457, WO's:

99052144-01 &

99126507-01.

I ____________________________ I I - I I

1 1

I i

i i

_________________ 1 4 -1 1

• I I

I__

_4_

Stamped Yes/No

7. Description of work: Remove/reinstall with rotated stock, the five "cattle chute" related Rx studs.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [ I Nominal Operating Pressure [ ]

Not Applicable [ X]

Test Pressure _

psig Test Temperature __ OF

9. Remarks: The Replacement Rx studs came from D3R16 under WO 99052144-01. They were deconed/cleaned/NDE performed under WO 99126507-01 and staged back on the refuel floor for D2R1 7.

SCertificate of Compliance We certify that.the statements made in this rep rt are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed John H. Youn ISI COORDINATOR Jan.12__

, 2002 (owner or Owner's Designlee)

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the S te r Province of Illinois, employed by Hartford Steam Boiler of CT having inspected the REPAmR/REPLACEMENT described in this report on

/o the

, 20C 7-*e.2B and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section % of the ASME Cede. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this 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:

e,,

Inspector: RobertT. Rainey ZI Commissions:

1L932, NB7742NISB I,/

(State or Province, National Board)

Repair Organization P.O. No., Job No. etc.

L ID Built Replaced No N/A N/A Not recorded N/A Replacement No N/A

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XM

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station

- (Name) 6500 North Dresden Road. Morris IL., 60450 (Address)

3. Work Performed By: Same as Above (Name)

Same as Above (Address)

4. Identification of System:

1500 (CCSW/LPCI)

5. (a)

Construction Code USAS B31.1-0 (b)

Edition of Section XA used for Repair/Replacement Date:

11-5-2001 Sheet: 1 Of 3 Unit:

2 DCP 9900395/WO 99231860/PLAN 2-01-003 Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO Addenda, Code Cases NONE 1989 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Pipe line 2-1558A-2"-D.

Unknown None N/A Associated with Hx N/A Replaced No 2-1503-A.

Pipe line 2-1558A-2"-D, Unknown HT#-720254 N/A Cat. ID-24507, UTC-N/A Replacement No pipe sch.80.

2066926.

Pipe line 2-1558A-2"-D, Unknown Not Recorded N/A Cat ID-7480, UTC-N/A Replacement No flange set, 2" s.w., 3001b.

2600427.

5/8"-1 1 threaded rod for Unknown Not Recorded N/A Cat ID-39725, UTC-N/A Replacement No flange set on 2-1558A-2"-

2616440.

D.

5/8"-11 heavy hex nuts for Unknown Not Recorded N/A Cat ID-37029, UTC-N/A Replacement No flange set on 2-1558A-2"-

2005510.

D.H

7. Description of work:Replaced existing globe valves win gaie vaives da.UndJUu ijui ing tu,,"...

1LrA~Mr U-~

A 2 l Task 06.

07f nH Task 01 02 2

8. Test Conducted: Hydrostatic[]

Pneumatic Nominal Operating Pressure [X]

Not Applicable []

Test Pressure

• • - psig Test Temperature Ambient OF

9. Remarks:***227 psiq on 2-1558A-2" and 221 psigq on 2-15588-2" poertion of piping. A VT-2 was performed dudrin DOS 1500-12 for both affected trains.

Other than a packing leak noted on valve 2-1599-65B. no leakaae was detected.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XA of the ASME Code.

Signed: _

ISI COORDINATOR 20YZI (Owner br OwnerV s Designee)

(Title)

(Date)

Certificate of Inspection

/

, the undersigned, holding a valid commission issued by the National Board of Boi1..and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance n Ins Co.

of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on

,L.

20 n state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or prop damage or a loss of any kind arising from or connected with this inspection.

Date: 1 Inspector:

Commissions:

1L932, NB7742NISB (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL. 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By: Same as Above (Name)

DCP 9900395/WO 99 Same as Above (Address)

Repair Organization F

4. Identification of System:

1500 (CCSW/LPCI)

5. (a) Construction Code USAS B31.1-0 19 67 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section Xl used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE Date:

11-5-2001 Sheet: 2 Of 3 Unit:

2 231860/PLAN 2-01-003

".0. No., Job No. etc.

Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped 1_

._I_

No Replacement Yes/No 2" X 1" s.w. reducing insert Unknown None N/A Une #2-1558A-2" N/A Replaced No on pipe 2-1558A-2"-D.

2" X 1" s.w. 3000 psi, Unknown HT#021 J N/A Cat 11-38510, UTC-N/A Replacement No reducing insert.

2615426.

2" s.w. tee on pipe line 2-Unknown None N/A Une # 2-1558A-2" N/A Replaced No 1558A-2"-D.

2" s.w. 3000 psi, tee.

Unknown Not Recorded N/A Cat 11-7361, UTC-N/A Replacement No 2018116.

1 2" s.w. globe valve 2-1599-Hancock Model 5500W1 N/A EPN: 2-1599-65A N/A Replaced No 65A.

2" s.w. c1800 gate valve 2-Vogt Model N/A Cat ID-412907, N/A Replacement No 1599-65A.

SW12111 2" UTC-2602417.

Pipe line 2-1558B-2"-D.

Unknown None N/A Associated with Hx N/A Replaced No 2-1503-B.

Pipe line 2-1558B-2"-D, Unknown HT#-720254 N/A Cat 11-24507, UTC-N/A Replacement No pipe sch.80.

2066926.

Pipe line 2-1558B-2"-D, Unknown Not Recorded N/A Cat 1-7480, UTC-N/A Replacement No flange set, 2" s.w., 3001b.

2600427.

5/8"-11 threaded rod for Unknown None N/A Cat ID-39725, UTC-N/A Replacement No flange set on 2-1558B-2"-

2616440.

D.

5/8"-11 heavy hex nuts for Unknown HT#021J N/A Cat ID-37029, UTC-N/A Replacement No flange set on 2-1558B-2"-

2005510.

D.

2" X 1" s.w. reducing insert Unknown None N/A Line #2-1558B-2" N/A Replaced No on pipe 2-1558B-2"-D.

2" X 1" s.w. 3000 psi, Unknown HT#021J N/A Cat ID-38510, UTC-N/A Replacement No reducing insert.

2615426.

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Add

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Ad(

3. Work Performed By:

Same as Above (Name Same as Above (Addr

4. Identification of System:

1500 (CCSW/LPCI)

5. (a) Construction Code USAS B31.1-0 (b)

Edition of Section XI used for Repair/Replacement Date:

11-5-2001 Sheet: 3 Of 3 Unit:

2 DCP 9900395/WO 99231860/PLAN 2-01-003 Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO Addenda, Code Cases NONE 198_9 Edition, NO Addenda, Code Cases NONE Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No 2" s.w. tee on pipe line 2-Unknown None N/A Line # 2-1558B-2" N/A Replaced No 1558B-2"-D.

2" s.w. 3000 psi, tee.

Unknown Not Recorded N/A Cat ID-7361, UTC-N/A Replacement No 2018116.

2" s.w. globe valve 2-1599-Hancock Model 5500W1 N/A EPN: 2-1599-65B N/A Replaced No 65B.

2" s.w. c1 800 gate valve 2-Vogt Model N/A Cat ID-412907, N/A Replacement No 1599-65B.

SW12111 2" UTC-2602417.

I

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

'1 1 Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL., 60450 (Address)

3. Work Performed By: Same as Above (Name)

Same as Above (Address)

Date:

11-4-2001 Sheet: 1 Of 1 Unit:

2 DCP g900514 W/O 99232288 (PLAN 2-01-008)

4. Identification of System:

2500 (ACAD)

5. (a) -Construclon Code ASME Section III 1974 Edition, Summer1976 Addenda, Code Cases NONE (b) Edition of Section Xl used for Repair/Replacement 19 98* Edition NO Addenda, Code Cases NONE "1998 Edition implemented in accordance with Relief Request MCR-02

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped "No.

Replacement Yes/No Cap on line 2-2502A-1" Unknown None N/A Cat ID 38871 Unknown Replacement No through Containment Penetration X-202V Cap on line 2-2502B-1" Unkndwn None N/A Cat ID 3887.1 Unknown Replacement No through Containment Penetration X-204B Cap on line 2-2503A-1" Unknown None N/A Cat ID 38871 Unknown Replacement No through Containment Penetration X-316A Cap on line 2-2503B-1" Unknown None N/A Cat ID 38871 Unknown Replacement No through Containment Penetration X-316B Cap on line 2-2504-1" Unknown None N/A Cat ID 38871 Unknown Replacement No through Containment Penetration X-125

7. Description of work: Removed ACAD system, cut and capned lines at containment Penetrations.

8. Test Conducted: Hydrostatic []

Pneumatic [X]

Nominal Operating Pressure [

Not Applicable []

Test Pressure 49.5 psig Test Temperature Ambient OF

9. Remarks: Pneumatic test performed in accordance with 10 CFR 50 Appendix J and ASME Section XI IWE-5240 SCertfct of Compliance We certify that the statements made in this report are correct and this REPAIRcREPLACEMENT Conforms to Section XI of the ASME Code.

Signed:

g n

e d-IS COORDINATOR 1/i 202..L.

g 5or Owner's Designee)

(Title)

(Date)

)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurapce 9 Ins pecton Co. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on L and state to th best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this report Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or p damage or a loss of any kind arising from or connected with this inspection.

i

-/

nnr Commissions:

1932. NB7742NISB I

I Repair Organization P.O. No., Job No. etc.

udud:

(State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

WO 99014750-01 Date:

10-24-2001 Sheet: 1 Of 1 Unit:

2 PLAN 2-01-009

4. Identification of System:

2300 (High Pressure Coolant In

5. (a)

Construction Code USAS B31.1-0 (b)

Edition of Section XI used for Repair/Replacement 19 67 Edition, NO Addenda, Code Cases NONE 19 89 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components 4,

, _______

I ___

L ____

a ________

'7. Description of work: Replace the flanged relief valve with a new/refurbished one.

8. Test Conducted: Hydrostatic []

Pneumatic [ ] -Nominal Operating Pressure [ X ]

Not Applicable[

Test Pressure 60 psig Test Temperature Ambient OF

9. Remarks: Satisfactory VT-2 performed.

I Certificate of Compliance We cerlify that the statement; made in this report are correct and this REPAIRIREPLACEMENT Conforms to Section Xl of the ASME Code.

signed ISI COORDINATOR

_____Jan.11_

2002 LI er ort er's Des gnee)

(Title)

(Date)

Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Relief valve at EPN Consolidated-TC41364 N/A P/N: 1905-30 PC/SP N/A Replaced No 2-2301-53 Dresser Relief valve at EPN Consolidated-TL96055 N/A Cat ID-46883, UTC-N/A Replacement Yes 2-2301-53 Dresser 2056244, P/N:

1905NC-2-1 A MC324.

t 1

1 r

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler InsuranceA,,d Inspection Co. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on

/*-

, 2.

rand state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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: A,'

Inspector:

-A a" T: zCommissions:

IL932.NB7742NSB (State or Province, National Board)

Repair Organization P.O. No., Job No. etc.

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

1500 (Low Pressure Coolant Iniection)

5. (a) Construction Code ASME Sect.VIII, (b)

Edition of Section Xl used for Repair/Replacement WO g71113711-O1 Date:

10-22-2001 Sheet:

1 Of 1 Unit:

2 P1 AN ;)-131-f14 Repair Organization P.O. No., Job No. etc.

1965 Edition, NO Addenda, Code Cases NONE 1989 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components

7. Description of work: Replace the flanged relief valve with a new/refurbished one.

8. Test Conducted:

Hydrostatic [

Pneumatic [ ]

Nominal Operating Pressure [ X ]

Not Applicable [1 Test Pressure "7 psig Test Temperature Ambient OF

9. Remarks: Satisfactory VT-2 performed.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIRIREPLACEMENT Conforms to Section XI of the ASME Code.

Signed:

ISI COORDINATOR Jan. 11 2002_

.(Owner or es ignee)

(Title)

(Date)

Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Relief valve at EPN Consolidated-TF74326 N/A P/N: 1905FC N/A Replaced No 2-1599-13C Dresser XYM19.

Relief valve at EPN Consolidated-TM67812 N/A Cat ID44534, UTC-N/A Replacement No 2-1599-13C Dresser 2622132, P/N:

1905F-XLA2 NC3155.

4

+

t--t t

I I

1-t T1 T

F F

1-t TT T

F F

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insure,*l Inspecti.q Co. of Hartford, Connecticut having inspected the REPAIRIREPLACEM ENT described in this report on

,-/,

20__"--and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personalsjury or property dage or a loss of any kind arising from or connected with this inspection.

Date: k/di 'I2*-

Inspector:

/F/

(,,

f/,- kt-4'<7 Commissions:

1L932, NB7742NISB (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicaqo IL, 60680-5379 (Addi

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL.. 60450 (Adc

3. Work Performed By:

Same as Above (Name Same as Above (Addr

4. Identification of System:

1500 (Low Pressure Coolant Ini

5. (a) Construction Code ASME Sect.VIII, (b) Edition of Section Xl used for Repair/Replacement Date:

10-22-2001 Sheet:

1 Of 1 Unit:

2 WO 97110713-01 PLAN 2-01-015 Repair Organization P.O. No., Job No. etc.

19 65 Edition, NO Addenda, Code Cases NONE 1989 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Relief valve at EPN 2-1599-13D Relief valve at EPN 2-1599-13D Name OT I



lkI...4 (Mhn,'

r Vr T

Renair.

f Code Replaced or Stamped Name of Manufacturer Consolidated Dresser Consolidated Dresser Serial No.

TK52699 Brd Nkrý N/A P/N: 1905FC N/A i-replacea ID P/N: 1905FC-1 XMC368.

Built

.J.

1 4

I t

N/A Cat ID-44534, UTC-N/A Replacement No TM67809 Cat ID-44534, UTC 2622130, P/N:

1905F-XLA2 NC3155.

Replaced or Replacement I _______

I.

I.

F I

I 4

4 I

I I

I 4-I I

t I

.1 4 -I Ct1 Stamped Yes/No

.1



.1 1 _______________

7. Description of work:

Repace the flanqed relief valve with a new/refurbished one.

8. Test Conducted: Hydrostatic [

Pneumatic [ ]

Nominal Operating Pressure [ X ]

Not Applicable[

Test Pressure 7_ psig Test Temperature Ambient OF

9. Remarks: Satisfactory VT-2 performed.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIRIREPLACEMENT Conforms to Section XI of the ASME Code.

signed:

IS COORDINATOR

_____Jan.1 1-,

2002 (Owner or 0 er's Desig ýee)

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler insurance anr-nspection C;. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on

&,20D -and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this 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:

Inspector:

(

Commissions:

1-932. NB7742Nal B (State or Province, National Board)

Replaced INo N/A N/A N/A Replacement No N/A

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI S1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL.. 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

W0 99051247-01 Date:

10-31-2001 Sheet: 1 Of 1

Unit:

2 PLAN 2-01-016

4. Identification of System:

0203 (Main Steam)

5. (a)

Construction Code **ASME Section III 19 65 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 19 8-9 Edition, NO Addenda, Code Cases NONE General Electric APED Specification 21A5744.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Electromatic Relief Valve at Dresser Industries S/N: BK7002 N/A Type 1525VX Unknown Replaced Yes EPN: 2-0203-3B.

Electromatic Relief Valve to Dresser Industries S/N: BK7079 N/A Cat ID-42845, UTC-Unknown Replacement Yes EPN: 2-0203-3B.

2622214

7. Description of work: Removed exdsting ERV and replaced with a rebuilt spare ERV..

9. Test Conducted: Hydrostatic [(]

Pneumatic [

Nominal Operating Pressure ]

Not Applicable []

Test Pressure 1005 psig Test Temperature > 135 /<212 *F

9. Remarks: Satisfactory VT-2 examination was recorded during the D2R17 10 Yr Hydro under WO 99124181-09.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section Xi of the ASME Code.

Signed:

-IS COORDINATOR

_____Jan.08_ 2002_

(Owner or Owner' Designe)

(Title)

(Date)

I, the undersigned, holding a valid commission issued by the National Board of Bo3i and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance I insp n Co. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on r-"L" 20_

I d state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal inju or property damage or a loss of any kind arising from or connected with this inspection.

Date:

Inspector.

/*/,"

/ 7 i%-,

Commissions:

,L932, NB7742NISB (State or Province, National Board)

Repair Organization P.O. No., Job No. etc.

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI 1: Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

0203 (Main Steam)

Wfl Q*R~l19A-n1 Date:

10-30-2001 Sheet: 1 Of 1 Unit:

2 Pl AN 2-01-017

5. (a) Construction Code **ASME Section III

, 19.65 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE

• • General Electric APED Specification 21A5744.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Electromatic Relief Valve at Dresser Industries S/N: BK7053 N/A Type 1525VX Unknown Replaced Yes EPN: 2-0203-3D.

Electromatic Relief Valve to Dresser Industries S/N: BK7050 N/A Cat ID-42845, UTC-Unknown Replacement Yes EPN: 2-0203-3D.

2622215

7. Description of work: Removed existing ERV and replaced with a rebuilt spare ERV..

S. Test Conducted: Hydrostatic DO Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [1 Test Pressure 1005 psig Test Temperature > 135/<212 OF

9. Remarks: Satisfactory VT-2 examination was recorded during the D2R17 10 Yr Hvdro under WO 99124181-09.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XA of the ASME Code.

Signed:

4!

ISI COORDINATOR

____Jan.0-2002 lOwner or*0Wners Desgnee)

(Title)

(Date)

I, the undersigned, holding a valid commission issued by the National Boar of BiadPreure Vessel.Inspectors a tState or Provinoe of Illinois, employed by The Hartford Steam and Boiler lnsuranc4 grid lnspectign

. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on I-In 20LA-u.ed state to the best of my knowledge and belief, this repair or replacement bas been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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:

Inspector:

.irý &

Commissions:

IL932, NB7742NISB (State or Province, National Board)

Ql 99051249-.

Repair Organization P.O. No., Job No. etc.

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Add

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL.. 60450 (Ad(

3. Work Performed By:

Same as Above (Name Same as Above (Addr

4. Identification of System:

8500 (N2 Inertinq and D/W 02

5. (a) Construction Code USAS B31.1-0 (b)

Edition of Section XI used for Repair/Replacement frneoor Date:

10-26-2001 Sheet:

1 Of 1 Unit:

2 WO 99063638-01 PLAN 2-01 -018 Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO Addenda, Code Cases NONE 1998* Edition, NO Addenda, Code Cases NONE

""1998 Edition implemented in accordance with ReliefR cequesn Mdle-l-C

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Relief valve at EPN 2-8526.

Relief valve at EPN 2-8526.

Name 01 1

.'-.-

T KI.* C r.*+

f Vnar 1

Renair.

T Code Replaced or Serial No.

Stamped Name of Manufacturer I Inln.ulwn Stamped Yes/No I_'rH I

tI I

N/A Not recorded

4.

t t

I N/A N/A Replacement Cat ID-35597 NO TG 13751 1 ~-1

1.

1-1 t

1.

I-4.

I t

r 1

4.

1 1

1 1

4-4 1

1 I

Brd Mn ID Built Replaced or Replacement

._ I

4.

I-i 1

.1 4-4 1

1 1

I I ______

' __

I ________

7. Description of work: Replace the flanged relief valve with a new/refurbished one. Replaced relief valve will be tested under WO 99229335-01..

8. Test Conducted: Hydrostatic [ ]

Pneumatic [X]

Nominal Operating Pressure [ ]

Not Applicable []

Test Pressure 50 psig Test Temperature Ambient OF

9. Remarks: Pneumatic test performed in accordance with 10 CFR 50 Appendix J and ASME Section XI IWE-5240.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section Xl of the ASME Code.

Signed:

ý jk

/

ISI COORDINATOR Jan.11

,2002 "or (Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Bojlj arn/Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurancea Inspection Co. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report onr 2002en state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance wit Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any persoal injuy or property damage or a loss of any kind arising from or connected with this inspection.

Dt. e

.*I*nspector:

/4(1'

//*

Commissions:

1L932. NB7742NISB ate:.-

(State or Province, National Board)

MI[il..

Serial No.

R~eplaced No N/A None No N/A Replacement N/A Cat ID-35597

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL.. 60450 (Address)

3. Work Performed By:

G.N. Venture (Name)

Same as Above (Address)

Wn QQ1 11436-03 Date:

10-28-2001 Sheet:

1 Of 1 Unit:

2 PLAN 2-01 -019

4. Identification of System:

1500 (LPCI)

5. (a)

Construction Code ASME Sect.lll 1965 Edition, NO Addenda, Code Cases NONE (b) Edition of Section XI used for Repair/Replacement 19 8_9 Edition, NO Addenda, Code Cases N-416-1

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No 2A CCSW/LPCl Hx Upper Unknown for the 05036-3 3006 EPN: 2-1503A 1967 Repair Yes and Lower Channels.

tubes.

7. Description of work: Weld repair/qrind/blend pitted areas on upper and lower channels on 2A CCSW/LPCl Hx during maintenance.

8. Test Conducted: Hydrostatic ]

Pneumatic [ ]

Nominal Operating Pressure [ X ]

Not Applicable [1 Test Pressure 227 psig Test Temperature Ambient OF

9. Remarks: No leakage identified by VT-2 during DOS 1500-12 on 10/31/01.

Certificate of Compliance We certify that the s temen m

e in this report are correct and this REPAIRIREPLACEMENT Conforms to Section Xl of the ASME Code.

Signed (IS COORDINATOR o

e eg)an.1t1e 2002 (owner or Owner s Desigre)

(Title)

(Date)

Certificate of Inspectio* *,

I, the undersigned, holding a valid commission issued by the National Board of o and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insu a d Inspecti*o

..of Harord, Connecticut having insptedte REPAIR/REPLACEMENT described in this report on 20d Bl-state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any pe,~onaJ injury or property/oamage or a loss of any kind arising from or connected with this inspection.

Date:

/

Inspector L,4 t

/

Commissions:

1L932.

NB7742NISB (State or Province, National Board)

Repair Organization P.O. No., Job No. etc.

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

G.N. Venture (Name)

Same as Above (Address)

WO 99116325-03 Date:

11-01-2001 Sheet: 1 Of 1 Unit:

2 PLAN 2-01-020 Repair Organization P.O. No., Job No. etc.

4. Identification of System:

1500 (LPCI)

5. (a) Construction Code ASME Sect.Ill 1965 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 19789 Edition, NO Addenda, Code Cases N-416-1

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No 2B CCSW/LPCI Hx Upper Unknown for the 05036-4 3007 EPN: 2-1503B 1967 Repair Yes and Lower Channels.

tubes.

7. Description of work: Weld repair/grind/blend pitted areas on upper and lower channels on 2B CCSW/LPCI Hx during maintenance.

8. Test Conducted: Hydrostatic [

Pneumatic [ ]

Nominal Operating Pressure [ X ]

Not Applicable[

Test Pressure 221 psig Test Temperature Ambient OF

9. Remarks: No leakage identified by VT-2 during DOS 1500-12 on 11/5/01.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section Xl of the ASME Code.

Signed: John H. Young ISI COORDINATOR

_Jan.15-2002 (Owner or 0 uer's Deal nee)

(Title)

(Date)

Certificate of Inspection 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the Stae or Province of Illinois, employed by Hartford Steam Boiler of CT having inspected the REPAIRIREPLACEMENT described in this report on.

,/'"/., 20..Ai and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date: / -".9)Th-nspector: Robert T. Rainey Commissions:

IL932, NB7742NISB (State or Province, National Board)

I

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

WAIC OOAR*7Al -A Date:

10-28-2001 Sheet: 1 Of 1 Unit:

2 Pl AN :>-A1-fl*1 Repair Organization P.O. No., Job No. etc.

4. Identification of System:

0203 (Main Steam)

5. (a) Construction Code **ASME Section III

,1965 Edition, S/66 Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE

• • General Electric APED Specification 21A5743, rev.1.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Consolidated Safety Valve Consolidated S/N: BK6299 N/A Model: 3777-QA-RT-Unknown Replaced Yes at EPN: 2-020X3-4A.

21-OS110 Consolidated Safety Valve Consolidated S/N: BK6527 N/A Cat ID-30366, UTC-Unknown Replacement Yes at EPN: 2-0203-4A.

2065265

7. Description of' r,....==t =,i~tinn *a."*ftv valve and replaced with a rebuilt/tested spare safety valve.

8. Test Conducted: Hydrostatic [ X I Pneumatic [ ]

Nominal Operating Pressure [ I Not Applicable [ ]

Test Pressure 1o.._ psig Test Temperature > 135 /<212 OF

9. Remarks: Satisfactory VT-2 examination was recorded during the D2R1 7 10 Yr Hydro under WO 99124181-09.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIRMREPLACEMENT Conforms to Section XI of the ASME Code.

Signed:

ISI COORDINATOR

_Jan.09

, 2002 (Owner or Owner's [esignee)

(TAtie)

(Date)

Certificate of Inspection* / c_.

1, the undersigned, holding a valid commission issued by the National Board of Boil, ad Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler lnsu and Inspection Co. of Hartford, Connecticut having inspected the REPAIRsREPLACEM ENT described in this report on rafc-,

204_---and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury92 property damage r a loss of any kind arising from or connected with this inspection.

Date:

'e9 Inspector:

,° ii" A

J/

Commissions:

1-932e, NBT742NISB (State or Province, National Board)

A, 0

,' -)dstn

-fp-tv valve and reolaced with a rebuilt/tested spare safety valve.

WO Z2

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By: Same as Above (Name)

Same as Above (Address)

4. Identification of System:

0203 (Main Steam)

Wfl qgnn74P-n1 Date:

10-28-2001 Sheet: 1 Of 1 Unit:

2 pl AN *'-fl1 -nP Repair Organization P.O. No., Job No. etc.

5. (a) Construction Code **ASME Section III

,1965 Edition, S/66 Addenda, Code Cases NONE (b) Edition of Section Xl used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE

• • General Electric APED Specification 21A5743, rev.1.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Consolidated Safety Valve Consolidated SIN: BK6263 N/A Model: 3777-QA-RT-Unknown Replaced Yes at EPN: 2-0203-4B.

21-0S110 Consolidated Safety Valve Consolidated S/N: BK7162 N/A Cat ID-30446, UTC-Unknown Replacement Yes at EPN: 2-0203-4B.

2065262 I

I I

t

l*

1 I ____________

I _________

n ______

7. Description of work: Removed existing safety valve and replaced with a rebuilt/tested spare safety valve.

8. Test Conducted: Hydrostatic [ X ]

Pneumatic [ ]

Nominal Operating Pressure I ]

Not Applicable[

Test Pressure 1005 psig Test Temperature > 135 / <212 OF

9. Remarks: Satisfactory VT-2 examination was recorded during the D2R1 7 10 Yr Hydro under WO 99124181-09.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section Xl of the ASME Code.

Signed :

ISI COORDINATOR Jan.09

, 2002 o(erer ewes ignee)

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boil Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insupnce Insppectoion Cofof Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on L/"

,' 20.C.

and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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:

-- /

InspectOr:

,4-Z

///*

kK7 Commissions:

1L932, NB7742NISB (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

0203 (Main Steam)

WO 99062743-01 Date:

10-28-2001 Sheet: 1 Of 1 Unit:

2 PLAN 2-01-023 Repair Organization P.O. No., Job No. etc.

5. (a)

Construction Code **ASME Section III (b)

Edition of Section Xl used for Repair/Replacement 19 65 Edition, S/66 Addenda, Code Cases NONE 198.9 Edition, NO Addenda, Code Cases NONE

• • General Electric APED Specification 21A5743, rev.1.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Consolidated Safety Valve Consolidated S/N: BK6526 N/A Model: 3777-QA-RT-Unknown Replaced Yes at EPN: 2-0203-4C.

21-0S110 Consolidated Safety Valve Consolidated S/N: BK6304 N/A Cat I D-30404, Unknown Replacement Yes at EPN: 2-0203-4C.

UTC-2065264

7. Description of work: Removed existinq safety valve and replaced with a rebuilt/tested spare safety valve.

8. Test Conducted: Hydrostatic [ X ]

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [ ]

Test Pressure 1005 psig Test Temperature > 135 / <212 *F

9. Remarks: Satisfactory VT-2 examination was recorded during the D2R1 7 10 Yr Hydro under WO 99124181-09.

Certificate of Compliance We certify that the statemenrs made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed:

ISI COORDINATOR Jan.0

, 2002 S" (Owner er's Designee)

(Title)

(Date)

Certificate of Inspection, I, the undersigned, holding a valid commission issued by the National Board of Boi

,'Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insur7c9 and I/.spection Co-..of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on I-"'Lq/,

20 and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property lmage or a loss of any kind arising from or connected with this inspection.

Date:___________ Inspector.

/

'.4r7 r

,t/

Commissions:

IL932, NB7742NISB kohate, or NoiU cel Naf~t O

I txxU E*J*Uu

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL.. 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

0203 (Main Steam)

Wo 9g9n2744-01 Date:

10-28-2001 Sheet:

1 Of 1 Unit:

2 PLAN 2-01-024

5. (a) Construction Code **ASME Section III

,1965 Edition, S/66 Addenda, Code Cases NONE (b)

Edition of Section Xl used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE

• • General Electric APED Specification 21A5743, rev.1.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Consolidated Safety Valve at EPN: 2-0203-4D.

Consolidated Safety Valve at EPN: 2-0203-4D.

1-3/8"-12 inlet flange nut for EPN: 2-0203-4D.

1-3/8"-12 inlet flange nut for EPN: 2-0203-4D.

Name of Manufacturer Consolidated Consolidated NI...+ 1 1

Vor 1

RAnRir T Code Built Replaced or Stamped Serial No.

Brd Kin l4-I I

I N/A Model: 3777-QA-RT-Unknown I Replaced S/N: BK6232 Model: 3777-QA-RT 21-OS110 S/N: BK6282 N/

Ca ID3j6 UTC Unn t

Cat ID-30446, UTC 2065261 J

I t

r..

N/A None Unknown Hepaced NO Unknown Dresser

.1 4.-4

+

t I

N/A Cat ID-34748, UTC-Unknown Replaced No Ht code: S01 Cat I D-34748, UTC 2056302

7. Description of work: Removed existing safety valve and replaced with a rebuilt/tested spare safety valve.

8. Test Conducted: Hydrostatic [ X ]

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [ I Test Pressure 1005 psig Test Temperature > 135 / <212 OF

9. Remarks: Satisfactory VT-2 examination was recorded during the D2R17 10 Yr Hvdro under WO 99124181-09.

ID Replaced or Replacement Stamped Yes/No Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XA of the ASME Code.

Signed :

T R

_____an.D 2002 (owner or Okner's Clesignee)

(Title)

(Date)

Certificate of Inspection*,_/.

I, the undersigned, holding a valid commission issued by the National Board of re Vessel Inspectors andtheState or Province of Illinois, employed by The Hartford Steam and Boiler insuiarce Inspect

_O of Hartford, Connect*ut having inspected the REPAIR/REPLACEMENT described in this report on 1

20L=--nr state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal i ury or property damaW ort loss of any kind arising from or connected with this inspection.

Date:

7 Inspector:

B Commissions:

11932, NBT742NISB (State or Province, National Board)

Repair Organization P.O. No., Job No. etc.

Built Replaced Yes N/A UnknownI Unknown Replacement Yes N/A Unknown Replaced No N/A None Unknown Replaced No N/A

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

Date:

1-27-2001 Sheet:

1 Of 1 Unit:

2 WR 990253002-01 (PLAN 2-01-025)

Repair Organization P.O. No., Job No. etc.

4. Identification of System:

3900 Service Water (Diesel Generator Cooling Water)

5. (a)

Construction Code USAS B31.1.0 1967 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section Xl used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases N-416-1

6. Identification of Components Repaired or Replaced and Replacement Components

. Description of work: Excavated pin hole leak to remove flaw by grinding and performed weld repair.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [ ]

Nominal Operating Pressure [X ]

Not Applicable[

Test Pressure 125 psig Test Temperature Ambient OF

9. Remarks: VT-2 examination performed at nominal operating pressure, no evidence of leakage noted.

Certificateof Compliance We certify that the statements made in this report are correct and this REPAIR Conforms to Section XI of the ASME Code.

Signed:

ISI COORDINATOR f12 9

,20Q1 I A

(OwJner6-Owners Designee)

(Title)

(Date) 7 Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Line 2/3-39248-3" Unknown N/A N/A Service water return N/A Repair No line from EPN 2/3-9400-102 Certificateof Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed byTIhe.Hartford Steam and Boiler Insurance and Inspection Co. of Hartford, Connecticut having inspected the REPAIR described in this report on 20..*__ and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section xi of the AS ME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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 kindarising from or connected with this inspection.

I I')

In~n*rtnr ector A

t./

Commissions:

IL932. NB7742NISB (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

0300 (Sram Discharge Volumel

5. (a) Construction Code USAS B31.1-0 1

(b)

Edition of Section XI used for Repair/Replacement Date:

10-25-2001 Sheet:

1 Of 3 Unit:

2 DCP 9900486 WO 99231572 PLAN 2-01-026 Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO Addenda, Code Cases NONE 19 89* Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No 2" Blind flange from line 2-Unknown None N/A P & ID M-34-Sheet 2 Unknown Replaced No 0384-8".

2" 1500# blind flange.

Unknown None N/A Cat ID-1230213, Unknown Replacement No UTC-2622669.

7/8" dia. bolting for blind Unknown None N/A Bolting consisting of Unknown Replaced No flange from line 2-0384-8".

threaded rod & nuts.

7/8"-9 threaded rod.

Unknown Not recorded.

N/A Cat ID's-39851, Unknown Replacement No 35357,1200180; UTC's-2610872, 2021857, 2607188.

7/8"-9 heavy hex nuts.

Unknown Not recorded.

N/A Cat ID-37033, UTC-Unknown Replacement No 2616435.

7. Description of work: Removed/replaced existing blind flanges and bolting. New blind flanges have ports to facilitate hydrolazing..

8. Test Conducted: Hydrostatic [ ]

Pneumatic [ ]

Nominal Operating Pressure [X]

Not Applicable [I Test Pressure 1525 psig Test Temperature Ambient OF

9. Remarks: An acceptable VT-2 accomplished during the performance of DOS 0300-12.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section Xl of the ASME Code.

Signed:

QJ I

ISI COORDINATOR I-0 (Owner br Ownbrs Designee)

(Title)

(Date)

Certificate of Inspecti on &,

7 '

I, the undersigned, holding a valid commission issued by the National Board of, oiJiand Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance an ji'spection Ca: of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on I-I/,&

20t02Ž-nd state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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: ___________

Inspector: _________

Commissions:

1L932. NB7742NISB kýli~LL or FI VI v

Ill In 0,,1m / 111 Ill FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Addi

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Add

3. Work Performed By:

Same as Above (Name:

Same as Above (Addri

4. Identification of System:

0300 (Sram Discharge Volume)

5. (a)

Construction Code USAS B31.1-0 (b) Edition of Section XI used for Repair/Replacement Date:

10-25-2001 Sheet: 2 Of 3 Unit:

2 DCP 9900486 WO 99231572 PLAN 2-01-026 Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO Addenda, Code Cases NONE 19 89" Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No 2" Blind flange from line 2-Unknown None N/A P & ID M-34-Sheet 2 Unknown Replaced No 0385-8".

2" 1500# blind flange.

Unknown None N/A Cat ID-1230213, Unknown Replacement No UTC-2622669.

7/8" dia. bolting for blind Unknown None N/A Bolting consisting of Unknown Replaced No flange from line 2-0385-8".

threaded rod & nuts.

7/8"-9 threaded rod.

Unknown Not recorded.

N/A Cat ID's-39851, Unknown Replacement No 35357, 1200180; UTC's-2610872, 2021857, 2607188.

7/8"-9 heavy hex nuts.

Unknown Not recorded.

N/A Cat ID-37033, UTC-Unknown Replacement No 261435.

2" Blind flange from line 2-Unknown None N/A P & ID M-34-Sheet 2 Unknown Replaced No 0386-8".

1 2" 1500# blind flange.

Unknown None N/A Cat ID-1230213, Unknown Replacement No UTC-2622669.

7/8" dia. bolting for blind Unknown None N/A Bolting consisting of Unknown Replaced No flange from line 2-0386-8".

threaded rod & nuts.

7/8"-9 threaded rod.

Unknown Not recorded.

N/A Cat ID's-39851, Unknown Replacement No 35357; UTC's 2610872, 2021857.

7/8"-9 heavy hex nuts.

Unknown Ht cd-QJS N/A Cat ID-37033, UTC-Unknown Replacement No 261435.

2" Blind flange from line 2-Unknown None N/A P & ID M-34-Sheet 2 Unknown Replaced No 0387-8".

2" 1500# blind flange.

Unknown None N/A Cat ID-1230213, Unknown Replacement No UTC-2622669.

7/8" dia. bolting for blind Unknown None N/A Bolting consisting of Unknown Replaced No flange from line 2-0387-8".

threaded rod & nuts.

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL. 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

DCP 9900486 WO 9E Same as Above (Address)

Repair Organization F

4. Identification of System:

0300 (Sram Discharge Volume)

5. (a) Construction Code USAS B31.1-0 1967 Edition, N.O Addenda, Code Cases NONE (b) Edition of Section Xl used for Repair/Replacement 19895 Edition, NO Addenda, Code Cases NONE Date:

10-25-2001 Sheet: 3 Of 3 Unit:

2 9231572 PLAN 2-01-026 P.O. No., Job No. etc.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Continued from Sht. 2.

7/8"-9 threaded rod.

Unknown Not recorded.

N/A Cat ID's-39851, Unknown Replacement No 35357; UTC's 2610872, 2021857.

7/8"-9 heavy hex nuts.

Unknown Ht cd-QJS N/A Cat ID-37033, UTC-Unknown Replacement No 261435.

1-1/2" Blind flanges (qty-2)

Unknown None N/A P & ID M-34-Sheet 2 Unknown Replaced No from line 2-0408A-6".

1 1-1/2" 1500# blind flanges Unknown None N/A Cat ID-1200176, Unknown Replacement No (qty-2).

UTC-2607424.

1" dia. bolting for blind Unknown None N/A Bolting consisting of Unknown Replaced No flange from line 2-0408A-threaded rod & nuts.

6".

1"-8 threaded rod.

Unknown Not recorded.

N/A Cat ID's-35220, Unknown Replacement No 1200181; UTC's 2005170, 2607191.

1"-8 heavy hex nuts.

Unknown Ht cd-HDF N/A Cat ID-37034, UTC-Unknown Replacement No 2057524.

1-1/2" Blind flanges (qty-2)

Unknown None N/A P & ID M-34-Sheet 2 Unknown Replaced No from line 2-0408B-6".

1-1/2" 1500# blind flanges Unknown None N/A Cat ID-1230213, Unknown Replacement No (qty-2).

UTC-2622669.

1" dia. bolting for blind Unknown None N/A Bolting consisting of Unknown Replaced No flange from line 2-0408B-threaded rod & nuts.

6".

1"-8 threaded rod.

Unknown Not recorded.

N/A Cat ID's-35220, Unknown Replacement No 1200181; UTC's 2005170, 2607191.

1"-8 heavy hex nuts.

Unknown Ht cd-HDF N/A Cat 11-37034, UTC-Unknown Replacement No 2059784.

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

WO 99120951-01 Date:

10-29-2001 Sheet: 1 Of 1 Unit:

2 PLAN 2-01-027 Repair Organization P.O. No., Job No. etc.

4. Identification of System:

0203 (Main Steam)

5. (a) Construction Code **ASME Section III (b) Edition of Section XI used for Repair/Replacement 1968 Edition, W/68 Addenda, Code Cases NONE 198.9 Edition, NO Addenda, Code Cases NONE

• • General Electric APED Specification 21A9206, rev.6.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Target Rock Relief Valve.

Target Rock Corp.

S/N: 121 N/A EPN: 2-0203-3A Unknown Replaced Yes Target Rock Relief Valve.

Target Rock Corp.

S/N: 223 N/A Cat ID-008070, Unknown Replacement Yes UTC-2062534 Class 3, outlet flange stud, Unknown N/A N/A Pipe line 2-3019A-8" Unknown Replaced No 1"-8 X 8" SA-193 Gr. B7.

1"-8 SA-193 Gr. B7 all-Nova Machine N/A N/A Cat ID-45397, Unknown Replacement No thread rod cut 8" for Products UTC-2545147 replacement stud.

7. Description of work: Removed existing relief valve and replaced with a rebuiltltested spare safety valve. Also replaced one outlet flange stud (Construction Code for this stud is USAS B31.1 1967 Ed.).

8. Test Conducted: Hydrostatic [ X ]

Pneumatic

]

Nominal Operating Pressure [

Not Applicable [1 Test Pressure 1005 psig Test Temperature > 135 / <212 OF

9. Remarks: Satisfactory VT-2 examination was recorded during the D2R17 10 Yr Hydro under WO 99124181-09. Reference Repair/Replacement Plan 2 99-038 that recorded the refurbishment of Replacement valve S/N 223 under P.O. 000239 Release 000003.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAJIREPLACEMENT Conforms to Section Xl of the ASME Code.

Signed: John H. Youna qQ&

f*'--",

ISI COORDINATOR -

.___Jan.22,2002 (Owner or Owner's D6signee)

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the S ate or Province of Illinois, employed by Hartford Steam Boiler of CT having inspected the REPAIR/REPLACEMENT described in this report on -L,,

. 20..)-%.

and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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:

-d, 3I-Inspector. Robert T. Raine

. 7 "r Commissions:

1L932, NB7742N]SB

"(State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By: Same as Above (Name)

Same as Above (Address)

Date:

7-16-2001 Sheet:

1 Of 1

Unit:

2 W/O 99259544 (PLAN 2-01-029)

Repair Organization P.O. No., Job No. etc.

4. Identification of System:

3900 (DGSW Keep Fill Supply to CCSW)

5. (a)

Construction Code USAS B31.1.0 19 67 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 19 8.9 Edition,. NO Addenda, Code Cases N-416-1

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No I

Replacement Yes/No DGSW Keep Fill Supply to Edwards Valves Unknown N/A EPN 2-3999-634 N/A Replaced No CCSW Check Valve DGSW Keep Fill Supply to Edwards Valves Unknown N/A EPN 2-3999-636 N/A Replaced No CCSW Check Valve DGSW Keep Fill Supply to Velan Valve Corp.

Unknown N/A EPN 2-3999-634 N/A Replacement No CCSW Check Valve DGSW Keep Fill Supply to Velan Valve Corp.

Unknown N/A EPN 2-3999-636 N/A Replacement No CCSW Check Valve

7. Description of work: Replaced CCSW check valves with new check valves.

8. Test Conducted: Hydrostatic ]

Pneumatic [ ]

Nominal Operating Pressure [ X ]

Not Applicable Test Pressure 183 psig Test Temperature Ambient OF

9. Remarks:

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed

,S, COORDINATOR 2001 S-(Owner or Owner's Designee)

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurnce a74 Inspec o.p Co. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on

/I g, 20C._ and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any person injur property daagmor a loss of any kind arising from or connected with this inspection.

Date: J"/Y I*. nspector:

/224

/-*

zn Commissions:

IL932, NB7742N.SB (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

0203 (Main Steam)

WO Q790721 R6-01 Date:

11-05-2001 Sheet: 1 Of 1 Unit:

2 PLAN 2-01-031 Repair Organization P.O. No., Job No. etc.

5. (a)

Construction Code USAS B31.1-0 (b)

Edition of Section XI used for Repair/Replacement 19 67 Edition, NO Addenda, Code Cases NONE 1989 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Main Steam Isolation Valve Crane N/A None Unknown Replaced No Plug/Stem assembly from 2-0203-2D.

Main Steam Isolation Valve Crane N/A Cat ID-1200124, Unknown Replacement No Plug/Stem for 2-0203-2D.

UTC-2622599.

7. Description of work: Replace the valve plug with a refurbished one.

8. Test Conducted: Hydrostatic [

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [ X]

Test Pressure _ psig Test Temperature __ OF

9. Remarks: None.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section Xl of the ASME Code.

Signed:

VA-ISICOORDINATOR

__ _sJan.11_as e200e)

(Owner o-r Owe' psge)(Title)

(Date)

Certificate of Inspection 1 67 I, the undersigned, holding a valid commission issued by the National Board of BoIilr-//Pressure Vessel Ins.pect°rs and. testate or PrOvince Of Illinois, employed by The Hartford Steam and Boiler lnsuý ea pection Co. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on L*L/, 20._'and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any person, injury or property dmage or a loss of any kind arising from or connected with this inspection.

Date: 1-..,/

A&ki'l7-inspector:

___________-__(Commissions:

iL932, NB7742NISB

/

~

(State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address) b2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

3900 (Service Water Supply ECCS Room Coolers)

5. (a) Construction Code USAS B31.1.0 19 67 Edition, NO

Addenda, (b)

Edition of Section XI used for Repair/Replacement 19 89 Edition, NO

Addenda,

6. Identification of Components Repaired or Replaced and Replacement Components Date:

5-14-2001 Sheet:

1 Of 1 Unit:

2 WR 990269493 (PLAN 2-01-032)

Repair Organization P.O. No., Job No. etc.

Code Cases NONE Code Cases NONE Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Service water to ECCS Powel Unknown N/A 2-3999-252 N/A Replaced No check valve Service water to ECCS Velan Valve 025099-VLV-N/A 2-3999-252 N/A Replacement No check valve 02/03/04

7. Description of work: Removed existing check valve and replaced new stainless steel swing check valve.

Test Conducted: Hydrostatic [

Pneumatic [ ]

Nominal Operating Pressure [ X ]

Not Applicable[

Test Pressure 86 psig Test Temperature 80 OF

9. Remarks:_

Certificate of Compliance We certify that the em s made in this report are correct and this REPLACEMENT Conforms to Section Xl of the ASME Code.

Signed:

ISI COORDINATOR S

/.

20Q O n,(owner or Owner's Designee)

(Title)

(Date)

I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartd S*t n and Boier Insurance and Inspection Co. of Hartford, Connecticut having inspected the REPLACEMENT described in this report on ) - /.X

,20,0/- and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any mnariner for any pers galinjury or property damage Q) a loss of any kind arising from or connected with this inspection.

Date:

-inspector

__Z Commissions:

1L932, NB7742NISB

/

txeoaroice e"oe oeu S

n.a2A:...a

.* 1...,t..,

I (State or r'rovince, iNau~onwoal

xru)

/

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL.. 60450 (Address)

3. Work Performed By:

General Electric (Name)

Same as Above (Address)

4. Identification of System:

0300 (Control Rod Drive)

5. (a) Construction Code ASME Sect. III (b)

Edition of Section XI used for Repair/Replacement Date:

10-27-2001 Sheet: 1 Of 6

Unit:

2 WO 99250494-05 thru 24 PLAN 2-01-033 Repair Organization P.O. No., Job No. etc.

19 65 Edition, W/65 Addenda, Code Cases 1335-2. 1351. 1352 19 89* Edition, NO Addenda, Code Cases N207**. 1361-2**

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Control Rod Drive General Electric 2027 Location: 58-27 Replaced Yes Control Rod Drive General Electric A8924 Cat. ID-00413, 1992 Replacement Yes UTC's-2059461 &

2063125 Control Rod Drive Flange Unknown Unknown N/A Location:

N/A Replaced No Cap Screws.

Control Rod Drive Flange Unknown Ht. Code-PJK N/A Cat. ID-42416, N/A Replacement No Cap Screws.

UTC's-2059461, 2063125

7. Description of work: Replace existing control rod drive assemblies and associated flange cap screws with new control rod drive assemblies and flange cap screws. The removed cap screws did not receive a VT-1 examination with application of Dresden StationThird Interval Relief Request CR-20. *See Code Data Report on file for specific information. **Code Cases referenced on replacement CRD's obtained from Perry Nuclear Power Plant.

8. Test Conducted: Hydrostatic [ X ]

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [ ]

Test Pressure 1005 psig Test Temperature > 135 / < 212 OF

9. Remarks: Satisfactory VT-2 examination was recorded during the D2R17 10 Yr Hydro under WO 99124181-09. -Year Built on these CRD's was not recorded prior to placement into their shipping containers..

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Bo~il* adPressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler lnsurance.I Inspection Co.of Hartfor, Connect having inspected the REPAIR/REPLACEMENT described in this report on

/ -

A2, 20L*

-id state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any pers,}nal injury or property damage or a loss of any kind arising from or connected with this inspection.

) -, 2 7

/) 1/2-nsrnk~eqnr A.Z 2..4a~

Commissions:

1L932, NB7742N]SB Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section Xl of the ASME Code.

Signed:

ISI COORDINATOR

___Jan. 10_

, 2002 (Omer or OwneTs Design*e)

(Titie)

(Date) 7

(

(State or Province, National Board)

Licitti:

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Addi

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL.. 60450 (Adc

3. Work Performed By:

General Electric (Name Same as Above (Addr

4. Identification of System:

0300 (Control Rod Drive)

5. (a)

Construction Code ASME Sect. Ill (b)

Edition of Section XI used for Repair/Replacement Date:

10-27-2001 Sheet: 2 Of 6

Unit:

2 WO 99250494-05 thru 24 PLAN 2-01-033 1965 Edition, W/65 Addenda, Code Cases 1335-2. 1361. 1352 19 89* Edition, NO Addenda, Code Cases N207"*, 1361-2"*

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Name of Manufacturer General Electric General Electric Unknown Unknown Serial No.

%Rnof Brd ID

-r-Y-r Reair Code i N o"L.

T P0nir f

Code Replaced or Stamped Replaced or Rnlep1qment 60CLcat.on 42-043599 Rplcmn Ye 895 Unknown Cat. ID-00413, UTC-2621571 I ___

I 1

4-1 N/A N/A Replaced No Location: 42-35 1

4 I

I

+

1.

N/A Cat. ID-42416, N/A Replacement No Ht. Code-Cl 92 Cat. ID-42416, UTC-2600344

1.

1 4-4 1

I I-

+

t Location: 42-11 1969 Replaced Yes General Electric General Electric Unknown Unknown General Electric General Electric Unknown 1052 1052_____J-.

966 Cat. ID-00413, UTC-2621572 I

4-1.

4 1

t N/A Location: 42-11 N/A Replaced No Unknown I

I I

I N/A Cat. ID-42416, N/A Replacement No Ht. Code-C192 Cat. ID-42416, UTC-2600344 1

4-I I _____

I I

+

I Replaced Yes A6523 Location: 14-07 A6523It 1

608C Cat. ID-00413, UTC-2621567

£ 1-

-1 t

N/A Location:14-07 N/A Replaced No Unknown Unknown Ht. Code-C192 General Electric General Electric Unknown Unknown I __

J 4

I N/A Cat. ID-42416, N/A Replacement No Cat. ID-42416, UTC-2600344

.i __

1 4

I t

A ____

1 1

4 I

Location: 26-15 1980 Replaced Yes 1080 1080_____L-1 199 Rplcmn 588 Cat. ID-00413, UTC-2621568 I

t t

N/A Location: 26-15 N/A Replaced No Unknown 1 ___

1 4-1 N/A Cat. ID-42416, N/A Replacement No Ht. Code-Cl 92 I

I ____________

Cat. ID-42416, UTC-2600344 4

I

-t Stamped Yes/No Yes Yes Yes N/A Rep4acement N/A Repair Organization P.O. No., Job No. etc.

Built Yes Replaced lk Location: 42-35 1967 Replacement Yes 1969 t

No N/A Replaced N/A No N/A Replacement N/A Replaced Location: 42-11 1969 Replacement Yes 1969

• r Location: 42-11 No N/A Replaced N/A No N/A Replacement N/A Replaced Replacement Yes 1967 Location:14-07 Replaced No N/A N/A No N/A Replacement N/A 1980 Replaced Location: 26-15 Replacement Yes 1969 Location: 26-15 N/A Replaced No N/A No

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

General Electric (Name)

Same as Above (Address)

4. Identification of System:

0300 (Control Rod Drive)

5. (a)

Construction Code ASME Sect. III 19 65 (b)

Edition of Section XI used for Repair/Replacement 19 8.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Control Rod Drive Control Rod Drive Control Rod Drive Range Cap Screws.

Control Rod Drive Flange Cap Screws.

T T

T N*

f.ht Other I

Year I

Reoair.

Code Name oT Manufacturer Date:

10-27-2001 Sheet: 3 Of 6 Unit:

2 WO 99250494-05 thru 24 PLAN 2-01-033 Repair Organization P.O. No., Job No. etc.

Edition, W/65 Addenda, Code Cases 1335-2, 1361, 1352

Edition, NO Addenda, Code Cases N207**, 1361-2*

Serial No.

Brd Nn ID Built Replaced or Replacement

______________No

,1 P.eneral Electric 1085 Location: 50-35

.1.

4-1 1

t F

1989 Replacement Yes General Electric

• • A8736 Cat. ID-00413, UTC-2621564 4

4-I I

t I

Location: 50-35 N/A Replaced No Unknown Unknown N/A Stamped Yes/No Unknown Ht Code-C475 NIA Cat. ID-42416, N/A Replacement No UTC-2617049 (Aneral Electric General Electric A4040

-A8098 Location: 34-19 Cat.ral Electr Cat. ID-00413, UTC-2621554 F

1-4 t

1 F

N/A Replaced No Unknown Unknown N/A Location: 34-19 i-i-

-t 1

F N/A Replacement No Unknown Ht Code-C475 N/A Cat. ID-42416, UTC-2617049 I

• I-t t

L _______

1 1

4 1

I Replaced Yes General Electric General Electric 93 188 Location: 18-39 I

t I

1967 Replacement Yes Cat. ID-00413, UTC-2621570

[ _______

4.

1-4 I

t I

Location: 18-39 N/A Replaced NO Unknown Unknown N/A 1

4-4 1

1 1

Cat. ID-4241 6, N/A Replacement NO Unknown Ht. Code-C475 N/A Cat. ICD-42416, UTC-2617049 I _______

F 1

1 1

1 General Electric General Electric Unknown 1

1 4-1 t

Replaced Yes A5115 6101 Location: 22-55 Cat. ID-00413, UTC-2621558 1974 Replacement Yes 1

4 4-

-t I

T N/A Replaced No Unknown N/A Location: 22-55 1

1 1

+

4 I

N/A Replacement No Unknown Ht. Code-C475 N/A Cat. ID-42416, UTC-2617049

.1

-

1 T

I I______ J

-I U ____

Replaced Yes t

1969 Replacement Yes 1989 11, N/A Replaced No Location: 50-35 Yes Replaced Heplacement Yes 19B6 No N/A Replaced Replacement No N/A Replaced Yes Repacement yes 1967 Location: 18-39 N/A Replaced No Replacement No N/A Replaced Yes Replacement Yes 1974 N/A Replaced No Replacement No N/A

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicaqo IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

General Electric (Name)

Same as Above (Address)

4. Identification of System:

0300 (Control Rod Drive)

5. (a) Construction Code ASME Sect. Ill (b)

Edition of Section Xl used for Repair/Replacement Date:

10-27-2001 Sheet: 4 Of 6 Unit:

2 WO 99250494-05 thru 24 PLAN 2-01-033 Repair Organization P.O. No., Job No. etc.

1965 Edition, W/65 Addenda, Code Cases 1335-2, 1361, 1352 19 89-Edition, NO Addenda, Code Cases N207**. 1361-2**

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Control Control Control Cap Scr Control Cap Scr

Rod Drive T

1Oth V

r TrJr Y

Reair Name oT Manufacturer General Electric MSri.

Serial No.

Brd ID Built Replaced or Replacement Stamped Yes/No

+

t t

Location: 10-31 1968 Replaced Yes 126 Rod Drive General Electric 888A Cat. ID-00413, 1969 Replacement Yes UTC-2621566 Rod Drive Flange Unknown Unknown N/A Location: 10-31 N/A Replaced No ews.

Rod Drive Flange Unknown Ht. Code-C475 N/A Cat. ID-42416, N/A Replacement No ews.

UTC-2617049 RodM IDrivA Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

General Electric General Electric A5444 Location: 30-23 Controltod Driv

• • A4054 it. ICD-00413, UTC-2621573 1

4 t

N/A Replaced No Unknown Unknown N/A Location: 30-23 4.~

~

44 iF I

Unknown Ht. Code-C475 N/A Cat. ID-42416, UTC-2617049

1.

1 I

I I

I

4.

I I

I I

I I

Replaced Yes General Electric A3700 Location: 18-51

1.

F I

I t

1 1968 Replacement Yes General Electric 599 Cat. ID-00413, UTC-2621557

1.

I I

I-I 1-T N/A Replaced No Unknown Unknown N/A Location: 18-51

4.

I I

f I-t t

Cat. 1042416, N/A Replacement No Unknown Ht. Code-C475 N/A Cat. ID-42416, UTC-2617049

4.

I I

+

t I

t

4.

4 1

1 t

I Replaced Yes General Electric General Electric 962 Location: 14-55 I

4--+

1'

-t I

1 9B9 Replacement Yes 8731 Cat. ID-00413, UTC-2621555

.1 4-4-4 t

I I

N/A Replaced No Unknown Unknown N/A Location: 14-55 4

+

+

I I

1 Cat. 10-42416, N/A Replacement No Unknown Ht. Code-C475 N/A Cat. ID-42416, UTC-2617049 I

.L I ___

I ___________

n _____

I I

I I

I I

N/A Replaced Yes

,it Location: 10-31 1968 Replaced Yes Replacement Yes 1992 Replaced No N/A No N/A Replacement Replaced Yes I1' Replacement Yes 1968 Replaced No N/A Replacement No N/A Replaced Yes Replacement Yes 19139 N/A Replaced No Replacement No

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section N3

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

General Electric (Name)

Same as Above (Address)

4. Identification of System:

0300 (Control Rod Drive)

5. (a)

Construction Code ASME Sect. III (b)

Edition of Section XI used for Repair/Replacement Date:

10-27-2001 Sheet: 5 Of 6 Unit:

2 WO 99250494-05 thru 24 PLAN 2-01-033 1965 Edition, W/65 Addenda, Code Cases 1335-2, 1361, 1352 19 89* Edition, NO Addenda, Code Cases N207**, 1361-2"

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Control Rod Drive Control Rod Drive Control Rod Drive Range Cap Screws.

Control Rod Drive Flange Cap Screws.

Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

7 nam 0 I M.,,

I Na~t 7~

Other T

erT

Repair, Code aNuacture of Manufacturer Serial No.

Brd ID Built Replaced or NReplacedmees CGeneral Electric 613C Stamped Yes/No General Electric 1101 Cat. ID-00413, 1969 Replacement Yes UTC-2621575 Unknown Unknown N/A Location: 34-43 N/A Replaced No Unknown Ht. Code-C475 N/A Cat. ID-42416, N/A Replacement No UTC-2617049 Gen A~ral Electric A3556 eral_____

El-ctric General Electric 700C Cat. I D-00413, UTC-2621556 Unknown Unknown N/A Location: 18-47 N/A Replaced No Unknown Ht. Code-C475 N/A Cat. ID-42416, N/A Replacement No UTC-2617049 Locaion 46I eae GPeneral Electric 1932 I

44 t4 General Electric 1541 Cat. ID-00413, UTC-2621565 4.j.

.

t T

N/A Location: 46-43 N/A Replaced No Unknown Unknown I _________________

I 4-l

I I

N/A Cat. ID-42416, N/A Replacement No Unknown Ht. Code-C475 Cat. ID-42416, UTC-2617049 I

4-4 I

I I

A _______________

.

4-4 I

I T

Location: 42-55 Replaced Yes Control Rod Drive Control Rod Drive Control Rod Drive Flange Cap Screws.

Control Rod Drive Flange Cap Screws.

Gene'rml Electric General Electric A5513 ral Electri 909 Cat. ID-00413, UTC-2621569

.1 1-J, 4

t t

N/A Replaced No Unknown Unknown N/A Location: 42-55 I

I I

+

'I" N/A Cat. ID-4241 6, N/A Replacement No Unknown Ht. Code-C475 Cat. ID-42416, UTC-2617049 I ________

I ___

.1 _____

Yes I

I I

t I

T NIA Replacement N/A Repair Organization P.O. No., Job No. etc.

Replaced Yes Location: 34-43 Replaced Yes Location: 18-47 Replacement Yes 1967 Replaced Location: 46-43 Replacement Yes 1970 Location: 46-43 Replaced No N/A N/A No N/A Replacement N/A Yes Location: 42-55 Replaced Replacement Yes 1969 lft Replaced No N/A No

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XN

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Add

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Adc

3. Work Performed By:

General Electric (Name Same as Above (Addr

4. Identification of System:

0300 (Control Rod Drive)

5. (a)

Construction Code ASME Sect III (b)

Edition of Section XI used for Repair/Replacement Date:

10-27-2001 Sheet: 6 Of 6 Unit:

2 WO 99250494-05 thru 24 PLAN 2-01-033 1965 Edition, W/65 Addenda, Code Cases 1335-2, 1361, 1352 19689* Edition, NO Addenda, Code Cases N207*, 1361-2"*

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

L ___

L ____________

Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Control Rod Drive General Electric 7020 Location: 38-27 1978 Replaced Yes Control Rod Drive General Electric

• • A9117 Cat. ID-00413, 1992 Replacement Yes UTC-2621561 Control Rod Drive Flange Unknown Unknown N/A Location: 38-27 N/A Replaced No Cap Screws.

Control Rod Drive Flange Unknown Ht. Code-C475 N/A Cat. ID-42416, N/A Replacement No Cap Screws.

UTC-4617049 Control Rod Drive General Electric 600C Location: 26-47 Replaced Yes Control Rod Drive General Electric 9173 Cat. ID-00413, 1978 Replacement Yes UTC-2621574 Control Rod Drive Flange Unknown Unknown N/A Location: 26-47 N/A Replaced No Cap Screws.

Control Rod Drive Flange Unknown Ht. Code-C475 N/A Cat. ID-42416, N/A Replacement No Cap Screws.

UTC-2617049 Control Rod Drive General Electric 509C Location: 38-59 Replaced Yes Control Rod Drive General Electric 272 Cat. ID-00413, 1967 Replacement Yes UTC-2621560 Control Rod Drive Flange Unknown Unknown N/A Location: 38-59 N/A Replaced No Cap Screws.

Control Rod Drive Flange Unknown Ht. Code-C475 N/A Cat. ID-42416, N/A Replacement No Cap Screws.

UTC-2617049 Repair Organization P.O. No., Job No. etc.

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner:

Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

Date:

5-21-2001 Sheet:

1 Of 1 Unit:

2 W/O 321079 (PLAN 2-01-036)

Repair Organization P.O. No., Job No. etc.

4. Identification of System:

1500 (CCSW to ECCS Room Coolers)

5. (a) Construction Code USAS B31.1.0 1967 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section X1 used for Repair/Replacement 19 8-9 Edition, NO Addenda, Code Cases N-416-1

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No CCSW Supply to ECCS KEROTEST Unknown N/A EPN 2-1599-131B N/A Repair No Room Coolers Check Valve

7. Description of work: Excavated flaw from upstream weld by grinding and performed weld repair.

!- Test Conducted: Hydrostatic []

Pneumatic [ ]

Nominal Operating Pressure [ X I Not Applicable[ J Test Pressure 180 psig Test Temperature Ambient OF

9. Remarks:

Surface examinations of excavation, root pass and final weld performed to ensure removal of flaw and to comply with Code Case N-416-1.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR Conforms to Section Xl of the ASME Code.

Signed 4

,S, COORDINATOR 5

20-'

X (O01 r)wners Designee)

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boil r Insurance and Inspection Co. of Hartford, Connecticut having inspected the REPLACEMENT described in this report on

"-" *'l

, 20_Ob4 and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a losof antind adsinrom orconnected with this inspection.

Date:

"A

/ i) /

Inspector'.

Adjei 7 Z./ 4, Commissions:

11L932, NB,742N/SB

/

(State or P'rovince, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XN

1. Owner: Exelon Nuclear (Name)

Date:

11-5-2001 P.O. Box 805379. Chicago IL, 60680-5379 (Address)

Sheet:

1 Of 2

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

Unit:

2

3. Work Performed By:

Same as Above (Name)

EC8074 W/O 99102788, 91 (PLAN 2-01-045)

Same as Above (Address)

Repair Organization P.O. No., Job No. etc.

4. Identification of System:

1600 (Containment)

5. (a) Construction Code ASME Section III 19 65 Edition, Summer 1965 Addenda, Code Cases NONE (b) Edition of Section Xl used for Repair/Replacement 19 98 Edition. NO Addenda, Code Cases NONE

"*1998 Edition implemented in accordance with Relief Request MCR-02

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Containment Penetration Pathway Unknown N/A EPN 2-1600-X-124 Unknown Replaced Yes X-124 Expansion Bellows Containment Penetration Pathway H73510-2-2 N/A EPN 2-1600-X-124 2001 Replacement Yes X-124 Expansion Bellows Catalog ID 1220657 (Inner Ply)

Containment Penetration Pathway H73510-2-3 N/A EPN 2-1600-X-124 2001 Replacement Yes X-124 Expansion Bellows Catalog ID 1220659 (Outer Ply)

I I

X-1 24 Stand Off Rings Ecker-Erhardt Co, None N/A EPN 2-1600-X-124 N/A Replacement No Inc.

Catalog ID 1226701 Containment Penetration Pathway Unknown N/A EPN 2-1600-X-1 16B Unknown Replaced Yes X-1 16B Expansion Bellows Containment Penetration Pathway H73510-1-2 N/A EPN 2-1600-X-1 16B 2001 Replacement Yes X-1 16B Expansion Bellows Catalog ID 1220656 (Inner Ply)

Containment Penetration Pathway H73510-1-3 N/A EPN 2-1600-X-1 16B 2001 Replacement Yes X-1 16B Expansion Bellows Catalog ID 1220658 (Outer Ply)

X-1 16B Stand Off Rings Ecker-Erhardt Co, None N/A EPN 2-1600-X-1 16B N/A Replacement No Inc.

Catalog ID1226700, 1226699

7. Description of work: Removed existing two ply bellows and replaced with inner and outer single Ply bellows.

8. Test Conducted: Hydrostatic [

Pneumatic [X]

Nominal Operating Pressure [ ]

Not Applicable [1 Test Pressure 49.5 psig TestTemperature Ambient OF

9. Remarks: Pneumatic test performed in accordance with 10 CFR 50.50 Appendix J and ASME Section Xl IWE-5240

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

Date:

11-5-2001 Sheet: 2 Of 2 Unit:

2 EC8074 WIO 99102788, 91 (PLAN 2-01-045)

Repair Organization P.O. No., Job No. etc.

4. Identification of System:

1600 (Containment)

5. (a) Construction Code ASME Section III 1965 Edition, Summer 1965 Addenda, Code Cases NONE (b)

Edition of Section Xl used for Repair/Replacement 1989 Edition, NO Addenda, Code Cases NONE Certificate of Compliance We certify that the stat s made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed ISI COORDINATOR

/-

,201o (Ownr or Owner's Designee)

(Title)

(Date) uate:

i (State or Province, National Board)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance.nd Inspection Co. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on A

, 20 and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property d /age or a loss of any kind arising from or connected with this inspection.

Commissions:

1L932, NB7742NISB

~~V e e-l-,-

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL. 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

1500 (LPCI)

5. (a) Construction Code USAS B31.1.0 (b) Edition of Section XI used for Repair/Replacement Date:

11-5-2001 Sheet:

1 Of 1 Unit:

2 EC8074 WIO 99102788-04 (PLAN 2-01-046)

Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO

Addenda, Code Cases NONE 19 89 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No X-1 16B Flued Head Anchor Unknown N/A N/A 2-1600-X-1 16B N/A Replaced No Support Members X-1 16B Flued Head Anchor Unknown N/A N/A Cat I D 24992 N/A Replacement No Support Members 5" Seamless Pipe (A-106 Grade B)

X-1 16B Flued Head Anchor Unknown N/A N/A Cat I D 673433 N/A Replacement No Support Members Heat B1Y6861 8" x 8" x 3/8" Plate (A36)

7. Description of work: Temporarily removed support members to facilitate bellows replacement.

8. Test Conducted: Hydrostatic [

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [X]

Test Pressure N/...A psig Test Temperature N/A

°F

9. Remarks: VT-3 baseline examination performed.

F Certificate ef Compliance We certify that the statements made in this report are correct and this REPAIRIREPLACEMENT Conforms to Section Xl of the ASME Code.

Sign A or Owes Designee)

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurarce arI nspection Co. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on

,/.

-20, 20&/

and state to the best of my knoweledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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: //-'*-1? / Inspector:

Commissions:

1L932. NB7742NISB (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

3000 (Main Steam)

5. (a) Construction Code USAS B31.1-0 (b)

Edition of Section XA used for Repair/Replacement Date:

11-2-2001 Sheet:

1 Of 2 Unit:

2 DCP 9900425 WO 99248274 PLAN 2-01-047 Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO Addenda, Code Cases NONE 19 89* Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Support M-564E-Sht.4 on Pacific Scientific/NPS S/N: 17630, N/A Mechanical snubber Unknown Replaced Yes line 2-3001 A-20". (Task 03)

P/N: PSA-10 w/ adaptor, Item #1 of original support assembly.

Support M-564E-Sht.4 on Unknown None N/A 2' Sch.80 pipe used Unknown Replaced No line 2-3001 A-20". (Task 03) as extension pc.,

Item #7 of original support assembly.

Support M-564E-Sht.4 on NPS P/N: SMTT N/A Transition kit, Item Unknown Replaced No line 2-3001A-20". (Task 03)

1. 9 of original support assembly.

Support M-564E-Sht.4 on Lisega S/N:

N/A Cat ID-1218470, Unknown Replacement No line 2-3001A-20". (Task 03) 612653122, UTC-2605440.

P/N: 307256

7. Description of work: Modify Main Steam piping support (snubber assembly) to facilitate station EPU.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [ X]

Test Pressure - psig Test Temperature Ambient OF

9. Remarks: Installation task is 03. Satisfactory VT-3/4 performed on final installation. Snubber functional test performed under Task 04.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section X1 of the ASME Code.

Signed ISI COORDINATOR 201 C2 (Owner br Owver's Designee)

(Title)

(Date)

Certificate of Inspection

.6/

I, the undersigned, holding a valid commission issued by the National Board of Boil and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler lnsuranrexand Inspection of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on /

20-Zi-7and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any)?ersonal inI or proerty damage or a loss of any kind arising from or connected with this inspection.

Date:

Inspector:

/

Commissions:

IL932, NB7742NISB (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL.. 60450 (Address)

3. Work Performed By: Same as Above (Name)

Same as Above (Address)

4. Identification of System:

3000 (Main Steam)

5. (a)

Construction Code USAS B31.1-0 (b)

Edition of Section XI used for Repair/Replacement Date:

11-2-2001 Sheet: 2 Of 2 Unit:

2 DCP 9900425 WO 99248274 PLAN 2-01-047 Repair Organization P.O. No., Job No. etc.

1967 Edition, NO Addenda, Code Cases NONE 1989* Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Support M-564E-Sht.4 on line 2-3001 A-20". (Task 03)

Support M-564E-Sht.4 on line 2-3001A-20". (Task 03)

Support M-564E-Sht.4 on line 2-3001A-20". (Task 03)

Support M-564E-Sht.4 on line 2-3001A-20". (Task 03)

Support M-564E-Sht.4 on line 2-3001A-20". (Task 03)

Support M-564E-Sht.4 on line 2-3001 A-20". (Task 03)

Name of Manufacturer Oth..

-Yea..I r

I Repair I

Code~

MSra.

Serial No.

Brd Mn ID Buil Replaced or Reolacement Stamped Yes/No NPS P/N: SPC N/A Pipe clamp, Item #6 Unknown Replaced No 200.

of original assembly.

Lisega P/N: 375164 SpI. E.

N/A Cat ID-1218465, UTC-2617451.

______________4.-ft t

I I

f-I 1

V.

Unknown Replaced No NPS P/N: SMRB N/A Rear bracket, Item

1. 8 of original assembly.

t 1

4

f t

t I

Unknown Replacement No Lisega P/N: 357959 N/A Cat ID-1218462, UTC-2617450 I

4.-f t

I I

£ 4

4.-f t

.

I Unknown Replaced No Unknown None N/A Support steel, Item

1. 3 of original assembly.

J.

I-f-I I

I..

Cat ID-514034, Unknown fieplacement No Unknown Ht #972774 N/A Cat ID-5104 UTC-2037010.

(Actually added to above Item #3.)

I I

+

I I

-I I

I I

+

I I

1

4.

+

I I

r I

I-

+

I I

I

1.

4 I

I 4

4 I

I t

I 1 ____

1 4

1 1

i t

I No Unknown Replacement Unknown Replaced No No Unknown Replacement Replaced No Unknown Unknown Replacement No

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

NWS Technologies (Name) 131 Venture Blvd. Spartanburg, SC 29301 (Address)

4. Identification of System:

0203 (Main Steam)

PO 23108-Rel.001 Date:

10-06-2001 Sheet:

1 Of 2 Unit:

2 PLAN 2-01-048

5. (a) Construction Code **ASME Section III

,1968 Edition, W/68 Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE

• • General Electric APED Specification 21A9206, rev.6.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Component Target Rock Relief Valve.

Target Rock Relief Valve.

name OT 1



TRI..., F 1

Vr I

Rnnir Code Replaced or Stamped Name o'r Manufacturer Thrnet Roc*k Corn.

Target Rock Corp.

miIN.

Serial No.

Brd ID Built Replaced or Replacement I



-t I

Unknown BodyS/N: 222 Repair Yes S/N: 130A N/A I

i I

I

-I1 S/N: 130A Cat I D-008070, UTC-2062536, Installed into body S/N: 115.

[

4

+

t t

1 Stamped Yes/No Target Rock Relief Valve Target Rock Corp.

Not recorded N/A P/N: 200243-1 Unknown Replaced No estage disc.

Target Rock Relief Valve Target Rock Corp.

S/N: 78 N/A SI-570E28, Unknown Replacement No 2_ stage disc.

QRI-D93-02504

7. Description of work: NWS to refurbish/test set pressure spare TRV. OEM parts used were items drawn/sent from Dresden Station Stores Dept.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [ X]

Test Pressure _

psig Test Temperature __ OF

9. Remarks: Hardcopy documents contained in Receipt #63277.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed: John H. Young s

(SI COORDINATOR (Ja II(Owner or Owners D igneý (Title)

(Date)

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 Itrovince of Illinois, employed by Hartford Steam Boiler of CT having inspected the REPAIR/REPLACEMENT described in this report on -_/ _.1

,20_17.

and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XA of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this 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: /

Inspector: Robert T. Rainey z

x/

Commissions:

IL932, NB7742NISB 11

• (State or Province, National Board)

Repair Organization P.O. No., Job No. etc.

-Yes Unknown Repair Body S/N: 222 Unknown Repaired Yes N/A

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicaqo IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450.(Address)

3. Work Performed By:

NWS Technologies (Name)

PO 23108-Rel.001 131 Venture Blvd. Spartanburq, SC 29301 (Address)

Repair Organization

4. Identification of System:

0203 (Main Steam)

5. (a)

Construction Code **ASME Section III 19 68 Edition, W/68 Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE

• • General Electric APED Specification 21A9206, rev.6.

6. Identification of Components Repaired or Replaced and Replacement Components Date:

10-06-2001 Sheet: 2 Of 2 Unit:

2 PLAN 2-01-048 P.O. No., Job No. etc.

Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No..

Brd ID Built Replaced or Stamped No Replacement Yes/No Target Rock Relief Valve Target Rock Corp.

Not recorded N/A P/N: 200242-1 Unknown Replaced No pilot disc.

Target Rock Relief Valve Target Rock Corp.

S/N: 452 N/A SI-570D56, Unknown Replacement No pilot disc.

QRI-292703

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

1400 (Core Spray) and 1500 (LPCI)

5. (a) Construction Code USAS B31.1-0 (b)

Edition of Section XI used for Repair/Replacement Date:

10-26-2001 Sheet:

1 Of 4 Unit:

2 DCP 9900842 WO 99248723 PLAN 2-01-049 Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO Addenda, Code Cases NONE 19 89* Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Support M-3214-23 on line Unknown None N/A Plate steel, Item #5 Unknown Replaced No 2-1508-18". (Task 03) of original support assembly.

Support M-3214-23 on line Unknown None N/A Cat ID-38329, UTC-Unknown Replacement No 2-1508-18". (Task 03) 2401080.

Support M-3214-23 on line Hilti None N/A Anchor bolts, Item #6 Unknown Replaced No 2-1508-18". (Task 03) of original support assembly, (qty-4).

Support M-3214-23 on line Drillco Devices, LTD P/N: MB-750-N/A Cat ID-35650, UTC-Unknown Replacement No 2-1508-18". (Task 03) 16-1/2-11-1/2 2618398.

7. Description of work: Modify four piping supports to facilitate station EPU.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [ ]

Nominal Operating Pressure [

Not Applicable [ X]

Test Pressure_- psig Test Temperature Ambient OF

9. Remarks: WO tasks affected are 03 thru 06. Satisfactory VT-3/4 performed on final installations.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed IS COORDINATOR 1 -20

" -'i (Owner or O4wner's Designee)

(Title)

(Date)

(State or Province, National Board)

Certificate of Inspection _

I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance (InpLnspection Co/of Hartford, Connecticut having inspected the REPAI R/REPLACEMENT described in this report on L-/ Z 200.- and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any rsonaD2 !3Ljr propty damage or a loss of any kind arising from or connected with this inspection.

• /<

Oh~

• tnr' 4

i*-*-'i Commissions:

1L932. NB7742NISB LJ,::Z*:,

/

v A

hs.... t or...

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner:

Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

1400 (Core Spray) and 1500 (LPCI)

5. (a) Construction Code USAS B31.1-0 (b)

Edition of Section Xl used for Repair/Replacement Date:

10-26-2001 Sheet: 2 Of 'Z Unit:

2 DCP 9900842 WO 99248723 PLAN 2-01-049 Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO Addenda, Code Cases NONE 19 89_ Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Support M-3381 on line 2-Unknown None N/A U-bolt, Item #5 of Unknown Replaced No 1527-3". (Task 04) original support assembly.

Support M-3381 on line 2-Unknown None N/A Nuts for U-bolt, Item Unknown Replaced No 1527-3". (Task 04)

1. 6 of original support assembly.

Support M-3381 on line 2-ITT Grinnel P/N: 137SN N/A Cat ID-1218452, Unknown Replacement No 1527-3". (Task 04)

UTC-2607161.

(U-bolt wlnuts.)

Support M-3209-24 on line Unknown None N/A U-bolt w/nuts, Item Unknown Replaced No 2-1404-12". (Task 05)

1. 8 of the original support assembly (qty-2).

Support M-3209-24 on line Consolidated Power P/N: 137SN N/A Cat ID-1218446, Unknown Replacement No 2-1404-12". (Task 05)

Supply UTC-2607162.

(U-bolt w/nuts.)

Support M-3209-24 on line Unknown None N/A Support members Unknown Replaced No 2-1404-12". (Task 05) consisting of Item's 9 and 10 from dwg.

BOM.

Support M-3209-24 on line Unknown None N/A Cat ID-641125, Unknown Replacement No 2-1404-12". (Task 05)

UTC-2606198.

Support M-3209-24 on line Consolidated Power P/N: 180471, N/A Cat ID-514702, Unknown Replacement No 2-1404-12". (Task 05)

Supply Ht. #U1192 UTC-2606197 Support M-3209-24 on line Elcen P/N: Fig.420, N/A Sway strut, originally Unknown Replaced No 2-1406-8". (Task 05)

Type 1, Size 5 as Item #1 part of support assembly.

Support M-3209-24 on line Lisega P/N:

N/A Cat ID-1218469, Unknown Replacement No 2-1406-8". (Task 05) 305253RE3, UTC-2622171.

S/N:

01615080/075

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

Date:

11-5-2001 Sheet: 1 Of 1 Unit:

2 I:C 330S65 wo 992358O6 PLAN 9**-Fl R

Repair Organization P.O. No., Job No. etc.

4. Identification of System:

1600 (Containment)

5. (a) Construction Code ASME Section 111 1965 Edition, Summer 1965 Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 19 98* Edition, NO Addenda, Code Cases NONE

"*1998 Edition implemented in accordance with Relief Request MCR-02

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Electrical Containment General Electric Unknown N/A EPN: X-202F N/A Replaced No Penetration X-202F Electrical Containment Conax Nuclear, Inc.

6160 6160 Cat ID-1220565, 2001 Replacement Yes Penetration X-202F UTC-2621983,

• . Description of work: Removed existing electrical containment penetration head from the sleeve and welded new head on the existing sleeve.

8. Test Conducted: Hydrostatic[

' Pneumatic [X]

Nominal Operating Pressure[ ]

Not Applicable []

Test Pressure 49.5 psig Test Temperature Ambient OF

9. Remarks: Pneumatic test performed in accordance with 10 CFR 50 Appendix J and ASME Section Xl IWE-5240 Certificate of Compliance, We certify that the tements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section Xl of the ASME Code.

ig ned:

ISI COORDINATOR Jan.10_.

, 2002 (Owner or O.vners Pesignee)

(Title)

(Date) 1 Certificate of Inspection/".

1, the undersigned, holding a valid commission issued by the National Board of BoiX eand Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insu pneand Insp9I Cffof Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on V1 L

2 state to the best of my knowledge and belief, this repair or replacement has. been constructed in accordance with seon XI of the ASME Code. By signing this certiiate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property d page or a loss of any kind arising from or connected with this inspection.

"Date:

u Isetr____

Commissions:

1L932, NB7742NISB Dne (State or Province, National Board)

EC330565 099235806 PLAN2-01-053

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL.. 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

WO QQn19 1s-r1 Date:

10-26-2001 Sheet: 1 Of 1 Unit:

2 Pl AN 9-fll-nlAn Repair Organization P.O. No., Job No. etc.

4. Identification of System:

0200 (Recim.)

5. (a) Construction Code USAS B31.1-0 (b) Edition of Section Xl used for Repair/Replacement 1967 Edition, NO Addenda, Code Cases NONE 19 89* Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mf rs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Support M-1 135-Sht.15, Pacific Scientific S/N: 6811, N/A Mechanical snubber.

Unknown Replaced Yes EPN 2-0202-03-B.

P/N: PSA-35 Support M-1135-Sht.15, Pacific Scientific S/N: 5425, N/A Cat ID-40805, UTC-1980 Replacement Yes EPN 2-0202-03-B.

PIN: PSA-35 2622819, BWD WR A32811.

7. Description ofworK: miemoveues/replace I, n oa*yýl l

8. Test Conducted: Hydrostatic [

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [ X Test Pressure -

psig Test Temperature __ OF

9. Remarks: Satisfactory VT-314 performed on final installation and Snubber functional test per DTS 0020-02. Removed snubber had degraded performance Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed:

=----

-r SI COORDINATOR Jan.08 2002 (Owner or Owner's Dfsignee)

(Title)

(Date)

Certificate of Inspecti y

• N.

6 o/

1, the undersigned, holding a valid commission issued by the National Board of BoiJ 4 and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance and Inspection Co.of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on /'"./.is/--2-20 and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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.

/k/

" Inspector:

Commissions:

1L932, NB7742NISB (State or Province, National Board)

I

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASMEE Code Section XI

1. Owner: Exelon Nuclear (Name)

Date:

10-27-2001 P.O. Box 805379. Chicago IL, 60680-5379 (Address)

Sheet:

I Of 1

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

Unit:

2

3. Work Performed By:

Same as Above (Name)

WO 99222112-01 PLAN 2-01-061 Same as Above (Address)

Repair Organization P.O. No., Job No. etc.

4. Identification of System:

3000 (Main Steam)

5. (a) Construction Code USAS B31.1-0 19 67 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section XA used for Repair/Replacement 19 89* Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Support M-564-Sht.1, EPN Pacific Scientific S/N: 8229, N/A Mechanical snubber.

Unknown Replaced Yes 2-3001-C-50.

P/N: PSA-35 Support M-564-Sht.1, EPN Pacific Scientific S/N: 11817, N/A Cat ID-40805, UTC-1983 Replacement Yes 2-3001-C-50.

P/N: PSA-35 2622817, BWD WR A32405.

7. Description of work: Remove/test/replace (if necessarv)reinstall PSA-35 mechanical snubber.

9. Test Conducted: Hydrostatic [

Pneumatic [ I Nominal Operating Pressure [ ]

Not Applicable [ X]

Test Pressure _

psig Test Temperature __ F

9. Remarks: Satisfactory VT-3/4 performed on final installation and Snubber functional test per DTS 0020-02. Removed snubber had degraded performance S~Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed: 5LAk 4=7 SI COORDINATOR Jan. 08

.2002 (OCwner oi Owner`9 Designee)

(Title)

(Date)

Certificate of lnspecti_,* n I, the undersigned, holding a valid commission issued by the National Board of BoEil r and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insur-_ce.,ppd Inspection Co. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on

LLL, 20t-,-and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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 4

I. Inspector

}*t.V77"11,

'A Commissions:

IL932. NB7742NISB

~(State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

3000 (Main Steam)

5. (a)

Construction Code USAS B31.1-0 (b)

Edition of Section Xl used for Repair/Replacement WO 0372768-01 Date:

10-27-2001 Sheet: 1 Of 1 Unit:

2 PLAN 2-01 -062 Repair Organization P.O. No., Job No. etc.

1967 Edition, NO Addenda, Code Cases NONE 1989* Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer SerialNo.

Brd ID Built Replaced or Stamped No Replacement Yes/No Support M-1 135-Sht.13, Pacific Scientific SIN: 6322, N/A Mechanical snubber.

Unknown Replaced Yes EPN 2-0202-12-A.

P/N: PSA-35 Support M-1 135-Sht.13, Pacific Scientific S/N: 11036, N/A Cat ID-40805, UTC-1983 Replacement Yes EPN 2-0202-12-A.

P/N: PSA-35 2622820, BWD WR A32388.

7. Description of work: Test and replace PSA-35 mechanical snubber that was discovered was foreign material covering it, ref. AR/CR 079637.

3. Test Conducted: Hydrostatic [

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [ X Test Pressure _

psig Test Temperature __ OF

9. Remarks: Satisfactory VT-3/4 performed on final installation and Snubber functional test per DTS 0020-02.

SCertificate of Compliance We certify that the statements made in this report are correct and this REPAIRIREPLACEMENT Conforms to Section Xl of the ASME Code.

Signed:

L ISI COORDINATOR Jan.07 2002 S(Own& 6r Owners Designee)

(Title)

(Date)

Certificate of inspectio n I, the undersigned, holding a valid commission issued by the National Board of Boilpe and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance and InspectiD Co.of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on 1Lt

,20" L L-anld state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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.

rIIns-r:

Commissions:

IL932n NB7or42NISB (State or Province, National Board)

L/

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

3900 (CCSW)

5. (a)

Construction Code USAS B31.1-0 (b)

Edition of Section XI used for Repair/Replacement Wo nOt74Rg5-nl Date:

10-27-2001 Sheet: 1 Of 1 Unit:

2 Pl AN 9-rn-NR."

Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO Addenda, Code Cases NONE 1989 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Pipe line 2/3-39251-3"-DX.

Unknown None N/A P & ID M-3121, N/A Replaced No associated with 2/3 9400-102 Refrigeration Condensing Unit.

Pipe line 2/3-39251-3"-DX, Unknown HT#-Y67155 N/A Cat. ID-385642, N/A Replacement No sch.80, A-106 Gr.B UTC-2048190.

7. Description of work: Replaced a section of vertical pipe that developed a leak.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [ ]

Nominal Operating Pressure [X]

Not Applicable[

Test Pressure 178 psig Test Temperature 71.4 OF

9. Remarks: VT-2 was performed, and no leakaqe was detected.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIRIREPLACEMENT Conforms to Section Xl of the ASME Code.

Signed:

_, '24 ISI COORDINATOR 1 /'7

,20C)-.Z (Owner or Owner's Designee)

(Title)

(Date)

(State or Province, National Board)

Certificate of lnspectio!-

I, the undersigned, holding a valid commission issued by the National Board of BoiJJr and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance and Inspection Qo.of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on LL-

/

., 20_..and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

/.-A-r Commissions:

L932, NB7742NISB

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL. 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

General Electric (Name)

Same as Above (Address)

4. Identification of System:

0200 Reactor Head Vent WO.qi117771-ni Date:

11-4-2001 Sheet:

1 Of 1 Unit:

2 PILAN 2-01-0364 Repair Organization P.O. No., Job No. etc.

5. (a) Construction Code USAS B31.1.0 1967 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Studs (7/8"-9 NSA-1 93 Gr.

Unknown N/A N/A HV2-12-FLG, N/A Replaced No B7) for flange set HV2 Isometric dwg.

FLG. on pipe line 2-0215-ISI-126.

2"-B.

Studs (7/8"-9 NSA-1 93 Gr.

NO-&

-IWAiIA-.A, Ht. Cd. - NWN N/A Cat ID - 037096, N/A Replacement No B7 cut all-thread bar stock)

UTC - 2045537, for flange set HV2-12-FLG.

Issue Tkt - 5453000 on pipe line 2-0215-2"-B.

7. Description of work: Replace the fiange studs that were lost during D2R17.

8. Test Conducted: Hydrostatic [ X ]

Pneumatic [ ]

Nominal Operating Pressure [

Not Applicable[

Test Pressure 1005 psig Test Temperature > 135 / < 212 'F

9. Remarks: Satisfactory VT-2 examination was recorded during the D2R17 10 Yr Hydro under WO 99124181-09. ***Year Built on these CRD's was not recorded prior to placement into their shipping containers..

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed: JohnH. Younq ISI COORDINATOR

_____Jan.16

,2002 (Owner or Owner's Designe)(

(Title)

(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 Province of Illinois, employed by Hartford Steam Boiler of CT having inspected the REPAIR/REPLACEMENT described in this report on

,-*Z,

. 20.0 L and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section I of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date:

//

"- 6 2 -inspector: Robert T. Rainey Commissions:

11932, NBT742NISB I (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

4700 (Instrument Air)

5. (a) Construction Code USAS B31.1-0 "

(b)

Edition of Section Xl used for Repair/Replacement Date:

11-5-2001 Sheet:

1 Of 1 Unit:

2 DCP 9900485 WIO 99225126 (PLAN 2-01-065)

Repair Organization P.O. No., Job No. etc.

19 67 Edition, NO Addenda, Code Cases NONE 19 98* Edition, NO Addenda, Code Cases NONE "1998 Edition implemented in accordance with Relief Request MCR-02

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Cap on line 2-47320-1" Unknown None N/A Cat ID 7442 Unknown Replacement No through Containment Penetration X-139D

7. Description of work: Removed Instrument Air line, cut and capped line at containment penetration.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [X]

Nominal Operating Pressure [ ]

Not Applicable Test Pressure 49.5 psig Test Temperature Ambient OF

9. Remarks: Pneumatic test performed in accordance with 10 CFR 50 Appendix J and ASME Section Xl IWE-5240.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section X1 of the ASME Code.

Signed:-.

ISI COORDINATOR

//

d5

,20 I

I Designee)

(Title)

(Date) uate:

i- -

p 7/

(State or Province, National Board)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insuranco and Inspection Co. of Hartford, Connecticut having inspected the REPAIR/REPLACEMENT described in this report on

//

, 20-0j, and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XA of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this 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.

S...../

,,,,I Commissions:

11932. NB7742NISB

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

Date:

11-5-2001 Sheet: 1 Of 1 Unit:

2 WO 00381568-01 PLAN 2-01-066 Repair Organization P.O. No., Job No. etc.

4. Identification of System:

1500 (LPCI)

5. (a)

Construction Code USAS B31.1.0 19 67 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section XA used for Repair/Replacement 19 8-9 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped I

No Replacement Yes/No Pipe line 2-1510-8"-D weld Unknown N/A N/A P & ID: M-29-Sht 2 N/A Repaired No immediately downstream of pump 2-1501-44B.

Pipe line 2-1510-8"-D weld Unknown N/A N/A P & ID: M-29-Sht. 2 N/A Repair No immediately downstream of pump 2-1501-44B.

7. Description of work: Weld repair through wall leakage on 8" elbow to flange weldment.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [ ]

Nominal Operating Pressure [X]

Not Applicable [1 Test Pressure 190 psig Test Temperature Ambient OF

9. Remarks: Acceptable VT-2 baseline examination after repairs.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed:

<0,4 (L...

ISI COORDINATOR I

, 20 (Owner or Owner's 0 signee)

(Title)

(Date)

Certificate of Inspection r

/

I, the undersigned, holding a valid commission issued by the National Board of BoiE'an

ý'Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance a 4nspecti C-of Hartford, Connecticut having inspected the REPAIR/REPLACEM ENT described in this report on _

14 Z.

and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any persgnal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date:

I//

"-Inspector:

/4 j.-

Commissions:

1L932, NB7742NiSB (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road. Morris IL.. 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

WO N 0N4004-01 Date:

01-21-2002 Sheet:

1 Of 1 Unit:

2 P1 AN 2-02-001 Repair Organization P.O. No., Job No. etc.

4. Identification of System:

1500 (LPCI) and 5700 (HVAC)

5. (a) Construction Code USAS B31.1.0 19 67 Edition, NO Addenda, Code Cases NONE (b)

Edition of Section Xl used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Unit 2 CCSW Vault Room Aerofin Model: C-N/A EPN: 2-5700-30A N/A Replaced No Cooler.

12AE 20.6X70.5-10 1

Unit 2 CCSW Vault Room A & A EQUIPMENT HT# 988WNT N/A Cat. Id-005013, N/A Replacement No Cooler, isolated with blind

& SUPPLY CO.

UTC-2032914. Pipe flanges, qty-2 (see work lines: 2-15100B-2" description below),

and 2-15101 B-2".

7. Description of work:Under Temporary Modification 334930 remove the cooler and place blind flanqes on associated pipe flanges until new replacement cooler is installed under WO 0400171.

8. Test Conducted: Hydrostatic [

Pneumatic [ ]

Nominal Operating Pressure [ X ]

Not Applicable [1 Test Pressure 194.2 psig Test Temperature Ambient OF

9. Remarks: Acceptable VT-2 was performed.

Date: L-.;

'? - Inspector: Robert T. Rainey Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed: John H. Youn ISI COORDINATOR

_____Jan.28

, 2002 (Owner or Owner's Desi nee)

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State 04 Pjovince Illinois, employed by Hartford Steam Boiler of CT having inspected the REPAIR/REPLACEM ENT described in this report on 206.--

and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section Xl of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shail 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.

i,*C o

m mis Commissions:

1L932, NB7742NISB

'X (State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASMEE Code Section NJ

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

4. Identification of System:

0203 (Main Steam)

5. (a) Construction Code USAS B31.1-0 (b) Edition of Section Xl used for Repair/Replacement WO 972047223 Date:

08-03-2001 Sheet: 1 Of 1 Unit:

2 PLAN 2-99-002 Repair Organization P.O. No., Job No. etc.

1967 Edition, NO Addenda, Code Cases NONE 19 8_9 Edition, NO Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Spare Main Steam Isolation Crane S/N: 25, N/A None Unknown Repair No Valve Disc removed from Ht. #5-21207 3-0203-2D.

Spare Main Steam Isolation Crane S/N: 25, N/A None Unknown Repaired No Valve Disc removed from Ht. #5-21207 3-0203-2D.

Pilot seat welded to MSIV Crane None N/A None Replaced No disc removed from 3-0203 2D.

Pilot seat welded into spare Crane P/N: 1552 N/A Cat ID-07995, UTC-Replacement No MSIV disc.

2059412.

7. Description of work: Weld repair Stellite surfaces such as seating and guides along with replacing pilot seat welded to spare disc.

8. Test Conducted: Hydrostatic [

Pneumatic [

Nominal Operating Pressure []

Not Applicable [ X]

Test Pressure _

psig Test Temperature __ OF

9. Remarks: NDE ( PT surface) performed on disc excavations and final machined/welds.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XA of the ASME Code.

Signed: _

eor__-eISI COORDINATOR Jan.08

, 2002_

'(Ownr or Ow&ners D nee)

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Bo'lerand Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insure arnsIpection Co.of Hartford, Connecticut having inspected the REPAIR/REPLACEM ENT described in this report on

/

1/ -

20.

• a state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XA of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, conceming the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date:

/ //*/-6 twz2-sc~tor:

Ci,/F~~uz~ifommissions:

IL932 NB7742NISB V,

(State or Province, National Board) jr

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI 1.. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

NWS Technologies (Name) 131 Venture Blvd. Spartanburg, SC 29301 (Address)

Date:

09-10-1999 Sheet:

1 Of 1 Unit:

2 PC 367668-ReI.DR2 PLAN 2-qq-n5q7 Repair Organization P.O. No., Job No. etc.

4. Identification of System:

0203 (Main Steam)

5. (a) Construction Code **ASME Section III

,19 68 Edition, W/68 Addenda, Code Cases NONE (b)

Edition of Section XA used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE General Electric APED Specification 21A9206, rev.6.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Target Rock Relief Valve.

Target Rock Corp.

S/N: 214 N/A Body S/N: 223 Unknown Repair Yes Target Rock Relief Valve.

Target Rock Corp.

S/N: 214 N/A Cat ID-008070, Unknown Repaired Yes UTC-2042359

7. Description of work: NWS to refurbish/test set pressure spare TRV. Repair is actually seat(s) weld removal to facilitate seat replacement.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [ ]

Nominal Operating Pressure [ ]

Not Applicable [ X Test Pressure _

psig Test Temperature __ OF

9. Remarks: Satisfactory VT-2 examination was recorded during the D3R1 6 during the Rx pressure test.. Reference Repair/Replacement Plan 3-99-043 that recorded Replacement valve system S/N 214 into the system under WO 99046067-01.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIRIREPLACEMENT Conforms to Section XI of the ASME Code.

Signed: John H.

ounq ISI COORDINATOR Jan.22*

• 2002 (Owner or Owner's Designee)'

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State orgrovince of Illinois, employed by Hartford Steam Boiler of CT having inspected the REPAIR/REPLACEMENT described in this report on

/ - rZ3., 202'2-.

and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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.

11.

Date: /

Y Inspector: Robert T. Rainey Commissions:

1L932, NB7742NISB (State or Province, National Board)

I

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P,O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

NWS Technologies (Name) 131 Venture Blvd. Spartanburg, SC 29301 (Address)

Date:

08-28-2000 Sheet:

1 Of 2 Unit:

2 PC) 000239-Re1.0003 PLAN 2-99-038 Repair Organization P.O. No., Job No. etc.

4. Identification of System:

0203 (Main Steam)

5. (a)

Construction Code **ASME Section III 1968 Edition, W/68 Addenda, Code Cases NONE (b)

Edition of Section Xl used for Repair/Replacement 19 8.9 Edition, NO Addenda, Code Cases NONE

• • General Electric APED Specification 21A9206, rev.6.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Target Rock Relief Valve.

Target Rock Corp.

S/N: 223 N/A Body S/N: 214 Unknown Repair Yes Target Rock Relief Valve.

Target Rock Corp.

S/N: 223 N/A Cat ID-008070, Unknown Repaired Yes UTC-2062534 Target Rock Relief Valve Target Rock Corp.

Not recorded N/A P/N: 200243-1 Unknown Replaced No 2nd stage disc.

Target Rock Relief Valve Target Rock Corp.

S/N: 872 N/A Cat ID-08081, Unknown Replacement No 2'd stage disc.

UTC-2073446

7. Description of work: NWS to refurbish/test set pressure spare TRV. OEM parts used were items drawn/sent from Dresden Station Stores Dept.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [

Nominal Operating Pressure [

Not Applicable [ X I Test Pressure _

psig Test Temperature __ °F

9. Remarks: Satisfactory VT-2 examination was recorded during the D2R17 10 Yr Hydro under WO 99124181-09. Reference Repair/Replacement Plan 2 01-027 that recorded Replacement valve system S/N 223 into the system under WO 99120951-01.

Certificate of Compliance We certify that the statements made in this report are correct and this REPAIR/REPLACEMENT Conforms to Section XI of the ASME Code.

Signed: John H. Youing Ou

-Af "

ISI COORDINATOR -____Jan.22

, 2002 (Owner or Owner's Designee) I (Title)

(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 Qr Province of Illinois, employed by Hartford Steam Boiler of CT having inspected the REPAIR/REPLACEMENT described in this report on 47-

,f.2002-.

and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XA of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this 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:

/

X 3.

-4'nspector: Robert T. Rainey

/

/

Commissions:

11-932, NB7742NISB

-(State or Province, National Board)

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

Date:

08-28-2000 Sheet: 2 Of 2 Unit:

2 P0 flflO2.9-RnlI lNN3 PI AN *)-.Q~-O*R Repair Organization P.O. No., Job No. etc.

4. Identification of System:

0203 (Main Steam)

5. (a) Construction Code **ASME Section 111 1968 Edition, W/68 Addenda, Code Cases NONE (b)

Edition of Section Xl used for Repair/Replacement 19 89 Edition, NO Addenda, Code Cases NONE General Electric APED Specification 21A9206, rev.6.

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No Target Rock Relief Valve Target Rock Corp.

Not recorded N/A P/N: 200242-1 Unknown Replaced No pilot disc.

Target Rock Relief Valve Target Rock Corp.

S/N: 601 N/A Cat ID-08086, Unknown Replacement No pilot disc.

UTC-2049404

F, I

-Iff w

V6 56

.9191 IL to cp

.0.

31 of le IC tr LLI JI

FORM NIS-2 OWNER'S REPORT FOR REPAIR OR REPLACEMENTS As Required by the Provisions of ASME Code Section XI

1. Owner: Exelon Nuclear (Name)

P.O. Box 805379. Chicago IL, 60680-5379 (Address)

2. Plant: Dresden Nuclear Power Station (Name) 6500 North Dresden Road, Morris IL., 60450 (Address)

3. Work Performed By:

Same as Above (Name)

Same as Above (Address)

Date:

1-24-2001 Sheet:

1 Of 1 Unit:

2 WR 990053038-01 (PLAN 2-99-054)

Repair Organization P.O. No., Job No. etc.

4. Identification of System:

3900 Service Water (Diesel Generator Cooling Water)

5. (a)

Construction Code USAS B31.1.0 19 67 Edition, NO

Addenda, Code Cases NONE (b)

Edition of Section XI used for Repair/Replacement 19 89 Edition, NO

Addenda, Code Cases NONE

6. Identification of Components Repaired or Replaced and Replacement Components Name of Name of Mfrs.

Nat Other Year

Repair, Code Component Manufacturer Serial No.

Brd ID Built Replaced or Stamped No Replacement Yes/No 8" X 6" X 6" Concentric Unknown Unknown N/A EPN 2-3903 N/A Replaced No Expansion Joint 5/8" Bolting Unknown Unknown N/A EPN 2-3903 N/A Replaced No (Bolts, Nuts and Washers) 3/4" Bolting Unknown Unknown N/A EPN 2-3903 N/A Replaced No (Bolts, Nuts and Washers) 8" X 6" X 6" Concentric Proco Products, Inc.

Unknown N/A Cat ID 37883 N/A Replacement No Expansion Joint 5/8" Bolting Unknown Unknown N/A Cat ID 3192, 37029, N/A Replacement No (Bolts, Nuts and Washers) and 5227 3/4" Bolting Unknown Unknown N/A Cat ID 39295, N/A Replacement No (Bolts, Nuts and Washers) 37031, and 30154.

7. Description of work: Replaced existing expansion joint on suction piping of Unit 2 Diesel Generator Cooling Water pump with new expansion joint as preventative maintenance. Flange bolting replaced rather than cleaning and reinstalling existing material.

8. Test Conducted: Hydrostatic [ ]

Pneumatic [

Nominal Operating Pressure [X ]

Not Applicable []

Test Pressure 3.5. psig Test Temperature Ambient OF

9. Remarks: VT-2 examination performed at nominal operating pressure, no evidence of leakage noted.

Certificateof Compliance We certify that the sta emeqts made in this report are correct and this REPLACEMENT Conforms to Section Xl of the ASME Code.

Signed:

ISI COORDINATOR 1/24

, 20

.L

,,/-fOWn-err Owner's Designee)

(Title)

(Date)

Certificate of Inspection I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois, employed by The Hartford Steam and Boiler Insurance and Inspection Co. of Hartford, Connecticut having inspected the REPLACEMENT described in this report on

/-*

a. 4;-,

20_[._ and state to the best of my knowledge and belief, this repair or replacement has been constructed in accordance with Section XI of the ASME Code. By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair or replacement described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss)f any ki d arisinaom or connected with this inspection.

Date: / Z L0 / Inspector:

Z_

Commissions:

,L932, NB7742NISB (State or Province, National Board)