SVPLTR 05-0008, Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report

Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report

ML050740374
Person / Time
Site:	Dresden
Issue date:	03/07/2005
From:	Bost D Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR #05-0008
Download: ML050740374 (18)

Text

Exeklnn Exelon Generation Company, LLC www.exeloncorp.com Nucear Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450-9765 March 7, 2005 SVPLTR #05-0008 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Dresden Nuclear Power Station, Unit 3 Facility Operating License No. DPR-25 NRC Docket No. 50-249

Subject:

Final Third 10-Year Interval Inservice Inspection (ISI) Summary Report

References:

1) Letter from R. J. Hovey, (Exelon Generation Company, LLC) to U. S. NRC, "Inservice Inspection (ISI) Summary Report Fall 2002 Inservice Inspection Period," dated January 24, 2003.

2) Letter from L. W. Rossbach (U. S. NRC) to 0. D. Kingsley (Exelon Generation Company, LLC), "Exemption from the Requirements of 10 CFR 50.55a(g)(6)(ii)(A)(2), Inservice Examination of the Reactor Pressure Vessel," dated September 28, 2001 Enclosed is the Dresden Nuclear Power Station (DNPS) Unit 3 final Inservice Inspection (ISI)

Summary Report for ISI examinations and repair/replacement activities conducted since the last report, (Reference 1) for the Third 10-Year Interval. This report is submitted 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," 1989 Edition, Article IWA-6200, 'Requirements."

The Unit's third 10-Year ISI Interval began on March 1, 1992, and was completed on October 31, 2003. All scheduled ASME Section Xi examinations were completed prior to October 31, 2003, with the exception of Examination Category B-A reactor vessel shell welds. Approval to delay reactor vessel shell weld inspections was provided by the NRC in Reference 2.

Examination Category B-A examinations were completed during the Unit 3 refueling outage (D3R18) which began on October 26, 2004, and was completed on December 7, 2004.

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March 7, 2005 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. Pedro Salas, Regulatory Assurance Manager, at (815) 416 - 2800.

Respectfully, Danny Bost Site Vice President Dresden Nuclear Power Station

Attachment:

Inservice Inspection 90 Day Summary Report cc:

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

Exelon Generation Company (EGC, LLC) 200 Exelon Way, Kennett Square, PA, 19348 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 October 2004 Inservice Inspection Unit No. 3; National Board No. N-139 Commercial Service Date: 11-16-71 Table of Contents Introduction Form NIS-1 Owners Report for Inservice Inspections Scope of Inspection Abstract of ISI and Augmented Examinations Abstract of Corrective Measures Abbreviations Repairs and Replacements Since the Preceding Summary Report II 111 III IV V

1

Exelon Generation Company (EGC, LLC)

October 2004 Inservice Inspection 200 Exelon Way, Kennett Square, PA, 19348 Unit No. 3; National Board No. N-139 Commercial Service Date: 11-16-71 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section I Introduction The eighteenth Inservice Inspection (ISI) of Dresden Unit 3 was performed during the D3R18 outage which began on October 26, 2004 and was completed on December 7, 2004. This was the final refueling outage of the unit's 3rd 10-year Inservice Inspection Interval which commenced on March 1, 1992. The third inspection period commenced on November 1st, 1999 and was completed on October 31, 2003. All of the scheduled ASME Section Xl examinations were completed on-line prior to October 31, 2003 with the exception of Examination Category B-A reactor vessel shell welds. The reactor vessel shell welds were completed during the D3R1 8 refueling outage in accordance with a schedular exemption which extended the 3rd 10-year Inservice Inspection Interval. This report summarizes the reactor vessel weld examinations completed during D3R18 and on line examinations which were completed since the previous Unit 3 Summary Report (dated January 24, 2003).

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, and the ASME Boiler and Pressure Vessel Code, Section Xl, 1989 Edition.

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 Generation Company (EGC, LLC), 200 Exelon Way, Kennett Square, PA, 19348 (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 3

4. Owner Certificate of Authorization (if required)

N/A

5. Commercial Service Date 11-16-71

6. National Board Number for Unit N-139

7. Components Inspected See Section II of this report (report is 16 total pages).

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

Board No.

Serial No.

Reactor Vessel Babcock & Wilcox, 610-0111-51-52 B0082900 N-139 Barberton, Ohio Class I & 2 Systems General Electric-APED N/A N/A N/A Morris, IL I

I I __

I __

I Note: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8'/2 in. x I 1 l2 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

FORM NIS-1 (Back)

8. Examination Dates:

01/07/2003 to 12/07/2004

9. Inspection Period Identification:

3'd Period - From 11/1/1999 to 10/31/2003

10. Inspection Interval Identification:

3rd Interval - From 3/1/1992 to 10/31/2003*

• Category B-A examinations were completed after the stated date in accordance with a scheduler exemption.

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

12. Date/Revision of Inspection Plan:

04/01/2003 Revision 8

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 11 and 111.

14. Abstract of Results of Examinations and Tests. See Attached Sections 11 and Ill.

15. Abstract of Corrective Measures. See Attached Sections 11 and 111.

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)

N/A Expiration Date N/A Date 2

. 21 20 05 Signed Exelon Nuclear Dresden Nuclear Power Station.

By XDresden Station ISI Coordinator Owner CERTIFICATE OF INSERVICE INSPECTION 1, 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 01/07/2003 To 12/07/2004

, 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.

/94?

/IL 4

Commissions NB7742NISB, IL932 Insl{ector's Signature National Board, State, Province, and Endorsements Date 0-,. 3 -°II 20 05 4

Exelon Generation Company (EGC. LLC)

October 2004 Inservice Inspection 200 Exelon Way, Kennett Square, PA, 19348 Unit No. 3; National Board No. N-139 Commercial Service Date: 11-16-71 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section 11 Scope of Inspection Abstract of ISI and Auqmented Examinations ISI and Augmented Examinations Table A contains a list of components examined on-line prior to completion of the 3rd 1 0-Year Inservice Inspection Interval and Examination Category B-A examinations performed during the D3R18 refueling outage. These examinations are in accordance with the Dresden Station [SI Program, Dresden Station Technical Requirements Manual, and the ASME Boiler and Pressure Vessel Code, Section Xl, 1989 Edition. Those items which were examined and meet the acceptance standards of ASME Section Xl are identified as "Acceptable" under the results column. Those items that required further evaluation are identified with "Section lIt" in the results column and are further discussed in Section III of this report.

Reactor Vessel Weld (Category B-A) Examinations The Unit 3 reactor vessel shell welds are examined as required by 1 OCFR50.55(a) and ASME Section Xl. These welds are addressed under Examination Category B-A. Two relief requests were associated with these inspections. First, relief was requested, and subsequently granted, from requirements to examine circumferential shell welds. The technical basis for this request is established in BWRVIP-05. Second, a schedule exemption was requested, and subsequently approved, to allow performance of reactor vessel shell weld inspections over an additional refueling outage which was after the scheduled completion of the 3rd 1 0-Year Inservice Inspection Interval. Otherwise, the entire inspection would have been required during D3R1 7, the last outage in the third inspection interval. The basis of this request was to allow the station to take advantage of a new inspection technology, the AIRIS 21 system, to achieve an increased coverage without significantly impacting the outage.

5

Exelon Generation Company (EGC, LLC) 200 Exelon Way, Kennett Square, PA, 19348 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 October 2004 Inservice Inspection Unit No. 3; National Board No. N-139 Commercial Service Date: 11-16-71 Section 11 Scope of Inspection Abstract of ISI and Aucmented Examinations Current Interval Status The percentages listed in the table below represent the status of inspections for the 3rd 10-Year Inservice Inspection interval. This report documents completion of the 3rd 10-Year Inservice Inspection Interval.

Examination Deferral Is permissible in Inspected in accordance Category accordance with Table with Inspection Program B IWX-2500-1 B-A 100%

100%

B-D N/A 100%

B-E 100%

N/A B-G-1 100%

N/A B-G-2 100%'

100%

B-M-1 100%

N/A B-M-2 100%'

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

B-N-2 100%

N/A B-O 100%

N/A C-A N/A 100%

C-B N/A 100%

C-C N/A 100%

D-B N/A 100%

F-A N/A 100%

R-A N/A 100%

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

6

Exelon Generation Company (EGC, LLC) 200 Exelon Way, Kennett Square, PA, 19348 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 October 2004 Inservice Inspection Unit No. 3; National Board No. N-139 Commercial Service Date: 11-16-71 Section 11 Scope of Inspection Abstract of ISI and Auqmented Examinations Categor y.Item1 Augment RPSystem

.R.

V SHneL3..L-"

Component O. N Tye Exam xCeit 0Resulta bl B-A B1.12 N/A RPV RPVSHELL 3-SC2B-VERT LONG UT Xi Acceptable B-A B1.12 N/A RPV RPV SHELL 3-SC2A-VERT LONG UT Xi Acceptable B-A B1.12 N/A RPV RPV SHELL 3-SC2C-VERT LONG UT Xi Acceptable B-A B1.12 N/A RPV RPV SHELL 3-SC3B-VERT LONG UT Xl Acceptable B-A B1.12 N/A RPV RPV SHELL 3-SC4B-VERT LONG UT Xi Acceptable B-A B1.51 N/A RPV RPV SHELL MRA-013-1 REPAIR UT Xi Acceptable B-A B1.51 N/A RPV RPV SHELL MRA-013-2 REPAIR UT Xl Acceptable C-B C2.31 N/A ECCS 1501-20 20-10 SDL-SHL MT Xl Acceptable C-B C2.31 N/A ECCS 1501-20 20-12 SDL-SHL MT XI Acceptable C-C C3.10 N/A LPCI HTEX 3A-1503 M-1200D-1015 IWA MT Xl BL See Section III C-C C3.10 N/A LPCI 0TEX 38-1503 M-1200D-1019 IVA MT AD BL See Section ll C-C C3.20 N/A CRD 0386-8 M-1188D-1046 IVA MT Xi Acceptable C-C C3.20 N/A CRD 0387-8 M-1188D-1054

[WA MT Xi Acceptable C-C C3.20 N/A CRD 04093-20 M-1188D-1001 IWA MT Xi Acceptable C-C C3.20 N/A CS 1403-12 M-3409-26 IWA MT Xi Acceptable C-C C3.20 N/A CS 1404-12 M-3408-08 IWA MT Xi Acceptable C-C C3.20 N/A CS 1404-12 M-3408-10 IWA MT Xi Acceptable C-C C3.20 N/A ECCS 1501-24 M-3402-03 IWA MT Xi Acceptable C-C C3.20 N/A ECCS 1501 -24 M-3402-04 IWA MT Xi Acceptable C-C C3.20 N/A ECCS 1501-24 M-3402-05 IWA MT Xi Acceptable C-C C3.20 N/A ECCS 1501-24 M-3402-06 IWA MT Xi Acceptable C-C C3.20 N/A ECCS 1501-24 M-3402-07 IWA MT Xi Acceptable C-C C3.20 N/A ECCS 1501-24 M-3402-08 IWA MT Xl Acceptable C-C C3.20 N/A HPCI 2304-14 M-1187D-86 IWA MT Xi Acceptable C-C C3.20 N/A HPCI 2306-24 M-3412-03 (1/2)

IWA MT Xl Acceptable C-C C3.20 N/A LPCI 1502-24 M-3404-09 IWA MT Xi Acceptable C-C C3.20 N/A LPCI 1504-18 M-3414-10 IWA MT Xi Acceptable C-C C3.20 N/A LPCI 1506-18 M-3409-10 IWA MT Xi Acceptable C-C C3.20 N/A LPCI 1534-18 M-3414-09 IVA MT Xi Acceptable C-H C7.XX N/A CRD TEST BLOCK 3RC02 N/A VT-2 Xi Acceptable C-H C7.XX N/A SBLC TEST BLOCK 3SC02 N/A VT-2 Xl Acceptable D-B D2.IA N/A D-B D2.1A 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 CCSW 1514C-8 CCSW 1514C-8 CCSW 1514D-8 DGSW 3930-8 ISCO 3-1302 ISCO 3-1302 ISCO 3-1302 DGSW TEST BLOCK M-1200D-260 M-1200D-260 M-1200D-259 2/3-3930-1 M-11199D-1022 M-1199D-1023 M-1199D-1024 2/3DG01 IWA IWA IWA flVA IWA IWA IWA N/A VT-3 Xl VT-3 BL VT-3 BL Vr-3 XI VT-3 Xi VT-3 Xi VT-3 Xi VT-2 Xi Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable Acceptable See Section III 7

Exelon Generation Company (EGC, LLC) 200 Exelon Way, Kennett Square, PA, 19348 October 2004 Inservice Inspection Unit No. 3; National Board No. N-139 Commercial Service Date: 11 71 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section 11 Scope of Inspection Abstract of ISI and Augmented Examinations ICategory' tem,'-Augmnent':. System

.- Line Component Type:' '- Exam Credit.'

':'Results' I

D-B D2.XX N/A DGSW TEST BLOCK 2/3DG03 N/A VT-2 Xi Acceptable D-B D2.XX N/A DGSW TEST BLOCK 3DG03 N/A VT-2 Xl Acceptable F-A F1.10 N/A F-A F1.20 N/A F-A F1.20 WA 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 NMA 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 F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 NWA F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 N/A F-A F1.30 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 F-A F1.40 N/A F-A F1.40 N/A LPCI CS CS ECCS ECCS HPCI HPCI ISCO LPCI LPCI LPCI LPCI LPCI LPCI CCSW CCSW DGSW DGSW DGSW DGSW DGSW DGSW DGSW DGSW DGSW DGSW DGSW DGSW DGSW DGSW DGSW DGSW 1519-16 1402-16 1404-12 1501-20 1501-24 2304-14 2306-24 1303-12 1509-16 1509-18 1509-18 1519-18 1521-6 1530-18 11514C-8 11514D-8 3930-8 3930-8 3930-8 3930-8 3930-8 3930-8 3930-8 3930-8 3930-8 3930-8 3930-8 3930-8 3931-8 3931-8 3950-8 3950-8 X-1 16A-F M-3403-04 M-3408-06 M-3230-10 M-3402-13 M-1 187D-104 M-3412-06 M-1 199D-6 M-3413-31 M-3413-11 M-3413-12 M-3408-20 M-3413-08 M-3413-10 M-1200D-260 M-1200D-259 3930-M-320 M-1198D-114 M-1198D-119 M-1198D-133 M-1198D-137 M-1198D-164 M-1198D-169 M-1198D-181 M-1 198D-571 M-1 198D-584 M-1 198D-64 M-1198D-72 M-1 198D-592 M-1 198D-90 M-1 162D-295 M-1 198D-552 3D-1501-44 2/3-3903B 3-3903B 3-2302 M-1 200D-309 M-1200D-310 CL1 SUP VT-3 Xi CL2 SUP VT-3 Xl CL2 SUP VT-3 Xl CL2 SUP VT-3 Xi CL2 SUP VT-3 Xi CL 2 SUP VT-3 Xi CL 2 SUP VT-3 Xi CL2 SUP VT-3 Xi CL 2 SUP VT-3 Xi CL 2 SUP VT-3 Xi CL2SUP VT-3 Xi CL2SUP VT-3 Xi CL2SUP VT-3 Xi CL2 SUP VT-3 Xi CL3SUP VT-3 BL CL3SUP VT-3 BL CL3SUP VT-3 Xi CL3SUP VT-3 Xi CL3 SUP VT-3 Xi CL3SUP VT-3 Xi CL-3SUP VT-3 Xi CL3 SUP VT-3 Xi CL3SUP VT-3 Xl CL3SUP VT-3 Xi CL3 SUP VT-3 Xi CL3SUP VT-3 Xi CL3 SUP VT-3 Xl CL3SUP VT-3 Xi CL3SUP VT-3 Xi CL3 SUP Vr-3 Xi CL3 SUP VT-3 Xi CL3SUP VT-3 Xi CL3SUP VT-3 Xi CL3SUP VT-3 Xi CL3SUP VT-3 Xi CL2SUP VT-3 Xi CL2 SUP VT-3 Xi CL2SUP VT-3 Xi 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 CCSW PMP 3D-1501-44 DGSW PMP 2/3-3903B DGSW PMP 3-3903B HPCI PMP 3-2302 LPCI HTEX 3B-1 503 LPCI HTEX 3B-1 503 R-A R1.11 N/A HPCI 2306-24 24-17 EL-P UT-E XI Acceptable 8

Exelon Generation Company (EGC, LLC) 200 Exelon Way, Kennett Square, PA, 19348 October 2004 Inservice Inspection Unit No. 3; National Board No. N-139 Commercial Service Date: 11-16-71 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section 11 Scope of Inspection Abstract of ISI and Augmented Examinations l Category..Ite-rn'<.*Augment Sytem

, Line

'Component i'

' Type '

Exam' Credit Results ;

R-A R1.1 1 N/A HPCI 2306-24 R-A R1.20 N/A ECCS 1501-24 R-A R1.20 NIA ECCS 1501-24 R-A R1.20 N/A ECCS 1501-24 R-A R1.20 N/A ECCS 1501-24 R-A R1.20 N/A ECCS 1501-24 R-A R1.20 N/A ECCS 1501-24 R-A R1.20 N/A HPCI 2302-16 R-A R1.20 N/A HPCI 2304-14 R-A R1.20 N/A LPCI 1502-24 R-A R1.20 N/A LPCI 1507-24 R-A R1.20 N/A LPCI 1509-10 24-18 24-23 24-25 24-43 24-47 24-48 24-52 16-4 14-31 24-4 24-2 10-42 P-EL UT-E Xi Acceptable P-TEE UT-E XI Acceptable TEE-P UT-E XI Acceptable P-P UT-E Xi Acceptable P-P UT-E XI Acceptable P-P UT-E XI Acceptable P-P UT-E XI Acceptable P-EL UT-E Xi Acceptable P-EL UT-E Xi Acceptable P-EL UT-E Xi Acceptable P-EL UT-E Xi Acceptable P-EL UT-E Xi Acceptable 9

Exelon Generation Company (EGC, LLC) 200 Exelon Way, Kennett Square, PA, 19348 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 October 2004 Inservioe Inspection Unit No. 3; National Board No. N-139 Commercial Service Date: 11-16-71 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, and the ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition.

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

10

Exelon Generation Company (EGC, LLC)

October 2004 Inservice Inspection 200 Exelon Way, Kennett Square, PA, 19348 Unit No. 3; National Board No. N-139 Commercial Service Date: 11 71 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section III Abstract of Corrective Measures l CategoryI.-Utem

-Augment

.;System K Line Component

.Type; C-C C3.10 LPCI HTEX 3A-1503 M-1200D-1015 IWA During MT examination of 3A LPCI heat exchanger tWA M-1200D-1015, two linear indications were discovered.

Condition Report 178950 was Initiated to document the as-found condition. Weld repairs were performed under Work Order 420251. Welds were examined after repairs were performed and found acceptable. Since one welded attachment on the 3A LPCI heat exchanger was Initially examined, the remaining similar welded attachment associated with the 3B LPCI heat exchanger was expanded to.

C-C C3.10 LPCI HTEX 3B-1503 M-1200D-1019 IWA During MT examination of 3B LPCI heat exchanger IWA M-1 200D-1 019, five linear indications were discovered.

Condition Report 189106 was Initiated to document the as-found condition. Weld repairs were performed under Work Order 420251. Welds were examined after repairs were performed and found acceptable. Since all similar welded attachments associated with the 3A and 3B LPCI heat exchangers were examined, no additional expansion was performed.

D-B D2.XX DGSW TEST BLOCK 2/3DG01 NIA During the system pressure test, leakage was discovered at 213-6669B, DGCW Heat Exchanger head (bolted connection) and 2/3-3930-501, DGCW Pump Discharge Check Valve (bolted connection). Initiated Condition Report 151656 to assess the discrepancy. Corrective measures were taken in accordance with Relief Request PR-22.

Leakage at 2/3-6669B was stopped and leakage at 213-3930-501 was evaluated. Therefore, removal of bolting and performance of a VT-3 examination was not required In accordance with the alternate provisions of Relief Request PR-22. No further action required.

11

Exelon Generation Company (EGC, LLC)

October 2004 Inservice Inspection 200 Exelon Way, Kennett Square, PA, 19348 Unit No. 3; National Board No. N-139 Commercial Service Date: 11-16-71 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 RT Radiograph 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 Xl ASME Section Xl Requirement System CCSW Containment Cooling Service Water CRD Control Rod Drive CS Core Spray DGSW Diesel Generator Service Water ECCS Emergency Core Cooling System Ring Header FW Feedwater HPCI High Pressure Coolant Injection ISCO Isolation Condenser LPCI Low Pressure Coolant Injection MS Main Steam RHS Reactor Head Spray RPV Reactor Pressure Vessel RR Reactor Recirculation RVBD Reactor Vessel Bottom Drain SBLC Standby Uquid Control SDC Shutdown Cooling 12

Exelon Generation Company (EGC, LLC)

October 2004 Inservice Inspection 200 Exelon Way, Kennett Square, PA, 19348 Unit No. 3; National Board No. N-139 Commercial Service Date: 11-16-71 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section IV Abbreviations Type BELLOW Bellows BLTCONN Bolted Connection BPC Branch Pipe Connection BPCS Branch Pipe Connection Saddle CAP Pipe Cap CL Class 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 SNB Snubber SUP Support 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 SWT Socket Welded Tee SWV Socket Welded Valve TBSHT Tubesheet TEE Tee 13

Exelon Generation Company (EGC, LLC) 200 Exelon Way. Kennett Square, PA, 19348 October 2004 Inservice Inspection Unit No. 3; National Board No. N-1 39 Commercial Service Date: 11-16-71 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section IV Abbreviations VB VLV VLVBLT VLVWLD Vacuum Breaker Valve Valve Bolting Valve Weld 14

Exelon Generation Company (EGC, LLC)

October 2004 Inservice Inspection 200 Exelon Way, Kennett Square, PA, 19348 Unit No. 3; National Board No. N-139 Commercial Service Date: 11-16-71 Dresden Nuclear Power Station 6500 N. Dresden Road, Morris, IL 60450 Section V Repairs and Replacements Since the Preceding Summary Report A review of the Dresden Station Section Xi Repair/Replacement Program Log was conducted in order to identify ASME Section Xl repair/replacement activities that have taken place at Dresden Unit 3 since the previous summary report was issued. One repair/replacement activity performed under the 1989 Edition of ASME Section Xi prior to transition to the Fourth 1 0-Year Inservice Inspection Interval was identified (Work Order 95060570-01). A Copy of the NIS-2 form has been included in this section.

15

r FORM NIS-2 OWNER'S REPORT FOR REPAIR/REPLACEMENT ACTIVITY As Required by the Provisions of the ASME Code Section XI

1. Owner Exelon Generation Company (EGC, LUC)

Name 200 Exelon Way, Kenriett Square, PA 19348 Address

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

01-07-04 Sheet 1

of 1

Unit 3

Work Order 95060570-01 (R/R Plan 3-02-083)

3. Work Performed by Same as Above Hepair/IHeoaCement Urganization F.U. NO. Job No. etc.

Type Code Symbol Stamp None Authorization No.

Not Applicable Expiration Date Not Applicable Same As Above Address

4. Identification of System 2300, High Pressure Core Iniection (HPCI), ASME Section XI, Class 2

5. (a) Applicable Construction Code USAS B31.1 1967

Edition, No

Addenda, (b) Applicable Edition of Section XI Used for Repair/Replacement Activity 1989

Edition, No

Addenda, No Code Case None Code Case

6. Identification of Components ASME National Corrected, Code Name of Name of Manufacturer Board Other Year Removed, or Stamped Component Manufacturer Serial No.

No.

Identification Built Installed (Yes

___or N o)

EPN 2-2320-GSLO Pump, Centrifugal Worthington Not Recorded N/A None Unknown Removed No Pump, 25 GPM, 160 ft Head, Centrifugal with associated flanges and 025075-CP-Cat ID 1030313 bolting Worthington 03 NIA UTC 2606646 Unknown Installed No Pipe, 1-1/2, sch. 80. A-1 06 Gr. B Unknown Unknown NIA None Unknown Removed No Pipe, 1-1/2, sch. 80, A-106 Heat Code Cat ID 4625 Gr. B Unknown A63145 N/A UTC 2063470 Unknown Installed No

7. Description of work Replaced pump and associated flanges and bolting. Piping replaced to facilitate installation.

8. Tests Conducted:

Hydrostatic [ I Pneumatic [ J Nominal Operating Pressure [X ]

Exempt Other [ J Pressure 50 psig Test Temp.

ambient OF

9. Remarks Applicable Manutacturer's Data Reports to be attached CERTIFICATE OF COMPUANCE I certify that the statements made In the report are correct and that this conforms to the requirements of the ASME Code, Section Xl.

Type Code Symbol Stamp N/A Certificate of Au

• zati, NoN NIA Expiration Date N/A Signed X

JISI Coordinator Date tF iX a ' ie~er or Owneres Desiqnee Title CERTIFICATE OF INSERVICE INSPECTION l, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois and employed by The Hartford Steam and Boiler Insurance and Inspection Co. of Hartford. Connecticut have Inspected the components described In this Owners Report during the period 03-19-2002 to 02-03203. and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described In this Owners report In accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described In this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable In any manner for any personal Injury or property damage or a loss of any kind arising fron, or connected with this inspection.

Commissions IL 932, NB7742NISB Z'Is refr)

Sionature National Board, State, Province, and Endorsements Date 2

4'