SVPLTR 05-0007, Owner'S Activity Report Submittal Fourth 10-Year Interval 2004 Refueling Outage Activities

Owner'S Activity Report Submittal Fourth 10-Year Interval 2004 Refueling Outage Activities

ML050740371
Person / Time
Site:	Dresden
Issue date:	03/07/2005
From:	Bost D Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR #05-0007
Download: ML050740371 (8)

Text

Exeloii`Generation Company, LLC www.exeloncorp.com Exelkn.

Dresden Nuclear Power Station NuClear 65oo North Dresden Road Morris. IL60450-9765 March 7, 2005 SVPLTR #05-0007 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:

Owner's Activity Report Submittal Fourth 10-Year Interval 2004 Refueling Outage Activities This letter submits the Owner's Activity Report (i.e., Form OAR-1) and Invessel Visual Inspection (IWI) Report for the Dresden Nuclear Power Station (DNPS) Unit 3 refueling outage (D3R18) which began on October 26, 2004, and was completed on December 7, 2004. This is the first refueling outage conducted in the first inspection period of the fourth 10-year inservice inspection interval for DNPS Unit 3. A copy of the Owner's Activity Report and IWI Report are provided as attachments to this letter.

This Owner's Activity Report is submitted in accordance with American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Case N-532-1, 'Alternate Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission," and Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section Xl, Division 1," Revision 13. Code Case N-532-1 requires an Owner's Activity Report Form OAR-1 to be prepared and certified upon completion of each refueling outage. In accordance with the conditions of Regulatory Guide 1.147, this OAR-1 form is being submitted within ninety days of the completion of the refueling outage.

The IWI report meets the reporting requirements of BWRVIP-18, "BWR Vessel and Internals Project, BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines" and BWRVIP-94, "BWR Vessel and Internals Project Program Implementation Guide."

oq1,

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

Respectfully, Danny,,,. Bost Site \ice President Dresden Nuclear Power Station Attachments: Owner's Activity Report, Form OAR-1 Invessel Visual Inspection Report cc: Regional Administrator- Region IlIl NRC Senior Resident Inspector, Dresden Station

bcc: Director - Licensing, Mid-West Regional Operating Group (K. Jury)

Plant Manager - Dresden Nuclear Power Station Regulatory Assurance Manager - Dresden Nuclear Power Station Regulatory Assurance Manager - Quad Cities Nuclear Power Station (W. Beck)

Manager - Licensing - Dresden and Quad Cities Stations (P. Simpson)

Illinois Emergency Management Agency - Division of Nuclear Safety Manager of Energy Practice - Winston and Strawn Site Engineering Director - Dresden Nuclear Power Station (M. Kanavos)

Engineering Programs Supervisor - Dresden Nuclear Power Station (J. Sipek) -

Hartford Steam Boiler Inspection and Insurance Company Attn. Mr. Paul Fisher R. Bauman, ISI Coordinator- Dresden Nuclear Power Station H. Do, NGG ISI Engineer R. Rainey - ANII Dresden Nuclear Power Station Document Control Desk - Licensing Dresden Regulatory Assurance, SVP Letter File SVP Numerical File - SVPLTR #05-0007

FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number Refueling Outage D3R18 OAR-1 Owner Exelon Generation Company (EGC, LLC), 200 Exelon Way, Kennett Square. PA, 19348 (Name and Address of Owner)

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

Unit No. 3 Commercial Service Date 11-16-1971 Refueling outage no. D3R18 (ifapplicable)

Current inspection interval 4' Inspection Interval (1st, 2nd, 3rd, 4th, other)

Current Inspection period 1" Inspection Period

({st,2nd, 3rd)

Edition and Addenda of Section Xi applicable to the inspection plan 1995 Edition with 1996 Addenda Date and revision of inspection plan 05-30-2004, Revision 2 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan NIA CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owners Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report conform to the requirements of Section Xi.

Certificate of Authorization No. None Expiration Date Not Applicable (if applicable)

Signed orDate O2' SICoordinator -e-wesDesignee, Title ero CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Illinois , and employed by The Hartford Steam and Boiler Insurance and Inspection Co. of Hartford. Connecticut have inspected the items described in this Owners Activity Report, during the period 01-20-2003 to 01-17-2005 , and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations tests, repairs, replacements, evaluations, and corrective measures 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 inspecti 7 I

____________Commissions IL 932, NB7742NISB National Board. State. Province. and Endorsements Date D3R18 OAR-1 Page 1 of4

TABLE I ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Total Examinations Examinations Examinations Examinations Credited (%) Credited (%) To Examination Required for Credited for For The Date for The Category The Interval This Period Period Interval Remarks B-A 2 0 0 0 Components scheduled in accordance with Program B.

One during the second inspection period and one during the third inspection period.

-21 0 0 0 Deferral Permissible B-D 62 14 23 23 Components scheduled in accordance with Program B.

B-G-1 8 3 38 38 Deferral Permissible B-G-2 37 8 22 22 Components scheduled in accordance with Program B.

1 1 100 100 Examinations limited to components selected under Examination Category B-L-2 and B-M-2.

B-K 11 3 27 27 Components scheduled in accordance with Program B.

B-L-2 1 I 100 100 Examinations limited to disassembled components.

B-M-1 1 0 0 0 Deferral Permissible B-M-2 5 5 100 100 Examinations limited to disassembled components.

B-N-1 3 0 0 0 One component examined each inspection period.

B-N-2 79 1* 1 I Deferral Permissible

• Portions of Core Support Structure Made Accessible B-0 8 0 0 0 Deferral Permissible B-P 10 2 20 20 Two pressure tests performed each refuel outage.

C-A 2 0 0 0 Components scheduled in accordance with Program B.

One during the second inspection period and one during the third inspection period.

C-B 12 2 17 17 Components scheduled in accordance with Program B.

18 0 0 0 Six components examined each inspection period.

C-C 11 3 27 27 Components scheduled in accordance with Program B.

C-H 36 4 11 11 Twelve pressure tests performed each inspection period.

F-A 154 42 27 27 Components scheduled in accordance with Program B.

R-A 69 15 22 22 Components scheduled in accordance with Program B.

110 22 20 20 Twenty two components examined each refuel outage.

D3R18 OAR-1 Page 2 of 4

TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Item Flaw Flaw or Relevant Condition Found Category Number Description Characterization During Scheduled Section Xl (IWA-3300) Examination or Test (Yes or No)

No items with flaws or relevant conditions required evaluation for continued service during the period covered by this report.

D3R18 OAR-1 Page 3 of 4

TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Code Repair, Item Description Flaw or Relevant Date Repair/

Class Replacement, Description of Work Condition Found Completed Replacement or Corrective During Scheduled Plan Number Measure Section Xl Examination or Test (Yes or No) 1 Corrective Main steam sensing line support. Replaced broken rod hanger No 11/23/2004 3-04-063 Measure assembly.

2 Corrective HPCI Support M-1187D-75 Tightened loose bolted No 5/6/2004 N/A Measure connection.

2 Corrective HPCI Support M-1 187D-83 Adjusted unloaded support. No 11/19/2003 N/A Measure 2 Corrective HPCI Support M-1187D-98 Tightened loose bolted No 5/6/2004 N/A Measure connection.

2 Repair Integral Welded Attachment Removed flaws and performed Yes 10/13/2003 3-03-017 M-1200D-1015 welded repair.

2 Repair Integral Welded Attachment Removed flaws and performed Yes 12/17/2003 3-03-034 M-1200D-1019 welded repair.

D3R18 OAR-1 Page 4 of 4

r -

Invessel Visual Inspection Report D3R1 8 Core Spray System Examinations Previously identified Core Spray flaws have been addressed through lower sectional piping replacement of all four Core Spray lines. The lower sectional piping replacement replaced welds P4c, P4d, P5, P6, P7, P8a, P8b and P9 and removed all previously identified flaws on the Unit 3 Core Spray piping. The welds on the lower sectional replacement assemblies are not susceptible to IGSCC and will not require future inspections. The remaining Core Spray piping welds were visually examined during D3R1 8 as recommended in BWRVIP-1 8, "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines." Additionally, all 8 of the Core Spray piping brackets were visually inspected after completion of the lower sectional replacement. No flaws were identified in the piping welds or the brackets.

Steam Dryer EPU Inspections Detailed steam dryer inspections were performed in accordance with GE SIL 644 recommendations. Additional dryer component surfaces were examined to verify that the conditions previously identified at Quad Cities and Dresden were not present on the Dresden unit 3 dryer. During this inspection, flaws were identified in the support ring to the cover plate welds on the outer hoods and also in the outer hood vertical plate to dryer support ring welds. No loose parts were generated as a result of these flaws. The flaws were ground out and weld repairs performed. Additionally, the outer hoods were modified to address indications seen at Quad Cities in 2004. These modifications replaced the outer hood vertical plate with a 1" plate, extended the outer hood gussets and replaced the outer tie bars. These changes significantly reduced the stresses in the areas where the flaws were found. Additional indications found during the dryer inspection were determined to be non-structural and were either repaired or dispositioned for continued use.

Core Shroud Vertical Weld Inspections The core shroud ring segment welds associated with the shroud head flange ring (VI-V4), top guide support ring (V8-V13), and core plate support ring (V20-V25) were visually inspected in accordance with the requirements of BWRVIP-76, "BWR Core Shroud Inspection and Flaw Examination Guidelines." Vertical oriented cracking in the vicinity of welds V23 and V25 was previously identified during D3R14. The D3R18 inspection resulted in no observed increase in indication size. Therefore, the identified cracking remains bounded by the current flaw evaluation. No new flaws were identified in the remaining vertical core shroud ring segment *velds.