SVPLTR 07-0010, Owner'S Activity Report Submittal Fourth 10-Year Interval 2006 Refueling Outage Activities

Owner'S Activity Report Submittal Fourth 10-Year Interval 2006 Refueling Outage Activities

ML070590263
Person / Time
Site:	Dresden
Issue date:	02/20/2007
From:	Bost D Exelon Generation Co, Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR #07-0010
Download: ML070590263 (7)

Text

Exelkan.

Exelon Generation Company, LLC www.exeloncorp.coM Nuclear Dresden Nuclear Power Station 6500 North Dresden Road Morris, IL 60450-9765.

February 20, 2007 SVPLTR #07-0010 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 2006 Refueling Outage Activities This letter submits the Owner's Activity Report (i.e., Form OAR-i) and Invessel Visual Inspection (IVVI) Report for the Dresden Nuclear Power Station (DNPS) Unit 3 refueling outage (D3R19) whicti°began on November 3, 2006, and was completed on November 22, 2006. This is the first refueling outage conducted in the second inspection period of the fourth 10-year inservice inspection interval for DNPS Unit 3. A copy of the Owner's Activity Report and IVVI 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 14. 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 IVVI 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."

February 20, 2007 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. James Ellis, Regulatory Assurance Manager, at (815) 416-2800.

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

FORM OAR-I OWNER'S ACTIVITY REPORT Report Number Refueling Outage D3R19 OAR-1 Owner Exelon Generation Company (EGC, LLC), 300 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 IDate 11-16-1971 Refueling OutageNo. D3R19 (ifapplicable)

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

Current inspection period 2nd Inspection Period (I 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 09/15/2006 Revision 5 Edition and Addenda of Section XI applicable to repairs and replacements, if different than the inspection plan N/A CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's 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 jNot Applicable (if applicable)

Signed "t('

k ci. , ISI Coordinator Date 2 1/ ,,- 7 Owner or Owner's Designee, Title (¶ I-~

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 HSBCT of Hartford, Connecticut have inspected the items described in this Owner's Activity Report, during the period 02/18/2006 to 02/15/2007, 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 XI.

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 inspection.

• -.- Commissions IL 1546 Insoector's Sionature National Board. State. Province. and Endorsements Date -// - I)2

TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Total Examinations Examinations Examinations Examinations Credited (%) To Examination Required for Credited for Credited (%) Date for The Category The Interval This Period For The Period Interval Remarks B-A 2 1 50 50 Components scheduled in accordance with Program B.

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

23 0 0 0 Deferral Permissible B-D 62 5 8 34 Components scheduled in accordance with Program B.

B-G-1 8 0 0 38 Deferral Permissible B-G-2 37 7 19 41 Components scheduled in accordance with Program B.

1 0 0 100 Examinations limited to components selected under Examination Category B-L-2 and B-M-2.

B-K 11 4 36 64 Components scheduled in accordance with Program B.

B-L-2 N/A N/A N/A N/A Examinations limited to disassembled components.

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

B-N-1 1 0 0 100 One component examined each inspection period.

B-N-2 80 0 0 1 Deferral Permissible B-O 8 0 0 0 Deferral Permissible B-P 2 2 100 200 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 0 0 17 Components scheduled in accordance with Program B.

6 0 0 100 Six components examined each inspection period.

C-C 10 0 0 30 Components scheduled in accordance with Program B.

C-H 17 1 6 106 Eighteen pressure tests performed each inspection period.

F-A 154 41 27 54 Components scheduled in accordance with Program B.

R-A 71 20 28 52 Components scheduled in accordance with Program B.

24 24 100 200 Twenty-one components examined each refuel outage.

TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw Examination Item Characterization Flaw or Relevant Condition Found During Scheduled Section Xl Category Item Number Description (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.

TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Repair, Flaw or Relevant Condition Replacement, Found During Scheduled Repair/

Code or Corrective Section Xl Examination or Replacement Class Measure Item Description Description of Work Test (Yes/No) Date Completed Number U3 Target Rock Tightened Lock Nuts Corrective Snubber Lock Nuts To Proper Torque 1 Measure Found Loose Value No 11/18/06 N/A Loose Nuts On Corrective Penetration X-137 Torqued Penetration MC Measure Cover Cover Bolts. Yes 11/20/06 N/A 3A CCSW Pump Corrective Suction Support Found 3 Measure Unloaded Support Adjusted. No 9/14/06 N/A Spring Can For Support Corrective M-1 164D-88 Required Scheduled For 3 Measure Adjustment Adjust Support. Yes 4/19/07 N/A Loose Bracket Found Corrective On Iso Cdr Pipe 2 Measure Support Tightened Bracket. No 3/22/06 N/A

Dresden Unit 3 In-Vessel Visual Inspection Report Refueling Outage D3R19 Core Spray System Inspections During D3R18, Dresden performed a Lower Sectional Replacement (LSR) on all four Core Spray lines. The LSR replaced the piping with previously identified cracking. In D3R19, a visual inspection was performed on the LSR after one cycle of operation. The inspection included a VT-I of the accessible bolting and locking devices and a general visual examination (VT-3) to confirm the repair hardware is in place and has not shifted or changed from the installed condition. The inspection resulted in no relevant indications. (Note: All of the welds in the LSR are solution annealed after welding and are located in low carbon steel base material.

Fabrication requirements include appropriate measures from BWRVIP-84 to prevent surface cold work. Therefore, no periodic inspections of the welds in the LSR hardware are required.)

Steam Dryer Inspections The steam dryer was replaced with a new dryer similar to the steam dryers previously installed at Quad Cities 1 and 2. Inspections were performed on outer hood welds on the removed steam dryer where cracking had been identified and repaired during previous outages. No relevant indications were identified during these inspections. The purpose of the inspections was to evaluate the previous repairs and modifications for applicability to Dresden 2. The Dresden 2 steam dryer has not been replaced and has the same repairs/modifications as the old steam dryer removed from Unit 3.

Shroud Inspections Ultrasonic examinations were performed on the accessible core shroud vertical welds (excluding ring welds). Eleven welds were examined including all six in the beltline region. One relevant indication was identified in weld V27, which is below the beltline region. Over 69% of weld V27 was examined from each side. The indication was 1.8 inches in length (4.8% of weld) and less than 0.2 inches in depth (less than 10% thruwall). The flaw was evaluated in accordance with the guidance provided in BWRVIP-76. The evaluation concluded the V27 weld is acceptable until the next inspection (10 years).