View source for SVPLTR 08-0007, Owner'S Activity Report Submittal - Fourth 10-Year Interval 2007 Refueling Outage Activities

{{Adams
| number = ML080510695
| issue date = 02/12/2008
| title = Owner'S Activity Report Submittal - Fourth 10-Year Interval 2007 Refueling Outage Activities
| author name = Wozniak D
| author affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000237
| license number = DPR-019
| contact person = 
| case reference number = SVPLTR #08-0007
| document type = Inservice/Preservice Inspection and Test Report, Letter type:SVPLTR
| page count = 7
}}

=Text=
{{#Wiki_filter:ExeImn.Exelon Generation Company, LLC www.exeloncorp.com Dresden Nuclear Power Station NU]ea 65oo North Dresden Road Morris, I L 60450-9765 February 12, 2008 SVPLTR #08-0007 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:==
Owner's Activity Report Submittal Fourth 10-Year Interval 2007 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 2 refueling outage (D2R20) which began on October 29, 2007, and was completed on November 19, 2007. This is the first refueling outage conducted in the second inspection period of the fourth 10-year inservice inspection interval for DNPS Unit 2. A copy of the Owner's Activity Report and IVVI Report are provided as attachments to this letter.This Owner's Activi ty 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 XI, 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 12, 2008 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, David B. Wozniak 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 D2R20 OAR-i Owner Exelon Generation Companv (EGG, 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)Date 06/09/1970 Unit No. 2 Commercial Service I (if applicable)
Current inspection interval 4th Inspection Interval Refueling OutageNo.
D2R20 (1st, 2nd, 3rd, 4th, other)Current inspection period 2nd Inspection Period (1st, 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 Xl 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 Authorizati NO. None ExpiNo.(if applicable)
Signed II-- ./" , SI Coordinator Owner or Owner's Designee, Title ration Date Not Applicable Date t /Q(, /O I 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 02/16/2007 to 02/08/2008, 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 Sianature National Board. State. Province.
and Endorsements Date A A/0 K-D2R20 OAR-1 Page 1 of 5 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.25 0 0 0 Deferral Permissible B-D 62 14 23 48 Components scheduled in accordance with Program B.B-G-1 8 4 50 75 Deferral Permissible B-G-2 34 4 12 35 Components scheduled in accordance with Program B.1 0 0 100 Examinations limited to components disassembled selected under Examination Category B-L-2 and B-M-2.B-K 13 5 38 69 Components scheduled in accordance with Program B.B-L-2 1 1 100 100 Examinations limited to disassembled components.
B-M-1 1 0 0 0 Deferral Permissible B-M-2 6 1 17 100 Examinations limited to disassembled components.
B-N-1 1 0 0 100 One component examined each inspection period.B-N-2 60 0 0 25 Deferral Permissible B-O 8 0 0 0 Deferral Permissible B-P 2 2 100 300 Two pressure tests performed each refuel outage.C-A 2 1 50 50 Components scheduled in accordance with Program B.One during the second and one during the third period.C-B 12 4 33 50 Components scheduled in accordance with Program B.6 0 0 100 Six components examined each inspection period.C-C 10 4 40 60 Components scheduled in accordance with Program B.C-H 18 5 28 128 Eighteen pressure tests performed each inspection period.F-A 147 40 27 58 Components scheduled in accordance with Program B.R-A 76 24 32 58 Components scheduled in accordance with Program B.22 22 100 300 Twenty-one components VT-2 examined each refuel outage.D2R20 OAR-1 Page 2 of 5 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw Examination Characterization Flaw or Relevant Condition Found During Scheduled Section XI Category Item Number Item Description (IWA-3300)
Examination or Test (Yes or No)B-G-1 B6.50 Washers/Bushings-N/A Yes Bushing 81 appears to have disengaged (turned) during vessel head detensioning.
N/A N/A Isolation Indications No Condenser West Found Outside of End Channel NDE Exam Barrel to Inside Boundary of Cladding Interface Diaphragm Seal Weld After Maintenance D2R20 OAR-1 Page 3 of 5 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 XI Examination or Replacement Class Measure Item Description Description of Work Test (Yes/No) Date Completed Number Unit 2 Vessel Head To Removed Indications 1 Repair Flange Weld Indications Via Grinding Yes 11/17/07 2-07-070 Unit 2 Core Spray Line Tightened Bolt On 2 Repair Support Support Base Plate Yes 11/17/07 N/A Unit 3 HPCI Drain Line Replaced Leaking Item 2 Replacement Leak Per WO 992051 No 01/13/07 N/A Unit 2 Thru Wall Crack On SBLC Tank Temp 2 Repair Thermowell Encapsulated Leak No 01/19/07 2-07-001 2-1501-33B Valve Corrective Missing Bonnet To Installed Missing Bolt 2 Measure Body Flange Bolt and Nut No 02/21/07 2-07-003 Line 2-1510-16"-D Corrective Developed Thru Wall 3 Measure Leak Encapsulated Leak No 05/07/07 2-07-030 Unit 2 HPCI Inlet Drain Replaced Leaking Item 2 Replacement Pot Outlet Line Leak Per WO 1049528 No 07/27/07 N/A U3 HPCI Drain Line Replaced Leaking Item 2 Replacement Leak Per WO 1006173 No 03/03/07 N/A D2R20 OAR-1 Page 4 of 5 Dresden Unit 2 In-Vessel Visual Inspection Report Refueling Outage D2R20 Steam Dryer Replaced The steam dryer was replaced with a new dryer of the same design as the steam dryer installed in Dresden 3 during D3R19 (November 2006). Since this was the last of the four steam dryers to be replaced for Dresden and Quad Cities, no BWRVIP inspections were performed on the removed steam dryer. Future inspection of the new steam dryer will be performed in accordance with the guidance in BWRVIP-139.
Shroud Inspections Ultrasonic examinations were performed on five of the core shroud vertical welds (excluding ring welds). One relevant indication was identified in weld V18, which is in the beltline region. The flaw was evaluated in accordance with the guidance provided in BWRVIP-76.
The evaluation concluded the V1 8 weld is acceptable until the next scheduled inspection.
Attachment Weld Inspections Visual inspections were performed on two of the reactor vessel attachment welds as part of the Reactor Internals Program as well as the ASME Code requirements.
Each of these attachments consisted of Core Spray brackets.
No relevant indications were identified on these welds.D2R20 OAR-1 Page 5 of 5}}