SVPLTR 11-0010, Owner'S Activity Report Submittal Fourth 10-Year Interval 2010 Refueling Outage Activities

Owner'S Activity Report Submittal Fourth 10-Year Interval 2010 Refueling Outage Activities

ML110601308
Person / Time
Site:	Dresden
Issue date:	02/18/2011
From:	Hanley T Exelon Nuclear, Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR #11-0010
Download: ML110601308 (6)

Text

Exelon Generation Company, LLC www.exeloncorp.com Exelkn Dresden Nuclear Power Station Nuclear 65o0 North Dresden Road Morris, IL 60450-9765 February 18, 2011 SVPLTR #11-0010 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 2010 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 (D3R21) which began on November 1, 2010, and was completed on November 26, 2010. This is the first refueling outage conducted in the third 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-532-4, "Repair/Replacement Activity 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 15. Code Case N-532-4 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 Code Case N-532-4, this OAR-1 form is being submitted within ninety days of the completion of the refueling outage.

The IVVI results are provided to report vessel internal inspections and to support B-N-1 and B-N-2 relief request exam completion.

AL0L4

February 18, 2011 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. Dennis Leggett, Regulatory Assurance Manager, at (815) 416-2800.

Respectfully, 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 D3R21 OAR-1 Plant Dresden Nuclear Power Station, 6500 N. Dresden Road, Morris, IL 60450 Unit No. 3 Commercial Service Date 11/16/1971 Refueling Outage Number D3R21 (if applicable)

Current Inspection Interval 4 th Inspection Interval (1st, 2', 3', 4', other)

Current Inspection Period 3 rd Inspection Period

( 1 st, 2 nd, 3 d )

Edition and Addenda of Section XI applicable to the Inspection Plans 1995 Edition with 1996 Addenda Date / Revision of Inspection Plans 1/20/2010/Revision 7 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-416-3, N-649 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests, meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of D3R21 conform to the requirements of Section XI (refueling outage number)

Signed Lk . I, ,ISI Coordinator Date I (Owner or Owner's designee. Title)

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 inthis Owner's Activity Report, and state that to the best of my knowledge and belief, the Owner has performed all activities represented by this report inaccordance with the requirements of Section XI By signing this certificate neither the Inspector nor his employer makes any warranty expressed or implied concerning the repair/

replacement activities and evaluation 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 (Inspector's Signature) National Board, State, Province, and Endorsements Date -- ___ J111 D3R21 OAR-1 Page 1 of 4

TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION1 FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description N/A N/A N/A 4 4 4 4 4 4 4 4 4 i 4 4 4

I 4 4 4 4 4 4 4 4 4 4 A 4 4 4 4 1 A 4 D3R21 OAR-1 Page 2 of 4

TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Date Repair/

Class Description Of Work Completed Replacement Plan Number 3 Pitting Found on Unit 3 DGCW Flanges Repaired Flanges Thru Weld Build Up and 1/27/10 RRP 3-10-001 Machining

.3 Pitting Found on Unit 2/3 DGCW Flanges Repaired Flanges Thru Weld Build Up, Machining 4/01/10 RRP 3-10-019 and Replacement 2 Indication on Torus/ECCS Ring Header Saddle Removed Indication Thru Surface Conditioning 11/11/10 RRP 3-10-083 Support __

2 Loose Nuts on Iso Condenser Support Tightened Nuts 11/18/10 RRP 3-10-090 1 Indication On RPV Head Nut 37 Replaced Nut 37 11/23/10 RRP 3-10-091 1 Snubber 3-203-34 Failed Functional Test Replaced snubber 11/14/10 RRP 3-10-087 1 Snubber 3-3204E-38 Failed Functional Test Replaced snubber 11/14/10 RRP 3-10-088 1 Snubber 3-3001A-46 Failed Functional Test Replaced snubber 11/13/10 RRP 3-10-015 1 Snubber 3-3001D-48 Failed Functional Test Replaced snubber 11/4/10 RRP 3-10-016 1 Snubber 3-3019D-55 Failed Functional Test Replaced snubber 11/9/10 RRP 3-10-028 1 Snubber 3-3001A-42 Failed Functional Test Replaced snubber 11/09/10 RRP 3-10-031 1 Snubber 3-3001A-47 Failed Functional Test Replaced snubber 11/6/10 RRP 3-10-032 1 Snubber 3-3001C-50 Failed Functional Test Replaced snubber 11/3/10 RRP 3-10-033 1 Snubber 3-3001B-41 Failed Functional Test Replaced snubber 11/9/10 RRP 3-10-034

__________ A_______________________________________________ a D3R21 OAR-1 Page 3 of 4

Dresden Unit 3 In-Vessel Visual Inspection Report Refueling Outage D3R21 The ASME Section Xl inspections credited during D3R21 IVVI activities include the once-per-period B-N-1 inspection of the reactor vessel interior and B-N-2 inspections of reactor vessel interior attachments. Credit is being taken for these examinations in accordance with Relief Request, "Alternative Requirements to ASME Section XI, B-N-1 and B-N-2 using BWRVIP Guidelines, Fleet Relief," submitted April 19, 2007, as approved in the Safety Evaluation dated April 30, 2008.

To implement the requirements of the Boiling Water Reactor Vessel Internals Program (BWRVIP), GE was contacted to perform the In-Vessel Visual Inspections (IVVI). The following components and assemblies were examined:

• 153 welds and components on jet pump assemblies in accordance with the BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines (BWRVIP-41).

• Ten core spray piping welds and one core spray sparger bracket to shroud attachment weld in accordance with the BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines (BWRVIP-18-A). Inspected the Core Spray lower sectional piping and hardware that was installed in D3R18.

• 14 shroud vertical welds in accordance with the BWR Core Shroud Inspection and Flaw Evaluation Guidelines (BWRVIP-76).

• Attachment welds for two core spray piping brackets and two dryer wall support lugs in accordance with BWR Vessel and Internals Project Lower Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines (BWRVIP-48-A).

• Performed inspections of accessible stub tube and housing welds from two cells that were disassembled to install a plug in the bottom head drain in support of drain line valve maintenance (BWRVIP-48-A and B-N-2).

• Dryer examinations were performed for the second consecutive outage (new dryer installed in D3R19). All critical inspections were completed with no new indications. There was no evident change to the only indication previously identified in D3R20. This indication did not affect the structural integrity of the dryer or ability to remove moisture. Dryer inspections were performed in accordance with BWR Vessel and Internals Project Steam Dryer Inspection and Flaw Evaluation Guidelines (BWRVIP-139-A).

The following augmented examinations were also performed as part of the D3R21 IVVI activities:

• Five jet pump swing gate bolting tack welds were inspected for evidence of weld failure. These inspections were performed in response to previous tack weld failures.

• Inspected the eight feedwater sparger end bracket surfaces for evidence of wear. These inspections were a follow-up to evidence of wear from the pins observed during D3R20. Five of the eight brackets showed evidence of wear similar to that observed during D3R20. Dresden will continue to monitor this condition while long-term repair options are being evaluated.

• Six SRM/IRM dry tubes were inspected in accordance with SIL 409 guidance.

• One JP 11 auxiliary wedge was replaced due to previously identified wear.

• Inspected a steam separator guide rod top cone. The dryer had previously contacted the guide rod.

• Ultrasonic examinations were performed on the access hole cover welds in accordance with BWR Vessel and Internals Project Access Hole Cover Inspection and Flaw Evaluation Guidelines (BWRVIP-180).

The above BWRVIP and augmented examinations resulted in no indications identified in the reactor interior surface as defined in B-N-1 or the reactor interior attachments as defined by B-N-2.

D3R21 OAR-1 Page 4 of 4