SVPLTR 13-0008, Owner'S Activity Report Submittal, Fourth 10-Year Interval 2012 Refueling Outage Activities

Owner'S Activity Report Submittal, Fourth 10-Year Interval 2012 Refueling Outage Activities

ML13073A120
Person / Time
Site:	Dresden
Issue date:	03/04/2013
From:	Czufin D Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR #13-0008
Download: ML13073A120 (7)

Text

Ad m Dresden Nuclear Power Station A Exev on Generation, 6500 North Dresden Road Morris, IL 60450 815 942 2920 Telephone www.exeloncorp.com March 4, 2013 SVPLTR #13-0008 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:

Owner's Activity Report Submittal Fourth 10-Year Interval 2012 Refueling Outage Activities This letter submits the Owner's Activity Report (i.e., Form OAR-i) and Invessel Visual Inspection (IWI) Report for the Dresden Nuclear Power Station (DNPS) Unit 3 refueling outage (D3R22) which began on November 12, 2012, and was completed on December 5, 2012. This is the second 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 Owners 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, aInservice Inspection Code Case Acceptability, ASME Section XI, Division I ," 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.

March 4, 2013 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. Hal Dodd, Regulatory Assurance Manager, at (815) 416-2800.

Respectfully, David M. Czufin Site Vice Presiden 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-1 OWNER'S ACTIVITY REPORT Report Number Refueling Outage D31122 OAR-i Plant Dresden Nuclear Power Station, 6500 N. Dresden Road, Morris, IL 60450 Unit No. 3 Commercial Service Date 11/16/1971 Refueling Outage Number D3R22 (ifapplicable)

Current Inspection Interval 4th InseP ro* n Interval J11, 2-,3-,4, other)

Current Inspection Period 3"' Inspection Period (1-, 2% 3-)

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, Ifdifferent 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 D3R22 conform to the requirelf ts of Section )a .r ou nuero)

Signed -, , ,SI Coordinator Date __/_-_/___

(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 In this 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 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 repalr/

replacement activities and evaluation described in this report. Furthermore, neither the inspector nor his employer shaii be ilable 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 Endorserneas Date Ž*/- Q//

D3R22 OAR-1 Page I of 5

TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE

m. naEtio cameomyoad Numb*e

,m Item Description Evaluation Description

• one None None i i.

4 I l n 4.IIJ i i n i i Ii i i iH iJ I I i n I I -I.

4 4.

I t 1 . . . .. . . . . . . 4.

4

• 1~ Y

1. 4.

4. 4.

1* Y

4. 4.

4. 4 4.

4. 4 Dt3R22 OAR-1 Page 2 of 5

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

Class Description Of Work Completed Replacement Plan Number 1 Leak At Safety Relief Valve 3-203-4C Inlet Flange Re-Installed Valve and Replaced Gasket 12/2/12 RRP 3-12-73 4 4 4 4 4

• 4 4 4 4 1 4 t 4 4 4

• 4 .4.

4 4 F

• 4 4 F 4 4 4 F

• D3R22 OAR-1 Page 3 of 5

Dresden Unit 3 Reactor Internals Inspection Report Refueling Outage D3R22 The ASME Section XI inspections credited during D3R22 IVVI activities include the once-per-period B-N- I 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- I 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) and ASME Section XI, the In-Vessel Visual Inspections (IVVI) and reactor vessel welds ultrasonic tests were contracted out to General Electric Hitachi. The following components and assemblies were examined:

• 48 welds and components on jet pump assemblies in accordance with the BWRVIP-41 Rev. 3, "BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines".

" All 20 jet pump secondary riser brace to reactor vessel attachment welds in accordance with ASME Section XI requirements.

" Ten core spray piping welds and two core spray piping brackets in accordance with the BWRVIP-18-A, "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines".

" Core spray sparger exams were performed on 50% of the core spray nozzle assembly welds, all of the sparger pipe end cap welds and all of the sparger brackets in accordance with the BWRVIP-18-A, "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines".

• Nine shroud vertical welds in accordance with BWRVIP-76 Rev. 1, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines".

" Shroud support welds H8 and H9 in accordance with BWRVIP-38, "BWR Shroud Support Inspection and Flaw Evaluation Guidelines".

" All eight feedwater sparger bracket attachment welds in accordance with BWRVIP-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines".

DMR22 OAR-1 Page 4 of 5

" Dryer examinations were performed after three cycles of operation (new dryer installed in D3R20). Dryer inspections were performed in accordance with BWRVIP- 139-A, "Steam Dryer Inspection and Flaw Evaluation Guidelines".

" Top guide grid beams from 18 cells, all four aligner pin assemblies and accessible areas of the rim weld in accordance with BWRVIP-26-A, "BWR Top Guide Inspection and Flaw Evaluation Guidelines" and BWRVIP-183, "Top Guide Grid Beam Inspection and Flaw Evaluation Guidelines".

In addition to the BWRVIP inspection guidance, the following augmented examinations were also performed as part of the D3R22 IVVI activities:

" Inspected bolting on five jet pump swing gates and auxiliary wedges on two jet pumps.

" Inspected the four shroud repair tie rod assemblies in accordance with manufacturer's recommendations.

" Inspected feedwater spargers in accordance with NUREG 0619 guidance and the feedwater spargers end bracket surfaces for evidence of wear.

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

" Inspected a steam separator guide rod top cone due to previous contact with the steam dryer.

" All four steam dryer wall support lugs in accordance with steam dryer manufacturer recommendations.

" Selected Cast Austenitic Stainless Steel components were inspected in accordance with license renewal commitments.

" Inspected reactor vessel internal surfaces around instrument nozzles NI3A, NI3B, NI6A and NI6B.

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

The D3R22 ASME Section XI inspections inside the reactor vessel also included Category B-A volumetric examinations of the reactor vessel shell longitudinal welds, two repair areas and the shell to flange weld. All identified indications met the criteria for IWB-3510 acceptance.

D3R22 OAR-1 Page 6 of 5