SVPLTR 15-0014, Owner'S Activity Report Submittal Fifth 10-Year Interval 2014 Refueling Outage Activities

Owner'S Activity Report Submittal Fifth 10-Year Interval 2014 Refueling Outage Activities

ML15063A025
Person / Time
Site:	Dresden
Issue date:	02/11/2015
From:	Marik S Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
SVPLTR 15-0014
Download: ML15063A025 (7)

Text

ld = Dresden Nuclear Power Station Exelon Generation o 6500 North Dresden Road IL Morris, 60450 815 942 2920 Telephone www.exeloncorp.com February 11, 2015 SVPLTR #15-0014 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 Fifth 10-Year Interval 2014 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 (D3R23) which began on November 3, 2014, and was completed on November 19, 2014. This is the only refueling outage conducted in the first inspection period of the fifth 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 USNRC Safety Evaluation In Support of Request for Relief Associated With the Fifth 10-Year Inservice Inspection Interval Program dated September 30, 2013. 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.

February 11,2015 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. Bruce Franzen, Regulatory Assurance Manager, at (815) 416-2800.

Respectf ully, Shane Marik 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 D3R23 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 D3R23 (if applicable)

Current Inspection Interval 5 th Inspection Interval (1st, 2 nd, 3 rd, th, other) 4 Current Inspection Period 1 st Inspection Period (15, 2 nd, 3 rd )

Edition and Addenda of Section XI applicable to the Inspection Plans 2007 Edition with 2008 Addenda Date / Revision of Inspection Plans 6/30/14/Revision 1 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: 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 D3R23 conform to the requireýnts of Seleion XI (refueling outage number)

Signed , ISI 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 HSB Global Standards 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 repair/

replacement activities and evaluation described inthis report. Furthermore, neither the Inspector nor his employer shall be liable inany manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection

- J Commissions IL 1546; NB10972 A, N, I (Inspector's Signature) National Board, State, Province, and Endorsements Date o2 / s.

TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Number Item Description Evaluation Description None None None 4 4.

4 +

I 1*

4 +

I 4.

1 +

I *1-1 4.

I 4-4 4-I -I-

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 Repair pinhole leak on Unit 3 CCSW Line 3-1505- Welded cap over thru-wall leak. 5/17/14 RRP 3-13-002 24" per EC 393751.

1 Remove indications on U3 RPV Head Spray Machined out indications, weld build-up flange, 11/15/14 RRP 3-14-038 Bulkhead Flange. machined back to required dimensions.

3 Replace U3 CCSW pipe in Cribhouse. Replaced pipe with cap on it. 11/14/14 RRP 3-14-059 2/3 Remove and repair indications on 3A LPCI Heat Ground out cracks and re-welded. 11/17/14 RRP 3-14-077 Exchanger support M-1200D-1015.

2 Grind on LPCI support M-3403-09 pipe weld to Ground on weld and restored to drawing 11/15/14 RRP 3-14-078 stanchion to address construction issue. Not configuration.

service induced.

2/3 Restore 38 LPCI Heat Exchanger support M- Welded support back to drawing configuration 11/16/14 RRP 3-14-079 1200D-1019 back to original configuration. before grinding.

1 t J I I I

• I 1 1 I

.1 I I 1 9

.1 I' I I I I I I. I I

Dresden Unit 3 Reactor Internals Inspection Report Refueling Outage D3R23 The ASME Section XI inspections credited during D3R23 includes 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 the Boiling Water Reactor Vessel and Internals Project (BWRVIP) examinations in place of the B-N- I and B-N-2 examinations in accordance with Dresden Station Relief Request 15R-07, "Request for Relief for the Use of BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor Vessel Internals and Components Inspection In Accordance with IOCFR50.55a(a)(3)(i) Alternative Provides Acceptable Level of Quality and Safety".

To implement the requirements of the BWRVIP, General Electric - Hitachi (GEH) was contacted to perform the inspection activities.

The following components and assemblies were examined as directed by BWRVIP documents:

0 22 welds and components on jet pump assemblies in accordance with the BWRVIP-41 Rev. 3, "BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines".

• Ten core spray piping welds, three core spray piping brackets and one core spray sparger bracket in accordance with the BWRVIP-18 Revision 1-A, "BWR Core Spray Internals Inspection and Flaw Evaluation Guidelines".

0 Two shroud vertical welds in accordance with BWRVIP-76 Revision 1, "BWR Core Shroud Inspection and Flaw Evaluation Guidelines".

• Attachment welds for two core spray piping brackets and all four steam dryer support lugs in accordance with BWRVIP-48-A, "Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines".

• Inspected previous indication on steam dryer in accordance with BWRVIP- 139-A, "Steam Dryer Inspection and Flaw Evaluation Guidelines".

0 Previous indications in top guide aligner block welds in accordance with BWRVIP-26-A, "BWR Top Guide Inspection and Flaw Evaluation Guidelines".

0 Standby liquid control nozzle to safe end in accordance with BWRVIP-27-A, "BWR Standby Liquid Control System/Core Plate AP Inspection and Flaw Evaluation Guidelines".

In addition to the BWRVIP inspection guidance, the following augmented examinations were also performed in the reactor vessel as part of the D3R23 inspection activities:

• 35 jet pump components not required by BWRVIP-41.

• All eight feedwater sparger end brackets for evidence of wear.

0 Six SRM/IRM dry tubes in accordance with SIL 409 guidance.

0 One steam separator guide rod top cone due to previous indication.

0 Selected cast austenitic stainless steel components in accordance with license renewal commitments.

0 All four core spray lower sectional replacements.

0 Two previous indications on shroud repair hardware.

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