ML13085A025

Catawba Nuclear Station, Unit 1 - Inservice Inspection Report for End of Cycle 20 Refueling Outage

ML13085A025
Person / Time
Site:	Catawba
Issue date:	03/21/2013
From:	Henderson K Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13085A025 (7)

Text

/PDuke EEnergyCarolinas KELVIN HENDERSON Catawba Nuclear Station Site Vice President Duke Energy Carolinas, LLC 4800 Concord Rd.York, SC 29745 803- 701-4251 March 21, 2013 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Carolinas, LLC Catawba Nuclear Station, Unit 1 Docket Number 50-413 Inservice Inspection Report for End of Cycle 20 Refueling Outage In accordance with Section XI of the ASME Code, please find attached the subject 90-day report which provides the results of the inservice inspection associated with the subject outage.There are no regulatory commitments contained in this letter or its attachment.

If you have any questions concerning this material, please call L.J. Rudy at (803) 701-3084.Very truly yours, Kelvin Henderson LJR/s Attachment Oq -7 JUPP N-r-1 www. duke-energy.

com Document Control Desk Page 2 March 21, 2013 xc (with attachment):

V.M. McCree Regional Administrator U.S. Nuclear Regulatory Commission

-Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 G.A. Hutto, Ill, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station J.H. Thompson (addressee only)NRC Project Manager (Catawba)U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 8-G9A 11555 Rockville Pike Rockville, MD 20852-2738 Attachment Catawba Unit 1 End of Cycle 20 Inservice Inspection Report CASE N-532-4 FORM OAR-I OWN ER'S ACTIVITY REPORT Report Number Owner's Activity Report for Refueling Outage 1 EOC20 Plant Catawba Nuclear Station, 4800 Concord Road, York, SC 29745 Unit No.1 (if applicable)

Commercial service date 6/29/1985 Refueling outage no. 1 EOC20 Current inspection interval 3rd for Class 1, 2, & 3 Components

& Supports and 2 0d for Class MC Containment (1st, 2nd, 3rd, 4th, other)Current inspection period 3rd for Class 1, 2, & 3 Components

& Supports and Class MC Containment (1st, 2nd, 3rd)Edition and Addenda of Section Xl applicable to the inspection plans 1998 Edition through the 2000 Addenda Date and revision of inspection plans See Attachment Edition and Addenda of Section Xl applicable to repair/replacement activities, if different than the inspection plans Same Code Cases used: The following Code Cases are permitted by the ISI Plans: N-460, N-504-3, N-513-2, N-532-4, N-533-1, N-566-2, N-586-1, N-613-1, N-616, N-624, N-639, N-643-2, N-647, N-663, N-665, N-683, N-685, N-686, N-686-1, N-694-1, N-695, N-696, N-697, N-700, N-706, N-722, N-729-1, N-731, N-770-1 (if applicable)

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 Xl; and (c) the repair/replacement activities and evaluations supporting the completion of 1EOC20 conform to the requirements of Section XI.(refueling outage number)Signed MA-CZ-A '-p." ,<ur. 6x' -_ -Date 3 /3~~3 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 South Carolina and employed by HSB Global Standards of CT have inspected the items described in this Owners 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 Xl.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.

62'ez Commissions A/IS / Z 9/,d, S'r 2 3 3'A/,q Inspectors Signature National Board, State, Province, and Endorsements Date -/4j-)

Attachment Catawba Unit I End of Cycle 20 Inservice Inspection Report Date and Revision of Inspection Plans: 1. The following documents comprise the Catawba Nuclear Station 3 rd Interval Inservice Inspection Plan for Unit 1 (Class 1, 2, and 3 Components):

a. Third Interval Inservice Inspection Plan Catawba Nuclear Station Units 1 and 2 General Requirements, Document #CISI-1462.10-0030-GEN REQ, Rev 1, dated 06/26/2008, including the following addenda: i. CISI-1462.10-0030-3CNS-021 through CISI-1462.10-0030-3CNS-033

b. Catawba Nuclear Station Unit 1-Third Inspection Interval Inservice Inspection NDE Plan, Document #CISI-1462.10-0030-UNIT 1, Rev 1, dated 06/26/2008, including the following addenda: i. CISI-1462.10-0030-3CNS1-028 through CISI-1462.10-0030-3CNS1-071

2. The following documents comprise the Catawba Nuclear Station 3 rd Interval Inservice Inspection Pressure Test Plan for Unit 1: a. Third Inspection Interval Inservice Inspection Pressure Test Plan for Catawba Unit 1, Document #CISI-1462.20-0020-U1PTPLAN, Rev 1, dated 07/23/2008, including the following addenda: i. CISI-1462.20-0020-Cl-PT-031 through CISI-1462.20-0020-C1-PT-048

3. The following documents comprise the Catawba Nuclear Station 2 nd Interval Containment Inservice Inspection Plan for Unit I (Class MC): a. Catawba Nuclear Station Units 1 and 2 -Second Interval Containment Inservice Inspection Plan, Document #CN-ISIC2-1042-0001, Rev 2, dated 10/02/2008 CASE N-532-4 Catawba Nuclear Unit 1 Form OAR-1 Owner's Activity Report Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and Item Number Item Description Evaluation Description Boric acid residue found on RCP-1C and RCP-1D seal Areas identified in PIPs C-12-11344 and C-12-B-P / B15.60 housing areas and associated bolting (Zone Number 11341 were evaluated by Engineering using Code 1 NC-001 L-A) Case N-566-2 and found to be acceptable.

VT-3 examination revealed skewed sway strut.F-Al F1.10 C1.F1.10.0004/

1-R-NC-1539 Evaluation concluded the support was within tolerance and acceptable as is.VT-3 examination revealed that pipe is not bearing on support. Evaluation concluded that F-A/ F1.21 Cl .F1.21.0005/, 1-R-CA-1 549 pipe will rest on support once the pipe is filled and returned to service. The component is acceptable as is.VT-3 examination revealed a bolt and nut assembly was loose on pipe clamp. Evaluation F-A /F1.22 C1.F1.22.0004

/ 1 -R-CA-1 509 concluded the support was still able to perform its designed function.

Corrective measures were used to tighten the bolt and nut assembly as allowed by IWF-3112.3(b).

VT-3 examination revealed that support is not carrying the load. Evaluation concluded that F-A/ F1.30 C1.F1.30.0010/

1-R-CA-0033 gravity loading on the system will be resumed when the system is returned to service. The component is acceptable as is.VT-3 examination revealed that riser clamp was not in contact with bottom half of pipe. Evaluation F-A / F1.30 Cl F1.30.0041

/ 1-R-KC-0631 concluded the support was still able to perform its designed function.

Work request generated to adjust clamp assembly as allowed by IWF-3112.3(b).

VT-3 examination revealed degraded coatings and light surface rust. Evaluation concluded the F-A/ F1.30 C1 .Fl.30.0080/

1-R-RN-0293 support was still able to perform its designed function.

Work Request generated to have area cleaned and coatings re-applied to saddle area.VT-3 examination revealed gap behind base plate. Re-inspection revealed stamped markings F-A I F1.30 C1 1F1.30.0239/

1-R-VN-0067 used during construction to identify washers used to shim behind the base plate. Re-examination found component to be acceptable.

VT-3 examination revealed gap behind base plate. Re-inspection revealed stamped markings F-A/ F1.30 C1.F1.30.0302

/ 1-R-VN-0065 used during construction to identify washers used to shim behind the base plate. Re-examination found component to be acceptable.

CASE N-532-4 Catawba Nuclear Unit 1 Form OAR-1 Owner's Activity Report Table 1 (continued)

Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service Examination Category and Item Description Evaluation Description Item Number VT-3 examination revealed missing locknut on pipe clamp. Evaluation concluded the support F-A / F1.32 C1 F1l.32.0024

/ i-R-RN-0304 was still able to perform its designed function.Corrective measures were performed to add a locknut as allowed by IWF-3112.3(b).

Drawing does not show additional pipe attached at base of support. PIP C-1 2-10674 issued F-A / F1.32 C1 F 1.32.0028

/ 1 -R-VN-0052 Corrective Action to add a note to the drawing stating "Non-QA support for 1-1/2" pipe may be attached.

Change is editorial only.Table 2 Abstract of Repair/Replacement Activities Required For Continued Service Code Class Item Description Description of Work Date Completed Repair / Replacement Plan Number Cl.C3.10.0002

-Removed rejectable 2 Containment Spray indications, performed 2000695-07 Heat Exchanger 1 A weld repair. Reference 12/13/2012 Support Base Plate PIP C-12-10718