ML071350378
| ML071350378 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/07/2007 |
| From: | Morris J Duke Energy Carolinas, Duke Power Co |
| To: | Document Control Desk, NRC/NRR/ADRO |
| References | |
| Download: ML071350378 (17) | |
Text
P Duke
- OwEnergy, JAMES R. MORRIS Vice President Catawba Nuclear Station 4800 Concord Rd. / CNO1 VP York, SC 29745-9635 803 831 4251 803 831 3221 fax May 7, 2007 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C. 20555
Subject:
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)
Catawba Nuclear Station, Unit 2 Docket Number 50-414 Submittal of Steam Generator Inservice Inspection Documentation for Third Ten-Year Interval
References:
- 1. Letter from D.M. Jamil to NRC, Submittal of Third Ten-Year Interval Inservice Inspection Plan and Inservice Inspection Pressure Test Plan, dated March 6, 2006
- 2. Letter from D.M. Jamil to NRC, Steam Generator Outage Summary Inservice Inspection Report for End of Cycle 14 Refueling Outage, dated July 18, 2006 In the Reference 1 letter, Duke submitted the third ten-year interval inservice inspection plan and inservice inspection pressure test plan for Catawba Unit 2.
As part of this submittal, Duke indicated that Catawba Unit 2 began its third ten-year interval on October 15,
- 2005, which was earlier than its originally planned third ten-year interval start date of August 19, 2006.
This was being done in order to align all of Duke's nuclear units to the same ten-year interval ASME Code Edition/Addenda.
The first refueling outage in the Catawba Unit 2 third ten-year interval was the End of Cycle 14 Refueling Outage.
www. duke-energy. com
I U.S. Nuclear Regulatory Commission Page 2 May 7, 2007 In the Reference 2 letter, Duke submitted the steam generator outage summary inservice inspection report for the End of Cycle 14 Refueling Outage.
The NIS-l form contained in the Reference 2 letter erroneously referred to the third inspection period of the second inspection interval and also to the ASME Code Edition that was in effect for the second inspection interval.
When the Reference 2 letter was submitted, it was not recognized that the third ten-year interval start date for the Catawba Unit 2 inservice inspection plan had been changed.
On October 5, 2006, the Steam Generator Maintenance and Engineering group discovered the change in the third ten-year interval start date for the Catawba Unit 2 inservice inspection plan (the steam generator inservice inspection plan and the inservice inspection plan for the other plant components are separate documents which are developed independently by two different groups).
The discrepancy between the third ten-year interval start dates for the two plans was entered into Catawba's Corrective Action Program as Problem Investigation Process Report C-06-06816.
The purpose of this letter is to submit the following:
- 1.
Third Interval Steam Generator Inservice Inspection Plan for Catawba Unit 2 (Attachment 1)
- 2.
Revised Steam Generator Outage Summary Report title page and NIS-l form for Catawba Unit 2 End of Cycle 14 Refueling Outage (Attachment 2)
(the inspection scope and results were not affected by this revision; only the NIS-1 form has been revised to reflect the updated inspection interval and ASME Code Edition/Addenda)
Duke regrets any confusion that may have been caused as a result of this issue.
There are no regulatory commitments contained in this letter or its attachments.
If you have any questions regarding this information, please call L.J. Rudy at (803) 831-3084.
U.S. Nuclear Regulatory Commission Page 3 May 7, 2007 Very truly yours, JsJia R.
Morris LJR/s Attachments
U.S. Nuclear Regulatory Commission Page 4 May 7, 2007 xc (with attachments):
W.D. Travers, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23T85
- Atlanta, GA 30303 A.T. Sabisch, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station J.F. Stang, Jr., Senior Project Manager (addressee only)
U.S. Nuclear Regulatory Commission Mail Stop 8-H4A Washington, D.C. 20555-0001 Third Interval Steam Generator Inservice Inspection Plan for Catawba Unit 2
THIRD INTERVAL STEAM GENERATOR INSERVICE INSPECTION PLAN CATAWBA NUCLEAR STATION UNIT 2 REVISION 0 Duke V Power.
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC Prepared By:
Reviewed By:
Checked By:
Approved By:
ANII Review:
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-7 Date 4-2&--o-7 Steam Generator Tubing Inservice Inspection Plan Catawba Nuclear Station Unit 2 Revision 0
CATAWBA NUCLEAR STATION GENERAL INFORMATION Location:
4800 Concord Road. York, S. C. 29745 Commercial Service Date:
August 19, 1986 Third Interval Start Date:
October 15, 2005 Third Interval End Date:
August 19, 2016 Owner: Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC 526 South Church St.
Charlotte, N. C. 28201-1006 Steam Generator Tubing Inservice Inspection Plan Catawba Nuclear Station Unit 2 Revision 0
TABLE OF CONTENTS SECTION 1.
2.
3.
4.
5.
TITLE Applicable Codes and Standards for Inservice Inspection System Boundary Subject to Inspection Inspection Methods and Procedures to Be Used for Inservice Inspection Description of Inservice Inspection Plan for Steam Generator Tubing Calibration Standards REVISION 0
0 0
0 0
Steam Generator Tubing Inservice Inspection Plan Catawba Nuclear Station Unit 2 Revision 0
1.0 Applicable Codes and Standards for Inservice Inspection "In accordance with the requirements of paragraph 50.55a(g) of 10CFR Part 50 (effective date October 28, 2002), the inservice inspection of unit 2's steam generators of the Catawba Nuclear Station will be performed in accordance with inspection Program B of the 1998 Edition, thru 2000 Addenda of ASME Section XI hereafter referred to asSection XI. The inservice inspection examinations will be performed in accordance with Inspection Program B of Section XI. All examinations will be performed to the extent practicable within the limitations of design, geometry and materials of construction of the component.
Note: The steam generators are not included in Catawba Nuclear Station's 3rd interval station ISl plan other than by reference in section 1.1. The referenced paragraph states in full:
Steam generator tubing will be inspected as required by ASME Secton XI and the Catawba Technical Specifications for Catawba Nuclear Station. The Steam Generator Maintenance Section/Nuclear Technical Services Division has overall responsibility for this inspection. This work is planned, implemented, documented and reported independently from this document.
As a result, this stand-alone SG ISI plan is being developed for the 3rd Interval which covers 10/15/2005 thru 8/19/2016. This plan was not submitted at the same time as the remaining station components 3 Interval Plan due to an administrative oversight. Catawba unit 2 outage EOC14 is included as the first outage in this plan. Review of the requirements of the 1998 thru 2000 addenda have determined that the inspections completed and reporting of results for steam generator tubing during EOC14 outage to be in compliance.
1.1 Additional Codes and Standards Used Steam generator tubing will be inspected as required by ASME Section XI and the Technical Specifications for Catawba Nuclear Station. The Steam Generator Maintenance and Engineering Group of the Nuclear Technical Services Division has overall responsibility for this inspection.
1.2 Code Case Applicable to ASME Boiler & Pressure Vessel Code Section XI The following code cases will be used for the third interval Inservice Inspection Program at Catawba Unit 2 for the steam generator tubing inspections:
None Steam Generator Tubing Inservice Inspection Plan Revision 0 Catawba Nuclear Station Unit 2 1
1.3 Applicable Duke Power Administrative Procedures The following Duke procedures will be used to control steam generator tubing inservice inspection activities and inservice inspection plans and reports:
PROCEDURE NUMBER NSD-300 NSD-701 NSD-702 NSD-703 NSD-704 NSD-800 SGMP TITLE ASME Section XI Program Records Management Document Management Administrative Instructions for Technical Procedures Technical Procedure Use and Adherence Software and Data Quality Assurance (SDQA) Program Steam Generator Management Program 2.0 System Boundary Subject to Inspection The steam generator tubing is part of the pressure boundary for the class 1 reactor coolant system (NC system).
2.1 Inspection Interval and Inspection Periods Third Inspection Interval Start Date End Date 10/15/2005 10/15/2008 10/15/2012 8/19/2016 1st Period Refueling Outage 1: EOC Refueling Outage 2: EOC 14 15 2nd Period Refueling Outage 3: EOC 16 Refueling Outage 4: EOC 17 Refueling Outage 5: EOC 18 3rd Period Refueling Outage 6: EOC 19 Refueling Outage 7: EOC 20 3.0 Inspection Methods and Procedures to Be Used for Inservice Inspection Inservice inspection of Catawba unit 2 will be performed using procedures which comply with the requirements of the applicable codes referenced in Section 1 of this plan. The volumetric Steam Generator Tubing Inservice Inspection Plan Revision 0 Catawba Nuclear Station Unit 2 2
method of inspection will be used to inspect the steam generator tubing as required. Each inspection will be performed under the QA program of the organization performing the inspection.
Interfacing Vendor Procedures, will be used to perform the steam generator tubing inservice inspection as reviewed and approved by Duke.
3.1 Volumetric Inspection Steam generator tubing will be examined using the eddy current inspection method as required by Section XI and the Catawba Technical Specifications. The Steam Generator Maintenance and Engineering Group (SGME) of the Nuclear Technical Services Division has overall responsibility for implementing and reporting inspections pertaining to steam generator tubing.
4.0 Description of Inservice Inspection Plan for Steam Generator Tubing The inservice inspection of the steam generator tubing shall be performed in accordance with the requirements of Article IWB-2000 of Section Xl. Specific examinations are defined in table IWB 2500-1, examination category B-Q, to be as required by the plant Technical Specifications.
Tube examination extent and frequency will follow CNS Technical Specification 5.5.9.
4.1 Examination Categories and Requirements The examination category for Steam Generators is listed in Table IWB-2500-1 of Section XI.
The specific examination will be identified by an item number similar to those listed in Table IWB-2500-1 of Section XI, plus an additional number to uniquely identify the steam generator being inspected.
Category B-Q IWB-2500-1 Item Steam Generator Tubing Component To Be Examined Comments B16.10 B16.20 Steam Generator Tubing in Straight Design Steam Generator Tubing in U-Tube Design N/A for Catawba unit 2 S/G Tubing is examined and documented by the SGME Group of the Nuclear Technical Services Division as required by CNS Technical Specifications Sect. 5.5.9.
Steam Generator Tubing Inservice Inspection Plan Catawba Nuclear Station Unit 2 Revision 0 3
4.2 Specific Steam Generator Item Number with Corresponding General Arrangement and As-Built Drawings ID Number, Steam Generator A
B C
D Item Number B16.020.001 B16.020.002 B1 6.020.003 B136.020.004 ID Number 2SGA - Tubes 2SGB - Tubes 2SGC - Tubes 2SGD - Tubes Drawing Number CNM 2201.01-0113 CNM 2201.01-0106 CNM 2201.01-0105 CNM 2201.01-0114 Vessel General Arrangement - CNM 2201.01-0102 4.3 Steam Generator Tubing Material and Dimensions Tubing Drawing Numbers CNM 2201.01-0939 CNM-2201.01-0635 thru CNM 2201.01-0642 Material SB-163 Alloy 600 0.750" Outside Diameter 0.043" Wall Thickness 5.0 Calibration Standards 5.1 Eddy Current Calibration Standards Calibration standards are vendor supplied. Calibration standards that will be used include bobbin, MRPC, array and plug type standards. Eddy current examinations are scheduled and performed per Catawba Technical Specification 5.5.9.
5.2 Calibration Standard Description Calibration standards are vendor supplied.
Steam Generator Tubing Inservice Inspection Plan Catawba Nuclear Station Unit 2 Revision 0 4
Revised Steam Generator Outage Summary Report Title Page and NIS-1 Form for Catawba Unit 2 End of Cycle 14 Refueling Outage
Steam Generator Outage Summary Report Catawba Unit 2 2006 Outage EOC 14 Location: 4800 Concord Road, York South Carolina 29745 NRC Docket No. 50-414 National Board No. 173 Commercial Service Date: August 19, 1986 Owner: Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC 526 South Church St.
Charlotte, N.C. 28201-1006 Revision 1 Prepared By:
Reviewed By:
Checked By:
Approved By:
Copy No.
Controlled:
Or~ryv\\~~
i~hi Date: 4 4-J_7 Date:_
Date: 2*9 r) -77 Date:
07__
Assigned To:
Uncontrolled:
Controlled Distribution Copy No.
Original Assigned To Catawba Nuclear Station Document Control Master File CN-208.21 NRC Document Control I
Uncontrolled Distribution Hartford Steam Boiler Inspection and Insurance Co. (AIA) 2 Electronic Steam Generator Desktop
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules
- 1. Owner: Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC 526 S. Church St.. Charlotte, NC 28201-1006 (Name and Address of Owner)
- 2.
Plant: Catawba Nuclear Station, 4800 Concord Road, York, S. C. 29745 (Name and Address of Plant) 3.
4.
5.
6.
7.
Plant Unit: 2 Owner Certificate of Authorization (if required)
Commercial Service Date: August 19, 1986 National Board Number for Unit 173 Components Inspected:
N/A Component Steam Generator 2A Steam Generator 2B Steam Generator 2C Steam Generator 2D Manufacturer Westinghouse Westinghouse Westinghouse Westinghouse Manufacturer State or National Serial No.
Province No.
Board No.
1923 N/A 4
1922 N/A 3
1921 N/A 2
1924 N/A 5
Revision 1:
Report is amended to reflect the 1998 edition of Section XI with 2000 addenda and reflect that EOC14 was first inspection for the 1st period of the 3rd interval.
Note:
Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 81/2 in. x 11 in., (2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
FORM NIS-1 (Back)
- 8.
Examination Dates 10/15/2005 to 04/24/2006
- 9.
Inspection Period Identification:
- 10.
Inspection Interval Identification:
- 11.
Applicable Edition of Section XI
- 12.
Date/Revision of Inspection Plan:
- 1
- 3 1998 Addenda 2000 Per Technical Specification (5.5.9)
- 13. Abstract of Examinations and Test. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan.
- 14. Abstract of Results of Examination and Tests.
- 15. Abstract of Corrective Measures.
We 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) corrective measures taken conform to the rules of the ASME Code,Section XI.
Certificate of Authorization No. (if applicable)
NA Duke Power Co. LLC Date V.
20 C7 Signed d/b/a Duke Energy Carolinas, LLC Owner Expiration Date NA By
_/e2 4-/,~L1.
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 of Province of NC employed by *The Hartford Steam Boiler Inspection and Insurance Company of Connecticut have inspected the components described in this Owners' Report during the period 03/27/2006 to 07/13/2006
, and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in the Ownersi Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.
By signing this certificate neither the Inspector nor his employer makes anywarranty, expressed or implied, concerning the examinations, test, and corrective measures described in this Ownersi Report.
F rthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or perty damage oIa less of any kind arising from or connected with this inspection Ci Commissions NC 978 Inspector's Sigdature National Board, State, Province, and Endorsements Date 4"- 2-__
20 0_L
- The Hartford Steam Boiler Inspection & Insurance Company of Connecticut (HSB CT) 2UU AsnTora Center Norm Suite 205 Atlanta, GA. 30338