ML12321A050

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Steam Generator Inservice Inspection Report
ML12321A050
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 11/01/2012
From: Capps S
Duke Energy Carolinas
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12321A050 (9)


Text

Duke EEnergy STEVEN D. CAPPS Vice President McGuire Nuclear Station Duke Energy MGO1VP / 12700 Hagers Ferry Rd.

Huntersville, NC 28078 980-875-4805 980-875-4809 fax Steven. Capps@duke-energy. corn November 1, 2012 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001

SUBJECT:

Duke Energy Carolinas, LLC McGuire Nuclear Station Docket No. 50-369 Steam Generator Inservice Inspection Report Pursuant to ASME Section Xl, please find attached the McGuire Unit 1, Fourth Interval Steam Generator Inservice Inspection Plan, Revision 0.

Questions regarding the attached report should be directed to Kay Crane, McGuire Regulatory Affairs at (980) 875-4306.

Steven Capps Attachment 4Tc~r 4~crr www. duke-energy. com

U. S. Nuclear Regulatory Commission November 1, 2012 Page 2 xc:

Mr. 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 Mr. Jon H. Thompson NRC Project Manager U. S. Nuclear Regulatory Commission Mail Stop 8G9A 11555 Rockville Pike Rockville, MD 20852-27238 Mr. John Zeiler NRC Senior Resident Inspector McGuire Nuclear Station

FOURTH INTERVAL STEAM GENERATOR INSERVICE INSPECTION PLAN MCGUIRE NUCLEAR STATION UNIT 1 REVISION 0 Duke

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MCGUIRE NUCLEAR STATION GENERAL INFORMATION Location:

12700 Hagers Ferry Road, Huntersville, North Carolina 28078-9340 Commercial Service Date:

Fourth Interval Start Date:

Owner:

December 1, 1981 December 1,2011 Duke Energy Company 526 South Church St.

Mail Code EC07J Charlotte, N. C. 28201-1006 Steam Generator Tubing Inservice Inspection Plan McGuire Nuclear Station Revision 0 2

REVISION

SUMMARY

TABLE OF CONTENTS Section Title

1.

Applicable Codes and Standards for Inservice Inspection

2.

System Boundaries Subject to Inspection

3.

Inspection Methods and Procedures to Be Used for Inservice Inspection

4.

Description of Inservice Inspection Plan for Steam Generator Tubing

5.

Examination Information

6.

Calibration Standards Steam Generator Tubing Inservice Inspection Plan McGuire Nuclear Station Revision 0

0 0

0 0

0 Revision 0 3

1.0Applicable Codes and Standards for Inservice Inspection "In accordance with the requirements of Paragraph 50.55a(g) of 10CFR Part 50, the inservice inspection of Unit l's Steam Generators of the McGuire Nuclear Station will be performed in accordance with the ASME Section XI 1998 Edition and the 2000 Addenda, hereafter referred to asSection XI. The inservice inspection examinations will be performed in accordance with Inspection Program B of Section Xl. All examinations will be performed to the extent practicable within the limitations of design, geometry and materials of construction of the component."

Note: Per Relief Request 10-MN-01, the NRC granted McGuire approval of a proposed alternative to the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (the Code) requirements for ISI. The alternative delays the required update of the McGuire 1 Code of Record for the fourth ISI interval until July 15, 2014. Therefore ASME Section XI 1998 Edition and the 2000 Addenda will be the McGuire 1 Code of Record until Julyl4th, 2014.

Note: The steam generators are not included in the McGuire Nuclear Station's 4th interval Inservice Inspection (ISI) plan. As a result, this stand-alone SG ISI plan has been developed for the Fourth Interval which covers 12/1/2011 thru 11/30/2021.

1.1 Additional Codes and Standards Used Steam Generator tubing will be inspected as required by ASME Section XI and the Technical Specifications for McGuire Nuclear Station. The Steam Generator Maintenance and Engineering (SGME) group of the Corporate Programs and Components Engineering 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 Fourth Interval Inservice Inspection Program at McGuire Unit 1 for the Steam Generator Tubing inspections:

None Note: Reference Relief Request 10-MN-01 for all applicable conditions.

1.3 Applicable Duke Power Administrative Procedures The following Duke Energy Company procedures will be used to control steam generator tubing inservice inspection activities and inservice inspection plans and reports:

PROCEDURE NUMBER TITLE NSD-300 ASME Section X1 Program NSD-701 Records Management Steam Generator Tubing Inservice Inspection Plan Revision 0 McGuire Nuclear Station 4

0 NSD-702 NSD-703 NSD-704 NSD-800 SGMP Document Control 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).

2.1 Inspection Interval and Inspection Periods Fourth Inspection Interval Start Date End Date 12/01/201 1 12/01/2(

1 st Period Refueling Outage 1 (EOC 22)

Refueling Outage 2 (EOC 23) 014 12/01/2018 11/30/2021 2nd Period 3rd Period Refueling Outage 3 (EOC 24)

Refueling Outage 5 (EOC 26)

Refueling Outage 4 (EOC 25)

Refueling Outage 6 (EOC 27) 3.0 Inspection Methods and Procedures to Be Used for Inservice Inspection Inservice inspection of McGuire Unit 1 will be performed using procedures which comply with the requirements of the applicable codes referenced in Section 1 of this plan. The volumetric 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.

NSD 703 will be used to review, approve, and control all vendor procedures that are used to perform the steam generator tubing inservice inspection.

3.1 Volumetric Inspection Steam generator tubing will be examined using a volumetric inspection method to meet the requirements of Section XI and the McGuire Technical Specifications. The Steam Generator Maintenance and Engineering group of the Corporate Programs and Component Engineering division has overall responsibility for implementing and reporting inspections pertaining to steam generator tubing.

Steam Generator Tubing Inservice Inspection Plan McGuire Nuclear Station Revision 0 5

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 XI.

4.1 Examination Categories and Requirements The examination category for steam generators is listed in Table IWB-2500-1 of Section Xl.

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 B116.20 Steam Generator Tubing in Straight Design Steam Generator Tubing in U-Tube Design N/A for McGuire Unit 1 S/G Tubing is examined and documented by the Steam Generator Maintenance and Engineering group of the Corporate Programs and Components Engineering division as required by the MNS Technical Specifications Sect. 5.5.9.

4.2 Specific Steam Generator Item Number with Corresponding ID Number, General Arrangement and As-Built Drawings Steam Generator A

B C

D Item Number B136.20.001 B16.20.002 B16.20.003 B16.20.004 ID Number 1 NC SGO005 1 NC SG0006 1NC SGO007 1 NC SGO008 Drawing Number MC 1201.01-0853 MC 1201.01-0850 MC 1201.01-0852 MC 1201.01-0851 Right Hand Vessel General Arrangement (B&D) - MCM 1201.01-0683 Left Hand Vessel General Arrangement (A&C) - MCM 1201.01-0684 4.3 Steam Generator Tubing Material and Dimensions Tubing Part Number 5158154 Material SB-163 UNS N06690 0.6875" Outside Diameter 0.040" Wall Thickness Steam Generator Tubing Inservice Inspection Plan McGuire Nuclear Station Revision 0 6

5.0 Fourth Interval Examination Information The Fourth Interval Inspection of McGuire Unit 1 Steam Generators will be performed in accordance with ASME Section XI and the McGuire Technical Specifications section 5.5.9.

6.0 Calibration Standards 6.1 Eddy Current Calibration Standards Calibration standards that will be used include but are not limited to bobbin, array, MRPC, and plug type standards. Eddy current examinations are scheduled and performed in accordance with ASME Section XI and the McGuire Technical Specifications Section 5.5.9.

6.2 Calibration Standard Description Calibration Standards are precision machined materials of the same type/size as the tubing in the Steam Generators with precision machined flaws used to calibrate Eddy Current.

Steam Generator Tubing Inservice Inspection Plan McGuire Nuclear Station Revision 0 7