Text

Fourth Inservice Inspection Interval Steam Generator Tube Plan
	ML15280A342
Person / Time
Site:	Catawba
Issue date:	10/05/2015
From:	Henderson K; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	CNS-l15-087
	Download: ML15280A342 (11)
	v • d • e

DUK

"'ENJERGY Vice President Catawba Nuclear Station Duke Energy CNO1VP I4800 Concord Road York, SC 29745 o: 803.701.4251 f: 803.701.3221 CNS-l15-087 October 5, 2015 10 CFR 50.55a U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001

Subject:

Duke Energy Carolinas, LLC (Duke Energy)

Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Fourth Inservice Inspection Interval Steam Generator Tube Plan Pursuant to 10 CFR 50.55a(g)(4), Duke Energy hereby submits the Catawba Nuclear Station, Units 1 and 2 subject plan for the fourth inservice inspection interval applicable to steam generator tubinlg.

There are no regulatory commitments contained in this letter or its enclosure.

If you have any questions or require additional information, please contact L.J. Rudy at (803) 701-3084.

Kelvin Henderson Vice President, Catawba Nuclear Station Enclosure www.duke-energy.com

U.S. Nuclear Regulatory Commission October 5, 2015 Page 2 xc (with enclosure):

V.M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1 257 G.E. Miller, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 8 G9A Rockville, MD 20852-2738 G.A. Hutto Ill, Senior Resident Inspector Catawba Nuclear Station

FOURTH INTERVAL STEAM GENERATOR TUBE INSERVICE INSPECTION PLAN CATAWBA NUCLEAR STATION UNITS 1 &2 REVISION 0 Document Number C-ISISG-0169.030.0040 QA Condition 1 f DUKE

ENERGY Prepared By: Date Checked By:. Date AY*

Level III Review:. ,-*.--

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AproedByC~)Z) J Page 1 of 9 FOURTH INTERVAL STEAM GENERATOR TUBE INSERVICE INSPECTION PLAN CATAWDA NUCLEAR STATION UNITS 2.&2 Revision 0 [C-ISISG-0169.030,0(]4a]

Fourth Interval Steam Generator Tube ISI Plan Revision Sheet Page 2 of 9 FOURTH INTERVAL STEAM GENERATOR TUBE INSERVICE INSPECTION PLAN CATAWBA NUCLEAR STATION UNITS 1 & 2 Revision 0 [C-ISISG-0169.030.0040]

CATAWBA NUCLEAR STATION GENERAL INFORMATION Note: The steam generator tubing is not included in Catawba Nuclear Station's 4th interval general station ISI plan. As a result, this stand-alone SG tubing 1SI plan is developed for the 4th Interval.

Plant Location: 4800 Concord Road, York, S. C. 29745 Unit 1 Unit 2 Commercial Service Date: June 29, 1985 August 19, 1986 Fourth Interval Start Date: August 19, 2015 August 19, 2015 Fourth Interval End Date: December 6, 2024 February 24, 2026 Owner: Duke Energy Carolinas, LLC 526 South Church St.

Mail code ECO5A Charlotte, N. C. 28201-1006 Note: Owner will be referred to as Duke or Duke Energy throughout this document.

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TABLE OF CONTENTS Section Title Revision

1. Applicable Codes and Standards for Inservice Inspection 0

2. Inspection Interval and Inspection Periods 0

3. Inspection Methods and Procedures to Be Used for Inservice 0 Inspection 4, Description of Inservice Inspection Plan for Steam Generator Tubing 0

5. Fourth Interval Examination Information 0

6. Calibration Standards 0 Page 4 of 9 FOURTH INTERVAL STEAM GENERATOR TUBE INSERVICE INSPECTION PLAN CATAWBA NUCLEAR STATION UNITS 1 & 2 Revision 0 [C-ISISG-0169.030.0040]

1.0 Applicable Codes and Standards for Inservice Inspection Based on a fourth interval start date of August 19, 2015 for CNS I and CNS 2, the requirements of 10OCFR50.55a(g)(4)(ii), inservice inspection activities for Catawba shall be performed in accordance with the 2007 Edition of ASME Section Xl with the 2008 Addenda, as modified by the 10OCFR50.55a Conditions and ASME Section XI Code Cases included in this Inservice Inspection Plan.

All examinations will be performed to the extent practical within the limitations of design, geometry and materials of construction of the component.

1.1 Additional Codes and Standards Used a) Catawba Nuclear Station Technical Specifications.

b) Nuclear Energy Institute 97-06 Steam Generator Program Rev 3 c) EPRI Pressurized Water Reactor Steam Generator Examination Guidelines Rev 7 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 Catawba Units 1&2 for the Steam Generator Tubing inspections:

N-532-5 Repair/Replacement Activity Documentation Requirements and Inservice Inspection Summary Report Preparation and Submission.

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 PD-EG-ALL-1 701 ASME Section XI Program PD-EG-ALL-1 702 ASME Section Xl Inservice Inspection Program Administration AD-DC-ALL-000 1 Document Control AD-DC-ALL-0002 Records Management NSD 703 Administrative Instructions for Technical Procedures AD-H U-ALL-0004 Procedure and Work Instruction Use and Adherence Page 5 of 9 FOURTH INTERVAL STEAM GENERATOR TUBE INSERVICE INSPECTION PLAN CATAWBA NUCLEAR STATION UNITS 1 & 2 Revision 0 [C-ISISG-0i69.030.0040]

AD-IT-ALL-0002 Software Quality Assurance (SQA)

Program MP/O/A/71 50/1 25 Steam Generator Controlling Procedure for Interfacing Vendor Procedures PD-EG-PWR-1 801 Steam Generator Management Program WG-01 Workplace Guide: Preparation and Implementation of ASME Section Xl Inservice Inspection Plans 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 Table 2.1-1: Catawba 1 Interval and Period Dates Interval 4: August 19,2015 to December 6, 2024 1st Period 2nd Period 3rd Period 8/19/15 to 8/19/18 8/20/18 to 8/19/22 8/20/21 to 12/06/2024 Refueling Outage 1 Refueling Outage 1 Refueling Outage I (EOC22) (EOC24) (EOC27)

Refueling Outage 2 Refueling Outage 2 Refueling Outage 2 O)(EOC23) (EOC25) (EOC28) 0 Refueling Outage 3 (EOC26)

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Table 2.1-1: Catawba 2 Interval and Period Dates Interval 4: August 19,2015 to February 24, 2026

___1st Period 2nd Period 3rd Period 8/19/15 to 8/19/18 8/20/18 to 1/19/23 8/20/21 to 2/24/2026 Refueling Outage I Refueling Outage 1 Refueling Outage 1 (EOC21) (EOC23) (EOC26)

Refueling Outage 2 Refueling Outage 2 Refueling Outage 2

*(EOC22) (EOC24) (EOC26) 0 Refueling Outage 1 (EOC25) 3.0 Inspection Methods and Procedures to Be Used for Inservice Inspection Inservice inspection of Catawba Units 1, & 2 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.

Vendor Procedures will be used to perform the steam generator tubing inservice inspection as reviewed and approved by Duke Energy per administrative procedures specified in section 1.3.

3.1 Volumetric Inspection Steam generator tubing will be examined using the eddy current inspection method as required by the applicable codes and standards referenced in Section 1. The Steam Generator Maintenance and Engineering (SGME) Group of the Nuclear Engineering Support Division has overall responsibility for 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.

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4.1 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 Xl, plus an additional number to uniquely identify the steam generator being inspected.

Category B-Q Steam Generator Tubing IWB-2500-1 Component To Be Examined Comments Item B16.10 Steam Generator Tubing in Straight Design N/A for Catawba B16.20 Steam Generator Tubing in U-Tube Design S/G Tubing is examined and documented by the SGME Group of the Nuclear Services Division as required by CNS 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 Item Number ID Number Drawing Number 1A B1 6.020.001 1SGA - Tubes CNM 1201 .01-0757 lB B16.020.002 1SGB - Tubes CNM 1201 .01-0756 10 B16.020.003 1SGC - Tubes CNM 1201 .01-0754 1D B16.020.004 1SGD - Tubes CNM 1201 .01-0755 2A BI16.020.001 2SGA - Tubes CNM 2201 .01-0113 2B B1 6.020.002 2SGB - Tubes CNM 2201 .01-0106 20 B1 6.020.003 2SGC - Tubes CNM 2201 .01-0105 2D B1 6.020.004 2SGD - Tubes CNM 2201 .01-0114 Right Hand Vessel General Arrangement (A&C) - CNM 1201.01-0524 Left Hand Vessel General Arrangement (B&D) - CNM 1201.01-0525 Vessel General Arrangement - CNM 2201.01-0102 4.3 Steam Generator Tubing Material and Dimensions Unit 1 Tubing Part Number 5124383- Material SB-I163 UNS N06690

-0.688" Outside Diameter

- 0.040" Wall Thickness Page 8 of 9 FOURTH INTERVAL STEAM GENERATOR TUBE INSERVICE INSPECTION PLAN CATAWBA NUCLEAR STATION UNITS 1 & 2 Revision 0 [C-1SISG-0169.030.0040]

Unit 2 Tubing Tubing Drawing Numbers CNM 2201.01-0939 -Material SB-i163 Alloy 600 CNM-2201 .01-0635 thru -0.750" Outside Diameter CNM 2201.01-0642 - 0.043" Wall Thickness 5.0 Fourth Interval Examination Information The Fourth Interval Inspection of Catawba Unit 1l&2 Steam Generators will be performed in accordance with ASME Section XI and the Catawba Technical Specifications section 5.5.9.

6.0 Calibration Standards 6.1 Eddy Current Calibration Standards Calibration standards that will be used in the Steam Generator tubing inspection include but are not limited to bobbin (ASME), Array, and EDM notch.

6.2 Calibration Standard Description The SG tubing Eddy Current 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 PrObes. The standards are built to the specifc type of probe used for the inspections. These standards are built and used per the applicable codes and standards referenced in section 1.

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DUK