ML15238A898
| ML15238A898 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/12/2015 |
| From: | Sheldon Clark Duke Energy Carolinas |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML15238A878 | List: |
| References | |
| CNS-15-074 CISI-1462.10.0040-ISI Plan, Rev. 1 | |
| Download: ML15238A898 (58) | |
Text
COVER SHEET Document
Title:
CATAWBA NUCLEAR STATION UNIT 1 AND UNIT 2 -FOURTH INTERVAL INSERVICE INSPECTION PLAN Rev: 001 Document Index Number: CISI-1462.10-0040 -ISI PLAN Addendum Number: N/A Record Retention Number: 421734 Document Owner: Sandy H Clark Q. A. CONDITION 1 Inservice Inspection Related VERIFY HARD COPY AGAINST NEDL PRIOR TO EACH USE
Duke Energy Corporation CATAWBA NUCLEAR STATION UNITS 1 AND 2 FOURTH INTERVAL INSERVICE INSPECTION PLAN Document No. CISl-1462.10.0040-ISI Plan REVISION 1
(/_~ DUKE
~ ENERGY Originated By:
Checked By:
Approved By:
~J-~i>d' Catawba Nuclear Station Units 1 and 2 4rd Interval lnservice Inspection Plan CISl-1462.10.0040-ISI Plan, Rev.1 Date Date Date 8/12/15 gLtzUS' I I y}zj~
I
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 2 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 ISI PLAN REVISION DOCUMENTATION SHEET Revision Number Revision Date Description of Revision Special Instructions to Recipients of this Revision 0
07/23/15 This is the original publication for the fourth Interval ISI Plan for Catawba Nuclear Station Unit 1 and Unit 2. Prepared to support ASME Section XI 2007/2008a.
Original Publication 1
8/12/15 Revise page 3, remove 4th Interval end dates
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 3 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 CATAWBA NUCLEAR STATION GENERAL INFORMATION Catawba Nuclear Stations Inservice Inspection Plan is contained in this document. In addition to the ISI Plan, separate ISI Schedules have been developed for each Unit.
Plant Location:
4800 Concord Road, York, South Carolina 29745 Commercial Service Date:
Catawba Unit 1 Catawba Unit 2 June 29, 1985 August 19, 1986 Fourth Interval Start Date:
Catawba Unit 1 Catawba Unit 2 August 19, 2015 August 19, 2015 Owner: Duke Energy Carolinas, LLC 526 South Church St.
Mail Code EC05A Charlotte, N. C. 28201-1006 Note: Owner shall be referred to as Duke Energy throughout this document.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 4 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Table of Contents SECTION TITLE 1.0 Applicable Codes and Standards for Inservice Inspection 2.0 System Boundaries Subject to Inspection 3.0 Examination Methods and Procedures to be Used for Inservice Inspection 4.0 Description of Inservice Inspection Plan for ASME Class 1 Components 5.0 Description of Inservice Inspection Plan for ASME Class 2 Components 6.0 Description of Inservice Inspection Plan for ASME Class 3 Components 7.0 Augmented and Owner Elective Inservice Inspection Plan 8.0 Description of Examination Listings 9.0 Requests for Relief From ASME Code Requirements 10.0 Calibration Standards 11.0 Inservice Inspection Reference Drawings - Unit 1 12.0 Inservice Inspection Reference Drawings - Unit 2 13.0 Miscellaneous Information and Attachments Inservice Inspection Schedules for Catawba Units 1 and 21 The Inservice Inspection Schedules for Unit 1 and 2 are maintained in separate documents that are filed independently in Nuclear Fusion Electronic Document Management System (EDMS).
Refer to the following documents for the Inservice Inspection Schedules:
- 1.
CISI-1462.10-0040-UNIT 1, Catawba Nuclear Station Unit 1 - Fourth Inspection Interval Inservice Inspection Schedule
- 2.
CISI-1462.10-0040-UNIT 2, Catawba Nuclear Station Unit 2 - Fourth Inspection Interval Inservice Inspection Schedule 1 In addition to the listed ISI Schedules, separate documents may be maintained in Nuclear Fusion Electronic Document Management System (EDMS) that identify and provide explicit examination requirements for each refueling outage.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 5 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 1.0 Applicable Codes and Standards for Inservice Inspection (ISI)
In accordance with the requirements of Paragraphs 10CFR50.55a (g)(4)(ii) (79 FR 73462, Dec.
11, 2014), the inservice inspection of Units 1 and 2 of the Catawba Nuclear Station shall be performed in accordance with the 2007 Edition of ASME Section XI, thru the 2008 Addenda, hereafter referred to asSection XI, subject to the following limitations and modifications:
Paragraph IWB-2500-1, Examination Category B-D (items B3.120 and B3.140), as defined in the 1998 Edition, shall be performed in accordance with 2007 Edition through 2008 addendum of ASME Section XI as required per Paragraph 50.55a(b)(2)(xxi)(A) of 10CFR Part 50. This paragraph allows a VT examination with enhanced magnification to be performed in lieu of the UT examination.
Ultrasonic procedures, personnel and equipment used to examine components listed in ASME Section XI, Appendix I as requiring use of Appendix VIII shall be qualified using the Performance Demonstration Initiative (PDI) Program as modified by 10CFR50.55a (b)(2)(xiv), (xv), and (xvi).
The Scope of this document does not include the Containment ISI Program, Pressure Testing ISI Program, Augmented ISI Program or Steam Generator Tubing program. These are described in the respective standalone program documents.
1.1 Inservice Inspection Basis Document The technical basis for the information included in this document shall be contained in the Catawba Nuclear Station (CNS) Units 1 and 2, ASME Section XI Program, Basis Document for the 4th Inservice Inspection Interval, Document Number CISI-1462.10-0040 - BASISDOC. This basis document shall include detailed information regarding the ASME Section XI requirements in this ISI Plan.
1.2 Code of Federal Regulations 10CFR50.55a Conditions The following mandatory and optional Code of Federal Regulations Conditions are included in 10CFR50.55a (79 FR 73462, Dec. 11, 2014),. These conditions were reviewed for inclusion in the ISI Program per document DUKE-008-001, Revision 0 and include only those 10CFR50.55a conditions applicable to the 2007 Edition with the 2008 Addenda of Section XI. Catawba shall implement these requirements for the Fourth Interval as follows:
1.2.1 10CFR50.55a(b)(2)(ii) - Pressure-Retaining Welds in ASME Code Class 1 Piping (applies to Table IWB-2500 and IWB-2500-1 and Category B-J)
Catawba Nuclear Station shall not utilize the option in 10CFR50.55a(b)(2)(ii), to examine Class 1 piping per ASME Section XI, 1974 Edition with the Summer 1975 Addenda.
1.2.2 10CFR50.55a(b)(2)(ix) - Examination of Metal Containments and the Liners of Concrete Containments Catawba Nuclear Station condition is addressed in the Catawba Nuclear Station Containment Inservice Inspection Plan (CN-ISIC3-1042-0001).
1.2.3 10CFR50.55a(b)(2)(x) - Quality Assurance Catawba Nuclear Station shall apply the requirements of 10CFR50 appendix B per the Duke QA Topical Report and as allowed per ASME Section XI IWA-1400(n)(1).
Therefore, 10CFR50.55a(b)(2)(x) is not applicable.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 6 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 1.2.4 10CFR50.55a(b)(2)(xii) - Underwater Welding The requirements for performing underwater welding as stated in 10CFR50.55a(b)(2)(xii) are not addressed in the Catawba Nuclear Station ISI Plan. This condition applies to repair/replacement activities, which are addressed in Fleet Procedure AD-EG-ALL-1702 and applicable Station Procedures.
1.2.5 10CFR50.55a(b)(2)(xiv) - Appendix VIII Personnel Qualification As allowed by 10CFR50.55a(b)(2)(xiv), for Appendix VIII Qualified Personnel, Catawba Nuclear Station shall use the annual practice requirements in VII-4240 of Section XI Appendix VII in place of the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of annual hands-on training (when deemed appropriate) as discussed in 10CFR50.55a(b)(2)(xiv). When utilizing this option, the annual practice requirements shall be performed on material or welds that contain cracks, or by analyzing prerecorded data from material or welds that contain cracks. All training shall be completed no earlier than 6 months prior to performing ultrasonic examinations. The implementation of ASME Section XI, Appendix VII and VIII requirements is addressed in the procedures listed in Section 3.7 of this document.
1.2.6 10CFR50.55a(b)(2)(xv)
Appendix VIII specimen set and qualification requirements.
Licensees using editions and addenda after 2001 Edition through the 2006 Addenda must use the 2001 Edition of Appendix VIII and may elect to comply with all of the provisions in paragraphs (b)(2)(xv)(A) through (M) of this section, except for paragraph (b)(2)(xv)(F) of this section, which may be used at the licensee's option.
These requirements shall be met during the Catawba 4th Inservice Inspection Interval.
1.2.7 10CFR50.55a(b)(2)(xviii)(A) - Certification of NDE Personnel As required by 10CFR50.55a(b)(2)(xviii)(A), Level I and II nondestructive examination personnel at Catawba Nuclear Station shall be recertified on a 3-year interval in lieu of the 5-year interval specified in IWA-2314(a) and IWA-2314(b) of the 2007 Edition with the 2008 Addenda. The certification of nondestructive examination personnel is addressed in the procedures listed in Section 3.7 of this document.
1.2.8 10CFR50.55a(b)(2)(xix) - Substitution of Alternative Methods As required by 10CFR50.55a(b)(2)(xix), Catawba Nuclear Station shall not apply the rules in IWA-4520(b)(2) and IWA-4521 of Section XI, 2007 Edition with the 2008 Addenda for the substitution of alternative examination methods during repair/replacement activities.
1.2.9 10CFR50.55a(b)(2)(xx)(B) - System Leakage Tests As required by 10CFR50.55a(b)(2)(xx)(B), Catawba Nuclear Station shall apply the rules in IWA-4540(a)(2) of the 2002 Addenda of Section XI when performing system leakage tests after repair and replacement activities performed by welding or brazing on a pressure retaining boundary. This condition applies to repair/replacement activities, which are addressed in Fleet Procedure AD-EG-ALL-1702 and applicable Station Procedures.
1.2.10 10CFR50.55a(b)(2)(xxi)(A) - Table IWB-2500-1 Examination Requirements As required by 10CFR50.55a(b)(2)(xxi)(A), the provisions of Table IWB-2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, Items Nos.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 7 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 B3.120 and B3.140 of Inspection Program B in the 1998 Edition shall be implemented by Catawba Nuclear Station.
As allowed optionally by 10CFR50.55a(b)(2)(xxi)(A), a visual examination with enhanced magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table IWB-3512-1, 2007 Edition with 2008 Addenda, with a limiting assumption on the flaw aspect ratio (i.e., a/l = 0.5), may be performed in place of an ultrasonic examination. Catawba Nuclear Station may perform an enhanced VT examination when the inner radius surface is accessible. When the inner radius surface is not accessible, a UT examination shall be performed.
1.2.11 10CFR50.55a(b)(2)(xxii) - Surface Examination.
As required by 10CFR50.55a(b)(2)(xxii)(B), Catawba Nuclear Station shall not apply the rules in IWA-2220, "Surface Examination," of Section XI, 2007 Edition with the 2008 Addenda that allow use of an ultrasonic examination method.
1.2.12 10CFR50.55a(b)(2)(xxiii) - Evaluation of Thermally Cut Surfaces Prohibition of the use of IWA-4461.4.2, which allows the elimination of mechanical processing of thermally cut surfaces as stated in 10CFR50.55a(b)(2)(xxiii) is not addressed in the Catawba Nuclear Station ISI Plan. This condition applies to repair/replacement activities, which are addressed in Fleet Procedure AD-EG-ALL-1702 and applicable Station Procedures.
1.2.13 10CFR50.55a(b)(2)(xxv) - Mitigation of Defects by Modification Prohibition of the use of IWA-4340 for the mitigation of defects by modification as stated in 10CFR50.55a(b)(2)(xxv) is not addressed in the Catawba Nuclear Station ISI Plan.
This condition applies to repair/replacement activities, which are addressed in Fleet Procedure AD-EG-ALL-1702 and applicable Station Procedures.
1.2.14 10CFR50.55a(b)(2)(xxvi) - Pressure Testing Class 1, 2, and 3 Mechanical Joints Placing restrictions on the pressure testing of replaced components and appurtenances per IWA-4540(c) as stated in 10CFR50.55a(b)(2)(xxvi) is not addressed in the Catawba Nuclear Station ISI Plan. This condition applies to repair/replacement activities, which are addressed in Fleet Procedure AD-EG-ALL-1702 and applicable Station Procedures.
1.2.15 10CFR50.55a(b)(2)(xxvii)-Removal of Insulation When performing visual examination in accordance with IWA-5240 of Section XI of the ASME B&PV Code, 2007 Edition with the 2008 Addenda Catawba Nuclear Station shall remove insulation from 17-4 PH or 410 stainless steel studs or bolts aged at a temperature below 1100 °F or having a Rockwell Method C hardness value above 30, and from A-286 stainless steel studs or bolts preloaded to 100,000 pounds per square inch or higher.
1.2.16 10CFR50.55a(b)(2)(xxviii) - Analysis of Flaws Catawba Nuclear Station shall implement the following conditions when implementing Equation (2) of A-4300(b)(1) of Appendix A:
For R < 0, KI depends on the crack depth (a), and the flow stress (f). The flow stress is defined by f = 1/2(ys + ult), where ys is the yield strength and ult is the ultimate tensile strength in units ksi (MPa) and (a) is in units in. (mm). For -2 R 0 and Kmax -
Kmin 0.8 x 1.12 f (a), S = 1 and KI = Kmax. For R < -2 and Kmax - Kmin 0.8 x 1.12
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 8 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 f (a), S = 1 and KI = (1 - R) Kmax/3. For R < 0 and Kmax - Kmin > 0.8 x 1.12 f (a),
S = 1 and KI = Kmax - Kmin.
1.2.17 10CFR50.55a(b)(2)(xxix) - Nonmandatory Appendix R When implementing Nonmandatory Appendix R,
Risk-Informed Inspection Requirements for Piping, of Section XI, 2007 Edition with the 2008 Addenda, Catawba Nuclear Station shall request and receive prior NRC authorization of this proposed alternative in accordance with paragraph 10CFR50.55a(z).
1.2.18 10CFR50.55a(g)(6)(ii)(D) - Reactor Vessel Head Inspections Catawba Nuclear Station shall meet the criteria of 10CFR50.55a(g)(6)(ii)(D) for the performance of reactor vessel head inspections. These examinations are addressed in the Augmented ISI program document (Doc No. CISI-1462.10-0030-AUGISI-U1&U2).
1.2.19 10CFR50.55a(g)(6)(ii)(E) - Reactor Coolant Pressure Boundary Visual Inspections Catawba Nuclear Station shall meet the criteria of 10CFR50.55a(g)(6)(ii)(E) for the performance of reactor coolant pressure boundary visual inspections. These examinations are addressed in the Augmented ISI program document(Doc No. CISI-1462.10-0030-AUGISI-U1&U2).
1.2.20 10CFR50.55a(g)(6)(ii)(F) - Examination Requirements for Class 1 Piping and Nozzle Dissimilar-Metal Butt Welds Catawba Nuclear Station shall meet the criteria of 10CFR50.55a(g)(6)(ii)(F) for the examination of Class 1 piping and nozzle dissimilar-metal butt welds. These examinations are addressed in the Augmented ISI program document (Doc No. CISI-1462.10-0030-AUGISI-U1&U2).
.1.3 Additional Codes and Standards Used Inspections performed in addition to those required by Section XI are described in Section 7.0 of this Plan. The following codes and standards apply to these inspections:
1.3.1 Steam generator tubing shall be inspected as required by ASME Section XI and the Catawba Technical Specifications for Catawba Nuclear Station. The Steam Generator Maintenance and Engineering Section/Engineering Support GO have overall responsibility for this inspection. This work is planned, implemented, documented and reported independently from this document.
1.3.2 Augmented examinations on certain systems or components shall be performed in accordance with other editions or addenda of ASME Section XI, as identified in the governing commitment. The Augmented Program is outside the scope of the ISI program. See Fleet procedure AD-EG-ALL-1704 and CISI-1462.10-0030-AUGISI-U1-U2.
1.3.3 Owner Elective examinations on certain systems or components shall be performed in accordance with other editions or addenda of ASME Section XI, as identified in the governing commitment.
1.3.4 Ultrasonic procedures, personnel and equipment used to examine components listed in ASME Section XI, Appendix I as requiring use of Appendix VIII shall be qualified using the Performance Demonstration Initiative (PDI) Program as modified by 10CFR50.55a (b)(2)(xiv), (xv), and (xvi).
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 9 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 1.4 Code Cases Applicable to the ASME Boiler and Pressure Vessel Code Section XI All ASME Code Cases listed in Table1 and Table 2 of NRC Regulatory Guide 1.147, Rev. 17 are approved for use during the Catawba Units 1 and 2 4th Inservice Inspection Interval and may be used, even if they are not listed below, provided the Code Case revision is applicable to the 2007 Edition with the 2008 Addenda.
The following specific code cases shall be used for the Fourth Interval Inservice Inspection Program at Catawba Units 1 and 2:
CODE CASE TITLE APPLICABILITY N-513-3 Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or Class 3 Piping,Section XI, Division 1. This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 2, with the following condition:
The repair or replacement activity temporarily deferred under the provisions of this Code Case shall be performed during the next scheduled outage.
1983 Edition with the Winter 1985 Addenda through the 2007 Edition with the 2008 Addenda N-532-5 Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000,Section XI, Division 1 (This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 1).
1995 Edition with the 1996 Addenda through the 2010 Edition N-586-1 Alternative Additional Examination Requirements for Classes 1, 2 and 3 Piping, Components, and Supports,Section XI, Division 1. (This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 1).
1977 Edition with the Summer 1978 Addenda through the 2007 Edition with the 2008 Addenda N-613-1 Ultrasonic Examination of Full Penetration Nozzles in Vessels, Examination Category B-D, Item Nos B3.10 and B3.90, Reactor Nozzle-To-Vessel Welds, Figs. IWB-2500-7(a), (b), and (c)
Section XI, Division 1. (This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 1).
1989 Edition with the 1989 Addenda through the 2007 Edition with the 2008 Addenda
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 10 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 CODE CASE TITLE APPLICABILITY N-639 Alternative Calibration Block Material,Section XI, Division 1. This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 2, with the following condition:
Chemical ranges of the calibration block may vary from the materials specification if (1) it is within the chemical range of the component specification to be inspected, and (2) the phase and grain shape are maintained in the same ranges produced by the thermal process required by the material specification.
1986 Edition with the 1987 Addenda through the 2013 Edition N-643-2 Fatigue Crack Growth Rate Curves for Ferritic Steels in PWR Water Environment,Section XI, Division 1. (This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 1).
1977 Edition with the Summer 1978 Addenda through the 2013 Edition N-648-1 Alternate Requirements for Inner Radius Examination of Class 1 Reactor Vessel Nozzles,Section XI Division 1. This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 2, with the following condition:
In lieu of a UT examination, licensees may perform a VT-1 examination in accordance with the code of record for the Inservice Inspection Program utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio.
1977 Edition with the Summer 1978 Addenda through the 2013 Edition N-663 Alternative Requirements for Classes 1 and 2 Surface ExaminationsSection XI, Division 1 (applies to category B-F, B-J, C-F-1, and C-F-2).
(This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 1).
1986 Edition through the 2010 Edition with the 2011 addenda N-706-1 Alternative Examination Requirements of Table IWB-2500- I and Table IWC-2500-1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers,Section XI, Division I (This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 1).
1977 Edition through the 2010 Edition with the 2011 Addenda
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 11 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 CODE CASE TITLE APPLICABILITY N-712 Class 1 Socket Weld Examination.(This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 1).
1986 Edition through the 2010 Edition with the 2011 Addenda N-722-1 Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 600/82/182 Materials,Section XI, Division 1. [Mandated by 10CFR50.55a(g)(6)(ii)(E) with conditions]
1980 Edition Through the 2013 Edition N-729-1 Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds,Section XI, Division 1. [Mandated by 10CFR50.55a(g)(6)(ii)(D) with conditions]
1980 Edition Through the 2004 Edition.
N-735 Successive Inspections of Class 1 and Class 2 Piping Welds. (This Code Case is approved for use in Regulatory Guide 1.147, Revision 17, Table 1).
1995 Edition with the 1996 Addendum through the 2013 Edition N-770-1 Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation ActivitiesSection XI, Division 1.
[Mandated by 10CFR50.55a(g)(6)(ii)(F) with conditions].
1989 Edition through the 2013 Edition.
1.5 Applicable Duke Energy Administrative Procedures The following administrative procedures apply to the Catawba 4th Interval Inservice Inspection Plan:
PROCEDURE NO.
TITLE PD-EG-ALL-1701 ASME Section XI Program AD-EG-ALL-1702 ASME Section XI Inservice Inspection Program Administration
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 12 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 1.6 License Renewal 1.6.1 The Inservice Inspection Plans are credited in the Catawba license renewal application (LRA), as described in UFSAR Section 18.2.15, with managing aging effects associated with the Reactor Coolant System pressure retaining components (including Class 2 portions of the steam generators), their integral attachments, and other structural components within the jurisdiction of ASME Section XI. Refer to UFSAR Section 18.2.15 prior to making changes to the lSI Plan. AR No.1898156 assignment #11 (Reference PIP No.C-12-3009, CA#11)
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 13 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 2.0 System Boundaries Subject to Inspection The boundaries of Class 1, 2 and 3 non-exempt systems are shown on ISI NDE Boundary Drawings listed in Section 11 and 12. Unless otherwise noted, systems designated as Class1 or Class A are equivalent to ASME Class 1, Class 2 or Class B are equivalent to ASME Class 2, and Class 3 or Class C are equivalent to ASME Class 3.
2.1 Class 1 Components Exempted From Volumetric and Surface Examination 2.1.1 Components that are connected to the reactor coolant system and part of the reactor coolant pressure boundary, and that are of such a size and shape so that upon postulated rupture the resulting flow of coolant from the reactor coolant system under normal plant operating conditions is within the capacity of make-up systems that are operable from on-site emergency power. The emergency core cooling systems are excluded from the calculation of makeup capacity. Reference Section XI, Paragraph IWB-1220(a).
2.1.2 Piping of NPS 1 and smaller, except for steam generator tubing. Reference Section XI, Paragraph IWB-1220(b)(1).
2.1.3 Components and piping segments which have one inlet and one outlet, both of which are NPS 1 (DN25) and smaller. Reference Section XI, Paragraph IWB-1220(b)(2).
2.1.4 Components and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 1 pipe. Reference Section XI, Paragraph IWB-1220(b)(3).
2.1.5 Reactor vessel head connections and associated piping, NPS 2 and smaller, made inaccessible by control rod drive penetrations. Reference Section XI, Paragraph IWB-1220(c).
2.1.6 Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe.
Reference Section XI, Paragraph IWB-1220(d).
2.2 Class 2 Components within Residual Heat Removal (RHR), Emergency Core Cooling (ECC), and Containment Heat Removal (CHR) Systems Exempted From Volumetric and Surface Examination 2.2.1 Components and piping segments NPS 4 and smaller in all systems except high pressure safety injection systems. Reference Section XI, Paragraph IWC-1221(a)(1).
2.2.2 Components and piping segments which have one inlet and one outlet, both of which are NPS 4 and smaller in all systems except high pressure safety injection systems.
Reference Section XI, Paragraph IWC-1221(a)(2).
2.2.3 Components and piping segments which have multiple inlets or multiple outlets, whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 pipe in all systems except high pressure safety injection systems.
IWC-1221(a)(3), Footnote (2) clarifies that for heat exchangers, the shell side and the tube side may be considered separate components. Reference Section XI, Paragraph IWC-1221(a)(3).
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 14 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 2.2.4 Components and piping segments 1 1/2 and smaller in high pressure safety injection systems. Reference Section XI, Paragraph IWC-1221(b)(1).
2.2.5 Components and piping segments which have one inlet and one outlet, both of which are 1 1/2 and smaller in high pressure safety injection systems. Reference Section XI, Paragraph IWC-1221(b)(2).
2.2.6 Components and piping segments which have multiple inlets or multiple outlets, whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of 1 1/2 pipe. IWC-1221(b)(3), Footnote (2) clarifies that for heat exchangers, the shell side and the tube side may be considered separate components.
Reference Section XI, Paragraph IWC-1221(b)(3).
2.2.7 Vessels, piping, pumps, valves, and other components and their connections of any size in statically pressurized, passive (i.e., no pumps) safety injection systems.
Reference Section XI, Paragraph IWC-1221(c).
2.2.8 Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operation. Reference Section XI, Paragraph IWC-1221(d).
2.3 Class 2 Components within Systems Other Than RHR, ECC, and CHR Exempted From Volumetric and Surface Examination 2.3.1 For systems, except auxiliary feedwater systems: components and piping segments, NPS 4 and smaller. Reference Section XI, Paragraph IWC-1222(a)(1).
2.3.2 For systems, except auxiliary feedwater systems: components and piping segments which have one inlet and one outlet, both of which are NPS 4 and smaller. Reference Section XI, Paragraph IWC-1222(a)(2).
2.3.3 For systems, except auxiliary feedwater systems: components and piping segments which have multiple inlets or multiple outlets, whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 pipe. IWC-1222(a)(3), Footnote (2) clarifies that for heat exchangers, the shell side and the tube side may be considered separate components. Reference Section XI, Paragraph IWC-1222(a)(3).
2.3.4 For auxiliary feedwater systems: Components and piping segments 1 1/2 and smaller.
Reference Section XI, Paragraph IWC-1222(b)(1).
2.3.5 For auxiliary feedwater systems: components and piping segments which have one inlet and one outlet, both of which are 1 1/2 and smaller. Reference Section XI, Paragraph IWC-1222(b)(2).
2.3.6 For auxiliary feedwater systems: components and piping segments which have multiple inlets or multiple outlets, whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 1-1/2 pipe. IWC-1222(b)(3),
Footnote (2) clarifies that for heat exchangers, the shell side and the tube side may be considered separate components. Reference Section XI, Paragraph IWC-1222(b)(3).
2.3.7 Vessels, piping, pumps, valves, other components, and component connections of any size in systems or portions of systems that operate (when the system function is required) at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200° F. Reference Section XI, Paragraph IWC-1222(c).
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 15 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 2.3.8 Piping and other components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal plant operating conditions.
Reference Section XI, Paragraph IWC-1222(d).
2.4 Class 2 Inaccessible Welds Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe are exempted from examination requirements. Reference Section XI, Paragraph IWC-1223.
2.5 Class 3 Components Exempted From Examination 2.5.1 The requirements of Subsection IWD apply only to those Class 3 components and welded attachments that support the following functions:
(a) reactor shutdown (b) emergency core cooling (c) containment heat removal (d) atmosphere cleanup (e) reactor residual heat removal (f) residual heat removal from spent fuel storage pool 2.5.2 Components and piping segments NPS 4 (DN 100) and smaller. Reference Section XI, Paragraph IWD-1220(a) 2.5.3 Components and piping segments which have one inlet and one outlet, both of which are NPS 4 (DN 100) and smaller. Reference Section XI, Paragraph IWD-1220(b).
2.5.4 Components and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 (DN 100) pipe. Reference Section XI, Paragraph IWD-1220(c).
2.5.5 Components that operate at a pressure of 275 psig or less and at a temperature of 200°F or less in systems (or portions of systems) whose function is not required in support of reactor residual heat removal, containment heat removal, and emergency core cooling. Reference Section XI, Paragraph IWD-1220(d).
2.5.6 Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe.
Reference Section XI, Paragraph IWD-1220(e).
2.6 Class 1, 2, and 3 Supports Exempted From VT-3 Examination Supports exempt from the examination requirements of IWF-2000 are those connected to piping and other items exempted from volumetric, surface, or VT-1 or VT-3 visual examination by IWB-1220, IWC-1220, and IWD-1220. In addition, portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe are also exempt from the examination requirements of IWF-2000. Reference Section XI, Paragraph IWF-1230.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 16 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 2.7 Examination Boundaries Section 11 and 12 contain a listing of ISI Boundary Diagrams that are color-coded to identify Class 1, 2, and 3 components that are subject to the requirements of the ASME Code,Section XI. Color coding on these drawings is used to depict the following:
Red Class 1 Components, not exempted Yellow Class 2 Components, not exempted Green Class 3 Components, not exempted Blue Class 1, 2, or 3 Components that are exempt from examination requirements of IWB-2000, IWC-2000, and IWD-2000, respectively.
Black Components that have not been classified as ASME Class 1, 2, or 3 for application of Section XI rules and are not subject to ASME Section XI Requirements.
Revisions to the plant system flow diagrams are reviewed for additions/changes to the ISI boundaries. These additions/changes are incorporated into the ISI NDE Boundary Drawings and the ISI Plan as necessary. These ISI NDE Boundary Drawings are stored electronically and can be found in the Nuclear Fusion Electronic Document Management System (EDMS).
2.8 Inspection Interval and Inspection Periods Reference Section 8.0 for a matrix of end of cycle vs. outage nomenclature.
Fourth Inspection Interval Unit 1 Start Date End Date 08/19/2015 08/19/2018 8/19/2022 12/06/2024 1ST Period 2ND Period 3RD Period Outage 1 (EOC 22)
Outage 3 (EOC 24)
Outage 6 (EOC 27)
Outage 2 (EOC 23)
Outage 4 (EOC 25)
Outage 5 (EOC 26)
Outage 7 (EOC 28)
Unit 2 Start Date End Date 08/19/2015 08/19/2018 1/19/2023 02/24/2026 1ST Period 2ND Period 3RD Period Outage 1 (EOC 21)
Outage 3 (EOC 23)
Outage 6 (EOC 26)
Outage 2 (EOC 22)
Outage 4 (EOC 24)
Outage 7 (EOC 27)
Outage 5 (EOC 25)
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 17 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Note: The Interval end dates for Unit 1 and 2 are set per AR#1897281 assignment # 8 (PIP C-14-9325) and align with the NRC commitment on start dates for Catawba Nuclear Station Unit 1 period of extended operation of 12/6/2024 and Unit 2 start date for period of extended operation of 02/24/2026.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 18 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 3.0 Examination Methods and Procedures to be used for Inservice Inspection Inservice inspection of Catawba Units 1 and 2 shall be performed using procedures which comply with the requirements of the applicable codes and code cases referenced in Section 1.0 of this plan. Volumetric, surface, and visual methods of examination shall be used as required.
Each examination shall be performed under the QA Program of the organization performing the examination.
A specific examination procedure is referenced for each examination method listed in Section 8.0 of this Plan. Procedures beginning with NDE or PDI are found in the Duke Energy NDE Procedure Manuals. Vendor inspection procedures that are to be used shall be listed in Section 3.7 of this plan as they become identified or included in the vendor contract documentation.
Duke Energy examination procedures shall also be listed in Section 3.7 of this plan.
3.1 Volumetric Examination Volumetric examination shall be performed by manual and/or automated ultrasonic methods, except in some cases where ultrasonic methods are not practical. Radiographic examinations shall be used in these cases in lieu of ultrasonic examinations. Examination of reactor vessel welds shall be performed using an automated ultrasonic inspection device.
Steam generator tubing shall be examined using eddy current inspection methods as outlined in the Catawba Technical Specifications. The Steam Generator Maintenance and Engineering Section/Engineering Support GO have overall responsibility for implementing and reporting any examinations pertaining to the Steam Generator Tubes. This work is planned, implemented, documented and reported independently from this document.
3.2 Surface Examination Surface examination shall be performed using either liquid penetrant or magnetic particle methods. The liquid penetrant method shall be used for all surface examinations on austenitic steels and may also be used on ferritic steel. The magnetic particle method shall only be used on ferritic steel.
3.3 Visual Examination Inservice visual examinations shall be performed using direct methods where practical. Remote visual examinations may be used in some cases. Enhanced visual methods may be used in lieu of ultrasonic for some examinations, as permitted by ASME Section XI and/or 10CFR50.55a.
3.7 Examination Procedures PROCEDURE NO.
TITLE NDE-12 General Radiography Procedure for Preservice and Inservice Inspection NDE-25 Magnetic Particle Examination NDE-35 Liquid Penetrant Examination NDE-62 Visual Examination (VT-1 and VT-3) of Bolting
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 19 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 PROCEDURE NO.
TITLE NDE-63 Remote Visual Examination (VT-1 and VT-3) of Reactor Pressure Vessel Internals NDE-64 Visual Examination (VT-3) of Pump and Valve Internals NDE-65 Visual Examination (VT-1) of Class 3 Welded Attachments and Pump Casing Welds NDE-66 Visual Examination (VT-3) of Hangers, Restraints, Supports and Snubbers NDE-68 VT-2, Visual Examination for Leakage NDE-69 VE Visual Examination of Reactor Pressure Vessel Bottom Mounted Instrument Penetration NDE-70 Visual Examination of Reactor Pressure Vessel Upper Head Penetrations NDE-600 Ultrasonic Examination of Similar Metal Welds in Wrought Ferritic and Austenitic Piping NDE-620 Ultrasonic Examination of Welds in Ferritic Pressure Vessels Greater than 2 Inches in Thickness NDE-640 Ultrasonic Examination using Longitudinal Wave and Shear Wave, Straight Beam Technique NDE-670 Ultrasonic Sizing of Flaws in Wrought Piping NDE-680 Ultrasonic Examination of Nozzle Inner Radii in Ferritic Pressure Vessels NDE-820 Ultrasonic Examination of Welds in Ferritic Pressure Vessels Greater Than 2 Inches in Thickness NDE-830 Ultrasonic Examination of Cast Austenitic Welds Using Refracted Longitudinal Waves at Catawba Nuclear Station NDE-940 Ultrasonic Thickness Measurement and Stud Location and examination of Lifting Rig Pins.
NDE-998 Ultrasonic Examination of Mid and Large Diameter Piping Butt Welds and Base Material for Thermal Fatigue Damage NDE-3630 Ultrasonic Examination of Welds in Pressure Vessels 2 Inches and Less in Thickness PDI-UT-1 PDI Generic Procedure for The Ultrasonic Examination of Ferritic Pipe Welds PDI-UT-2 PDI Generic Procedure for The Ultrasonic Examination of Austenitic Pipe Welds PDI-UT-3 PDI Generic Procedure for the Ultrasonic Through Wall Sizing In Pipe Welds PDI-UT-4 PDI Generic Procedure for The Ultrasonic Examination of Studs and Bolts from the Bore PDI-UT-5 PDI Generic Procedure for Straight Beam Ultrasonic Examination of Bolts and Studs
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 20 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 PROCEDURE NO.
TITLE PDI-UT-6 PDI Generic Procedure for The Manual Ultrasonic Examination of Reactor Vessel Welds PDI-UT-7 PDI Generic Procedure for the Manual Ultrasonic Through Wall and Length Sizing of Ultrasonic Indications in Reactor Pressure Vessel Welds PDI-UT-8 PDI-Generic Procedure for the Ultrasonic Examination of Weld Overlaid Similar and Dissimilar Metal PDI-UT-10 PDI Generic Procedure for The Ultrasonic Examination of Dissimilar Metal Piping Welds PDI-UT-12 Procedure for Manual Phased Array Ultrasonic Examination of Reactor Vessel Welds 54-PT-200 Color Contrast Solvent Removable Liquid Penetrant Examination of Components EPRI-DMW-PA-1 Procedure for Manual Phased Array Ultrasonic Testing of Dissimilar Metal Welds Note: For Catawba Nuclear Station Units 1 and 2 the latest revision of each procedure that has been approved shall be used. These procedures shall have Duke Energy approval prior to implementation. All Vendor procedures with Duke approvals shall be included in contract final report documentation. If used to perform examinations in accordance with the 4th Interval ISI Plan, this list shall be updated to include all vendor procedures used during the 4th Interval.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 21 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 4.0 Description of Inservice Inspection Plan for ASME Class 1 Components The inservice inspection of ASME Class 1 Components shall be performed in accordance with the requirements of Article IWB-2000 of Section XI. A description of examination listings and schedules are found in Section 8.0 of this Plan. Class 1 examinations were scheduled for the Fourth Inspection Interval in accordance with the following table from ASME Section XI Inspection Program:
Table IWB-2411-1 Inspection Interval Inspection Period, Calendar Years of Plant Service Within the Interval Minimum Examinations Completed, %
Maximum Examinations Credited, %
4rd 3
16 50 7
50 (Note 1) 75 10 100 100 Note 1: If the first period completion percentage for any examination category exceeds 34%, at least 16% of the required examinations shall be performed in the second period.
4.1 Examination Categories and Requirements The examination categories to be used are those listed in Table IWB-2500-1 of Section XI.
Specific examinations shall be identified by a Summary Number similar to those listed in Table IWB-2500-1 of Section XI, which is preceded by a C1 or a C2 to designate Catawba Unit 1 or Catawba Unit 2, plus an additional number to uniquely identify that examination. (Example:
C1.B1.22.0003)
Class 1 Components to be inspected include:
Category B-A Pressure Retaining Welds in Reactor Vessel IWB-2500-1 Item No.
Component To Be Examined Comments B1.10 Shell Welds B1.11 Circumferential B1.12 Longitudinal N/A for Catawba 1 B1.20 Head Welds B1.21 Circumferential B1.22 Meridional B1.30 Shell-to-Flange Weld B1.40 Head-to-Flange Weld B1.50 Repair Welds B1.51 Beltline region N/A for Catawba 1 and 2
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 22 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels IWB-2500-1 Item No.
Component To Be Examined Comments Pressurizer B2.10 Shell-to-Head B2.11 Circumferential B2.12 Longitudinal B2.20 Head Welds B2.21 Circumferential N/A for Catawba 1 and 2 B2.22 Meridional N/A for Catawba 1 and 2 Steam Generators (Primary Side)
B2.30 Head Welds B2.31 Circumferential N/A for Catawba 1 and 2 B2.32 Meridional N/A for Catawba 1 and 2 B2.40 Tubesheet-to-Head Weld Heat Exchangers (Primary Side) - Head B2.50 Head Welds B2.51 Circumferential N/A for Catawba 1 and 2 B2.52 Meridional N/A for Catawba 1 and 2 Heat Exchangers (Primary Side) - Shell B2.60 Tubesheet-to-Head Welds N/A for Catawba 1 and 2 B2.70 Longitudinal Welds N/A for Catawba 1 and 2 B2.80 Tubesheet-to-Shell Welds N/A for Catawba 1 and 2
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 23 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category B-D Full Penetration Welded Nozzles in Vessels IWB-2500-1 Item No.
Component To Be Examined Comments Reactor Vessel B3.90 Nozzle-to-Vessel Welds B3.100 Nozzle Inside Radius Section Pressurizer B3.110 Nozzle-to-Vessel Welds B3.120 Nozzle Inside Radius Section See Note Steam Generators (Primary Side)
B3.130 Nozzle-to-Vessel Welds N/A for Catawba 1 and 2 B3.140 Nozzle Inside Radius Section See Note Heat Exchangers (Primary Side)
B3.150 Nozzle-to-Vessel Welds N/A for Catawba 1 and 2 B3.160 Nozzle Inside Radius Section N/A for Catawba 1 and 2 Note: Item Nos. B3.120 and B3.140 of Inspection Program B in the 1998 Edition are included in the table above because of the condition imposed by 10 CFR 50.55a(b)(2)(xxi)(A).
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 24 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category B-F Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles IWB-2500-1 Item No.
Component To Be Examined Comments Reactor Vessel B5.10 NPS 4 or Larger Nozzle-to-Safe End Butt Welds B5.20 Less Than NPS 4 Nozzle-to-Safe End Butt Welds N/A for Catawba 1 and 2 B5.30 Nozzle-to-Safe End Socket Welds N/A for Catawba 1 and 2 Pressurizer B5.40 NPS 4 or Larger Nozzle-to-Safe End Butt Welds B5.50 Less Than NPS 4 Nozzle-to-Safe End Butt Welds N/A for Catawba 1 and 2 B5.60 Nozzle-to-Safe End Socket Welds N/A for Catawba 1 and 2 Steam Generator B5.70 NPS 4 or Larger Nozzle-to-Safe End Butt Welds B5.80 Less Than NPS 4 Nozzle-to-Safe End Butt Welds N/A for Catawba 1 and 2 B5.90 Nozzle-to-Safe End Socket Welds N/A for Catawba 1 and 2 Heat Exchangers B5.100 NPS 4 or Larger Nozzle-to-Safe End Butt Welds N/A for Catawba 1 and 2 B5.110 Less Than NPS 4 Nozzle-to-Safe End Butt Welds N/A for Catawba 1 and 2 B5.120 Nozzle-to-Safe End Socket Welds N/A for Catawba 1 and 2
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 25 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category B-G-1 Pressure Retaining Bolting, Greater Than 2 in. In Diameter IWB-2500-1 Item No.
Component To Be Examined Comments Reactor Vessel B6.10 Closure Head Nuts B6.20 Closure Studs B6.40 Threads in Flange B6.50 Closure Washers, Bushings Pressurizer B6.60 Bolts and Studs N/A for Catawba 1 and 2 B6.70 Flange Surface, when connection disassembled N/A for Catawba 1 and 2 B6.80 Nuts, Bushings, and Washers N/A for Catawba 1 and 2 Steam Generators B6.90 Bolts and Studs N/A for Catawba 2 B6.100 Flange Surface, when connection disassembled N/A for Catawba 2 B6.110 Nuts, Bushings, and Washers N/A for Catawba 2 Heat Exchangers B6.120 Bolts and Studs N/A for Catawba 1 and 2 B6.130 Flange Surface, when connection disassembled N/A for Catawba 1 and 2 B6.140 Nuts, Bushing, and Washers N/A for Catawba 1 and 2 Piping B6.150 Bolts and Studs N/A for Catawba 1 and 2 B6.160 Flange Surface, when connection disassembled N/A for Catawba 1 and 2 B6.170 Nuts, Bushing, and Washers N/A for Catawba 1 and 2 Pumps B6.180 Bolts and Studs B6.190 Flange Surface, when connection disassembled B6.200 Nuts, Bushings, and Washers N/A for Catawba 1 and 2 Valves B6.210 Bolts and Studs N/A for Catawba 1 and 2 B6.220 Flange Surface, when connection disassembled N/A for Catawba 1 and 2 B6.230 Nuts, Bushings, and Washers N/A for Catawba 1 and 2
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 26 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category B-G-2 Pressure Retaining Bolting, 2 in. And Less In Diameter IWB-2500-1 Item No.
Component To Be Examined Comments Reactor Vessel B7.10 Bolts, Studs, and Nuts Pressurizer B7.20 Bolts, Studs, and Nuts Steam Generators B7.30 Bolts, Studs, and Nuts N/A for Catawba 1 Heat Exchangers B7.40 Bolts, Studs, and Nuts N/A for Catawba 1 and 2 Piping B7.50 Bolts, Studs, and Nuts Pumps B7.60 Bolts, Studs, and Nuts Valves B7.70 Bolts, Studs, and Nuts Category B-J Pressure Retaining Welds in Piping IWB-2500-1 Item No.
Component To Be Examined Comments B9.10 NPS 4 or Larger B9.11 Circumferential Welds B9.20 Less Than NPS 4 B9.21 Circumferential Welds other than PWR HPI Systems B9.22 Circumferential Welds of PWR HPI Systems Item No. is new In 4th Interval B9.30 Branch Pipe Connection Welds B9.31 NPS 4 or Larger B9.32 Less Than NPS 4 B9.40 Socket Welds
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 27 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category B-K Welded Attachments for Vessels, Piping, Pumps, and Valves IWB-2500-1 Item No.
Component To Be Examined Comments Pressure Vessels B10.10 Welded Attachments Piping B10.20 Welded Attachments N/A for Catawba 1 and 2 Pumps B10.30 Welded Attachments N/A for Catawba 1 and 2 Valves B10.40 Welded Attachments N/A for Catawba 1 and 2 Category B-L-2 Pump Casings B-M-2 Valve Bodies IWB-2500-1 Item No.
Component To Be Examined Comments Pumps B12.20 Pump Casing (B-L-2)
Valves B12.50 Valve Body, Exceeding NPS 4 (B-M-2)
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 28 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category B-N-1 Interior of Reactor Vessel B-N-2 Welded Core Support Structures and Interior Attachments to Reactor Vessels B-N-3 Removable Core Support Structures IWB-2500-1 Item No.
Component To Be Examined Comments Reactor Vessel B13.10 Vessel Interior (B-N-1)
Each Inspection Period Reactor Vessel (PWR)
B13.50 Interior Attachments Within Beltline Region (B-N-2)
N/A for Catawba 1 and 2 B13.60 Interior Attachments Beyond Beltline Region (B-N-2)
B13.70 Core Support Structure (B-N-3)
Category B-O Pressure Retaining Welds in Control Rod Drive and Instrument Nozzle Housings IWB-2500-1 Item No.
Component To Be Examined Comments Reactor Vessel B14.20 Welds in CRD Housings B14.21 Welds in In-Core Instrumentation Nozzle Housings > NPS 2 inch.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 29 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category B-P All Pressure Retaining Components IWB-2500-1 Item No.
Component To Be Examined Comments B15.10 Pressure Retaining Components Reference Duke Energy Corporation 4th Interval Inservice Inspection Pressure Test Plan B15.20 Pressure Retaining Components Reference Duke Energy Corporation 4th Interval Inservice Inspection Pressure Test Plan Note: Catawba Pressure Testing Plan for 4th Interval is CISI-1462.20.0040-PTPLAN Category B-Q Steam Generator Tubing IWB-2500-1 Item No.
Component To Be Examined Comments B16.10 Steam Generator Tubing in Straight Tube Design N/A for Catawba 1 and 2 B16.20 Steam Generator Tubing in U-Tube Design Reference SG ISI Plan Document
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 30 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category F-A Supports IWF-2500-1 Item No.
Component To Be Examined Comments F1.10 Class 1 Piping Supports (Category A)
See Note F1.11 Class 1 Piping Supports (Category B)
See Note F1.12 Class 1 Piping Supports (Category C)
See Note F1.40 Supports Other Than Piping Supports (Class 1)
Note:
Duke has established Item numbers as shown to categorize support types as specified in Table IWF-2500-1, Footnote (1).
Categories Q-A Appendix Q Welds are inactive in the 4th Interval. These items were examined during the previous interval in accordance with Appendix Q (1998 edition with 2000 Addenda of Section XI) and are now addressed in fleet Procedure AD-EG-ALL-1704, Augmented Inspection Program Administration and are documented in CISI-1462.10-0030-AUGISI-U1&U2, Catawba Nuclear Station Augmented Inservice Inspection Plan and Schedule.
4.2 Selection of Piping Stress Welds for Inservice Inspection Piping welds whose stresses exceed limits specified in Table IWB-2500-1, Examination Category B-J, Footnote (2)(b) shall be selected for inservice inspection in accordance with Article IWB-2000 of Section XI. The selection criteria for each category of Table IWB-2500-1 shall be applied. The specification for identification of Class 1 piping stress welds is Duke Energy Piping Analysis Specification Catawba Nuclear Station CNS-1206.02-01-0008, Section 3.8.7. These are weld locations where the primary plus secondary stress intensity (ASME Section III, Eq. 10, NB-3653.1) is greater than 2.4 Sm for ferritic and austenitic steels, and where the cumulative usage factor (U) exceeded 0.40. Class 1 piping welds that exceed the stress criteria given above are listed below:
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 31 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 4.2.1 Catawba 1 Item Number Weld Number Piping Isometric NDE Boundary Drawings B09.021.008 1NC40-8 CN-1NC-40 CN-ISIN4-1553-1.0 B09.021.029 1NV201-1 CN-1NV-201 CN-ISIN4-1554-1.0 B09.021.030 1NV201-2 CN-1NV-201 CN-ISIN4-1554-1.0 B09.022.010 1NC42-1 CN-1NC-42 CN-ISIN4-1553-1.0 B09.022.011 1NC43-11 CN-1NC-43 CN-ISIN4-1553-1.0 B09.022.014 1NC51-1 CN-1NC-51 CN-ISIN4-1553-1.0 B09.022.015 1NC56-1 CN-1NC-56 CN-ISIN4-1554-1.0 B09.022.021 1NC82-1 CN-1NC-82 CN-ISIN4-1553-1.0 B09.022.031 1NV310-1 CN-1NV-310 CN-ISIN4-1554-1.0 B09.022.032 1NV310-2 CN-1NV-310 CN-ISIN4-1554-1.0 B09.040.013 1NC88-1 CN-1NC-88 CN-ISIN4-1553-1.1 B09.040.014 1NC88-2 CN-1NC-88 CN-ISIN4-1553-1.1 B09.040.015 1NC88-3 CN-1NC-88 CN-ISIN4-1553-1.1 B09.040.016 1NC88-9 CN-1NC-88 CN-ISIN4-1553-1.1 B09.040.017 1NC88-10 CN-1NC-88 CN-ISIN4-1553-1.1 B09.040.018 1NC88-11 CN-1NC-88 CN-ISIN4-1553-1.1 B09.040.019 1NC88-12 CN-1NC-88 CN-ISIN4-1553-1.1 B09.040.046 1NV307-12 CN-1NV-307 CN-ISIN4-1554-1.0 4.2.2 Catawba 2 Item Number Weld Number Piping Isometric NDE Boundary Drawings B09.021.017 2NC51-1 CN-2NC-51 CN-ISIN4-2553-1.0 B09.022.007 2NC52-8 CN-2NC-52 CN-ISIN4-2553-1.0 B09.021.028 2NV119-1 CN-2NV-119 CN-ISIN4-2554-1.0 B09.021.029 2NV119-2 CN-2NV-119 CN-ISIN4-2554-1.0 B09.022.018 2NV185-1 CN-2NV-185 CN-ISIN4-2554-1.0 B09.022.019 2NV185-2 CN-2NV-185 CN-ISIN4-2554-1.0 B09.040.009 2NC74-1 CN-2NC-74 CN-ISIN4-2553-1.0 Note: For the Catawba 4th Interval this list of stress welds could not be validated as accurate and was brought forward from the 3rd Interval ISI Document CISI-1462.10.0030- GEN REQ Section 4.2. AR# 01937922 was generated for CNS Design Engineering to provide validation documentation for the 4th Interval ISI Plan.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 32 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 5.0 Description of Inservice Inspection Plan for ASME Class 2 Components The inservice inspection of ASME Class 2 Components shall be performed in accordance with the requirements of Article IWC-2000 of Section XI. A description of examination listings and schedules are found in Section 8.0 of this Plan. Class 2 examinations were scheduled for the Fourth Inspection Interval in accordance with the following table from ASME Section XI Inspection Program:
Table IWC-2411-1 Inspection Interval Inspection Period, Calendar Years of Plant Service Within the Interval Minimum Examinations Completed, %
Maximum Examinations Credited, %
4th 3
16 50 7
50 Note 1 75 10 100 100 Note 1: If the first period completion percentage for any examination category exceeds 34%, at least 16% of the required examinations shall be performed in the second period.
5.1 Examination Categories and Requirements The examination categories to be used are those listed in Table IWC-2500-1 of Section XI.
Specific examinations shall be identified by a Summary Number, similar to those listed in Table IWC-2500-1 of Section XI, which is preceded by a C1 or a C2 to designate Catawba Unit 1 or Catawba Unit 2, plus an additional number to uniquely identify that examination. (Example C2.C1.10.0001)
Class 2 Components to be inspected include:
Category C-A Pressure Retaining Welds in Pressure Vessels IWC-2500-1 Item No.
Component To Be Examined Comments C1.10 Shell Circumferential Welds C1.20 Head Circumferential Welds C1.30 Tube sheet-to-Shell Weld
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 33 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category C-B Pressure Retaining Nozzle Welds in Vessels IWC-2500-1 Item No.
Component To Be Examined Comments C2.10 Nozzles in Vessels < 1/2 in. Nominal Thickness C2.11 Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Weld C2.20 Nozzles Without Reinforcing Plate in Vessels > 1/2 in. Nominal Thickness C2.21 Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Weld C2.22 Nozzle Inside Radius Section C2.30 Nozzles With Reinforcing Plate in Vessels > 1/2 in. Nominal Thickness C2.31 Reinforcing Plate Welds to Nozzle and Vessel C2.32 Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Welds When Inside of Vessel is Accessible N/A for Catawba 1 and 2 C2.33 Nozzle-to-Shell (Nozzle to Head or Nozzle to Nozzle) Welds When Inside of Vessel is Inaccessible Reference Duke Energy Corporation Inservice Inspection Pressure Test Plan Note: Catawba Pressure Testing Plan for 4th Interval is CISI-1462.20.0040-PTPLAN Category C-C Welded Attachments for Vessels, Piping, Pumps, and Valves IWC-2500-1 Item No.
Component To Be Examined Comments Pressure Vessels C3.10 Welded Attachments Piping C3.20 Welded Attachments Pumps C3.30 Welded Attachments Valves C3.40 Welded Attachments
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 34 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category C-D Pressure Retaining Bolting Greater Than 2 in. In Diameter IWC-2500-1 Item No.
Component To Be Examined Comments Pressure Vessels C4.10 Bolts and Studs N/A for Catawba 1 and 2 Piping C4.20 Bolts and Studs N/A for Catawba 1 and 2 Pumps C4.30 Bolts and Studs N/A for Catawba 1 and 2 Valves C4.40 Bolts and Studs N/A for Catawba 1 and 2 Category C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping IWC-2500-1 Item No.
Component To Be Examined Comments C5.10 Piping Welds > 3/8 in. Nominal Wall Thickness for Piping > NPS 4 C5.11 Circumferential Weld C5.20 Piping Welds >1/5 in. Nominal Wall Thickness for Piping > NPS 2 and
< NPS 4 C5.21 Circumferential Weld C5.30 Socket Welds C5.40 Pipe Branch Connections of Branch Piping > NPS 2 C5.41 Circumferential Weld
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 35 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel Piping IWC-2500-1 Item No.
Component To Be Examined Comments C5.50 Piping Welds > 3/8 in. Nominal Wall Thickness for Piping > NPS 4 C5.51 Circumferential Weld C5.60 Piping Welds >1/5 in. Nominal Wall Thickness for Piping > NPS 2 and
< NPS 4 C5.61 Circumferential Weld C5.70 Socket Welds C5.80 Pipe Branch Connections of Branch Piping > NPS 2 C5.81 Circumferential Weld Category C-H All Pressure Retaining Components IWC-2500-1 Item No.
Component To Be Examined Comments C7.10 Pressure retaining components Reference Duke Energy Corporation Inservice Inspection Pressure Test Plan Note: Catawba Pressure Testing Plan for 4th Interval is CISI-1462.20.0040-PTPLAN CATEGORY F-A SUPPORTS IWF-2500-1 Item No.
Component To Be Examined Comments F1.20 Class 2 Piping Supports (Category A)
See Note F1.21 Class 2 Piping Supports (Category B)
See Note F1.22 Class 2 Piping Supports (Category C)
See Note F1.40 Supports Other Than Piping Supports (Class 2)
Note: Duke has established Item numbers as shown to categorize support types as specified in Table IWF-2500-1, Footnote (1).
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 36 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 6.0 Description of Inservice Inspection Plan for ASME Class 3 Components The inservice inspection of ASME Class 3 Components shall be performed in accordance with the requirements of Article IWD-2000 of Section XI. A description of examination listings and schedules are found in Section 8.0 of this Plan. Class 3 examinations were scheduled for the Fourth Inspection Interval in accordance with the following table from ASME Section XI Inspection Program:
Table IWD-2411-1 Inspection Interval Inspection Period, Calendar Years of Plant Service Within the Interval Minimum Examinations Completed, %
Maximum Examinations Credited, %
[Note 1]
4th 3
16 50 7
50 Note 1 75 10 100 100 Note 1: If the first period completion percentage for any examination category exceeds 34%, at least 16% of the required examinations shall be performed in the second period.
6.1 Examination Categories and Requirements The examination categories to be used are those listed in Table IWD-2500-1 of Section XI.
Specific examinations shall be identified by a Summary Number, similar to those listed in Table IWD-2500-1 of Section XI, which is preceded by a C1 or a C2 to designate Catawba Unit 1 or Catawba Unit 2, plus an additional number to uniquely identify that examination; Example, (C1.D1.10.0001).
Class 3 Components to be inspected include:
Category D-A Welded Attachments for Vessels, Piping, Pumps, and Valves IWD-2500-1 Item No.
Component to be Examined Comments Pressure Vessels D1.10 Welded Attachments Piping D1.20 Welded Attachments Pumps D1.30 Welded Attachments Valves D1.40 Welded Attachments N/A for Catawba 1 and 2
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 37 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Category D-B All Pressure Retaining Components IWD-2500-1 Item No.
Component To Be Examined Comments D2.10 Pressure retaining components Reference Duke Energy Corporation Inservice Inspection Pressure Test Plan Note: Catawba Pressure Testing Plan for 4th Interval is CISI-1462.20.0040-PTPLAN Category F-A Supports IWF-2500-1 Item No.
Component to be Examined Comments F1.30 Class 3 Piping Supports (Category A)
See Note F1.31 Class 3 Piping Supports (Category B)
See Note F1.32 Class 3 Piping Supports (Category C)
See Note F1.40 Supports Other than Piping Supports (Class 3)
Note: Duke has established Item numbers as shown to categorize support types as specified in Table IWF-2500-1, Footnote (1).
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 38 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 7.0 Augmented and Elective Inservice Inspections 7.1 Augmented inservice inspections are addressed in fleet Procedure AD-EG-ALL-1704, Augmented Inspection Program Administration and are documented in CISI-1462.10-0030-AUGISI-U1&U2, Catawba Nuclear Station Augmented Inservice Inspection Plan and Schedule.
7.2 Elective inservice inspections are contained within the Inservice Inspection Plan, but are not required by the ASME Code,Section XI. These examinations are exempt from ANII review, verification and/or record certification. Elective inservice inspections included in the 4th Interval Inservice Inspection Plan are documented in this section:
7.2.1 NI Cold Leg Accumulator Welds Subject to Unanalyzed Thermal Transients (Summary number series H1.1)
Ultrasonic examination shall be performed on specified Class 1 Piping circumferential welds long seam weld and base material.
Exam required is: UT of weld, base metal and longitudinal seam welds.
Frequency is: Once per Interval
Reference:
ER-CNS-99-01 Rev 01 Applicable to Unit 1 and Unit 2.
7.2.2 Thermal Fatigue Volumetric examination per MRP 192 (Summary number series H2.1 Unit 1 and H3.1 Unit 2)
Volumetric examination shall be performed on specified circ welds and base material Applicable to Unit 1 and Unit 2.
Exam required is: UT Frequency is: Every 6 years
Reference:
Unit 1 and 2 ER-CNS-10-05 and ER-CNS-12-02 Interval 3 Unit 1 ISI Plan Addenda 3CNS1-028,3CNS1-037,3CNS1-066 Interval 3 Unit 2 ISI Plan Addenda 3CNS2-035, 3CNS2-072, 3CNS2-079, and 3CNS2-084 7.2.3 Welded attachment 2-R-NC-1929 - Unit 2 only Surface examination (Summary number series Unit 2 H2.1)
Surface examination shall be performed on specified Class 1 Welded Attachment Applicable to Unit 2 only.
Exam required is: Surface Exam Frequency is: Once per Interval
Reference:
ER-CNS-99-02
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 39 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 7.2.4 Westinghouse Technical Bulletin TB-07-02 Rev 01 CRDM Nozzle Interface enhanced video (Summary number series H4.1)
Video Visual exam per TB-0702 Rev 1 and evaluation of results documented in engineering evaluation. These exams to be performed at same time as C1.B4.20.001 and C2.B4.20.001. Remote video inspection of the thermal sleeve to CRDM nozzle interface looking for signs of wear. Physical UT measurements are required to be taken if wear is found. This work would be in scope to RPV internal examination vendor.
Applicable to Unit 1 and Unit 2.
Exam required is: Video Visual exam evaluation by engineering results Frequency is: Once per Interval
Reference:
ER-CNS-14-02
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 40 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 8.0 Description of Examination Listings All ASME Class 1, 2, and 3 systems and components have been reviewed to determine the inservice examination requirements for Catawba Units 1 and 2. Examination Listing and Schedules referenced by this section were written in accordance with the criteria found in Sections 3.0, 4.0, 5.0, 6.0 and 7.0 of this Plan.
For administrative purposes, the printouts identifying NDE examinations to be performed during each Refueling Outage that accompany this ISI Plan (ISI Schedules) shall reflect the refueling outages as shown below. These numbers shall correlate back to the End of Cycles Number for Units 1 and 2.
Unit 1 Outage No.
1 2
3 4
5 6
7 End of Cycle No.
22 23 24 25 26 27 28 Unit 2 Outage No.
1 2
3 4
5 6
7 End of Cycle No.
21 22 23 24 25 26 27 8.1 Examination Information The following information is listed for each examination where applicable:
8.1.1 Summary Number The Summary Number for each examination is composed of three sections. The first section of the Summary number designates the Plant and Unit. The second section designates the Code Item Number for ASME Class 1, Class 2, and Class 3. ASME Class 1, Class 2, and Class 3 Item Numbers are similar to Item numbers assigned in Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1 of Section XI. The third section of the Summary Number designates the unique number for the item. Example C1.B9.11.0001.
Item Numbers for Class 1, 2, and 3 piping supports (IWF-2500-1) are identified as follows:
Class 1 F1.10
= Category A (One directional support)
F1.11
= Category B (Multi-directional support)
F1.12
= Category C (Thermal movement, i.e. springs, snubbers and constant supports)
Class 2 F1.20
= Category A (One directional support)
F1.21
= Category B (Multi-directional support)
F1.22
= Category C (Thermal movement, i.e. springs, snubbers and constant supports)
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 41 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Class 3 F1.30
= Category A (One directional support)
F1.31
= Category B (Multi-directional support)
F1.32
= Category C (Thermal movement, i.e. springs, snubbers and constant supports) 8.1.2 Component ID Number The Component ID Number is selected so that, by using the specified reference drawing(s) and any applicable comments, the area to be examined can be accurately identified. Several different weld identification systems were used by various equipment vendors. A consistent system of weld or component identification has been developed and is described below:
8.1.2.1 The first character of each Component ID Number indicates the Plant and Unit to which the examination applies.
8.1.2.2 The Unit Number is followed by a combination of letters to indicate the component or system to be examined. Some of the abbreviations used are:
Catawba 1 Abbreviation System or Component RPV Reactor Pressure Vessel PZR Pressurizer SGA Steam Generator A SGB Steam Generator B SGC Steam Generator C SGD Steam Generator D RCP Reactor Coolant Pump CA Auxiliary Feedwater System CF Main Feedwater System FD Diesel Generator Engine Fuel Oil System FW Refueling Water System KC Component Cooling System KD Diesel Generator Engine Cooling Water System LD Diesel Generator Engine Lube Oil System NC Reactor Coolant System ND Residual Heat Removal System NI Safety Injection System NS Containment Spray System
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 42 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Abbreviation System or Component NV Chemical and Volume Control System RN Nuclear Service Water System SA Auxiliary Steam System SM Main Steam System SV Main Steam Vent to Atmosphere System TE FDWP Turbine Exhaust System VN Diesel Generator Engine Air Intake & Exhaust System YC Control Area Chilled Water System NSHX Containment Spray Heat Exchanger RHRHX Residual Heat Removal Heat Exchanger SWINJF Seal Water Injection Filter CBD Cation Bed Demineralizer CCP Centrifugal Charging Pump Support CRD CRD Housing CRACC Control Room Area Chiller Condenser CRACWP Control Room Area Chill Water Pump CRAHU Control Room Air Handling Unit DGE Diesel Generator Engine DGEES Diesel Generator Engine Exhaust Silencer DGEJWC Diesel Generator Engine Jacket Water Cooler DGEJWSTP Diesel Generator Engine Jacket Water Standpipe EVAPC Evaporator Cooler FWST Refueling Water Storage Tank LDCA Diesel Generator Engine Lube Oil Cooler A LDSA1 Diesel Generator Engine Lube Oil Strainer 1A1 LDSTA Diesel Generator Engine Lube Oil Sump A DGEJWL Diesel Generator Engine Jacket Water DGELOC Diesel Generator Engine Lube Oil Cooler DGELOF Diesel Generator Engine Lube Oil Tank DGELOS Diesel Generator Engine Lube Oil Strainer DGELOST Diesel Generator Engine Lube Oil Sump Tank
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 43 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Abbreviation System or Component DGPOS Diesel Generator Prelube Oil Strainer DGEESA Diesel Generator Engine Exhaust Silencer DGEIAF Diesel Generator Engine Intake Air Filter ELDHX Excess Letdown Heat Exchanger FPCP Fuel Pool Cooling Pump KCHX Component Cooling Heat Exchanger KCP Component Cooling Pump KCST Component Cooling Surge Tank KFHX Fuel Pool Cooling Heat Exchanger LDF Diesel Generator Lube Oil Filter LDHX Vertical Letdown Heat Exchanger MBD Mixed Bed Demineralizer MDCAP Motor Driven Aux. FDW Pump NSHX Containment Spray Heat Exchanger NSP Containment Spray Pump PDARCP Pulsation Dampener Assembly Reciprocating Charging Pump REPEC Recycle Evaporator Package Evaporator Condenser REGHX Regenerative Heat Exchanger RHRHX RHR Heat Exchanger RHRP Residual Heat Removal RNP Nuclear Service Water Pump RNS Nuclear Service Water Strainer SIP Safety Injection Pump SWHX Seal Water Heat Exchanger TDCAP Turbine Driven Auxiliary Feedwater Pump VCT Volume Control Tank WEPEC Waste Evaporator Package Evaporator Condenser
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 44 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Catawba 2 Abbreviation System or Component RPV Reactor Pressure Vessel PZR Pressurizer SGA Steam Generator A SGB Steam Generator B SGC Steam Generator C SGD Steam Generator D RCP Reactor Coolant Pump CA Auxiliary Feedwater System CF Main Feedwater System FD Diesel Generator Engine Fuel Oil System FW Refueling Water System KC Component Cooling System KD Diesel Generator Engine Cooling Water System LD Diesel Generator Engine Lube Oil System NC Reactor Coolant System ND Residual Heat Removal System NI Safety Injection System NS Containment Spray System NV Chemical and Volume Control System RN Nuclear Service Water System SA Auxiliary Steam System SM Main Steam System SV Main Steam Vent to Atmosphere System TE FDWP Turbine Exhaust System VN Diesel Generator Engine Air Intake & Exhaust System YC Control Area Chilled Water System NSHX Containment Spray Heat Exchanger "A" RHRHX Residual Heat Removal Heat Exchanger SWINJF Seal Water Injection Filter CBD Cation Bed Demineralizer CCP Centrifugal Charging Pump
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 45 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Abbreviation System or Component CRD CRD Housing DGE Diesel Generator Engine Turbocharger / Aftercooler /
Engine Jacket / Engine Driven Lube Oil Pump DGEJWC Diesel Generator Engine Jacket Water Cooler DGEJWLA Diesel Generator Jacket Water DGEJWSTP Diesel Generator Engine Jacket Water Standpipe DGELOC Diesel Generator Engine Lube Oil Cooler DGELOF Diesel Generator Engine Lube Oil Tank DGLOS Diesel Generator Engine Lube Oil Strainer DGLOST Diesel Generator Engine Lube Oil Sump Tank DGPOS Diesel Generator Prelube Oil Strainer DGEES Diesel Generator Engine Exhaust Silencer DGEIAF Diesel Generator Engine Intake Air Filter ELDHX Excess Letdown Heat Exchanger FWST Refueling Water Storage Tank FPCP Fuel Pool Cooling Pump KCHX Component Cooling Heat Exchanger KCP Component Cooling Pump KCST Component Cooling Surge Tank KFHX Fuel Pool Cooling Heat Exchanger LDC Diesel Generator Engine Lube Oil Cooler LDF Diesel Generator Lube Oil Filter LDHX Vertical Letdown Heat Exchanger LDS Diesel Generator Engine Lube Oil Strainer LDST Diesel Generator Engine Lube Oil Sump Tank MBD Mixed Bed Demineralizer MDCAP Motor Driven Aux. FDW Pump NSHX Containment Spray Heat Exchanger NSP Containment Spray Pump PDARCP Pulsation Dampener Assembly Reciprocating Charging Pump REGHX Regenerative Heat Exchanger RHRHX RHR Heat Exchanger
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 46 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 Abbreviation System or Component RHRP Residual Heat Removal Pump RNP Nuclear Service Water Pump RNS Nuclear Service Water Strainer SIP Safety Injection Pump SWHX Seal Water Heat Exchanger TDCAP Turbine Driven Auxiliary Feedwater Pump / Auxiliary Feedwater Pump Turbine Engine VCT Volume Control Tank 8.1.2.3 The remainder of the ID Number shall indicate the exact weld or component to be examined, as shown on the reference drawings.
Additional information shall be included in the comments space when necessary to positively identify the area to be examined.
8.1.3 Drawing Numbers At least one Duke Energy Drawing Number is listed for each examination, if available.
Drawing numbers beginning with "CNM" are vendor's component drawings. Drawing numbers beginning with "CN-ISIN4-" followed by a four digit number are ISI boundary drawings. All listed drawings are available at Catawba Nuclear Station.
8.1.4 Location (Optional)
Location of Item: building, degree, elevation, axis, etc.
8.1.5 Examination Required / Configuration (Pipe to Elbow, Valve to Pipe, Flange to Tee, etc.)
The following abbreviations are used to describe the type of inspection required for each item:
ECT Eddy Current Testing EVT-1 Enhanced VT-1 Inspection (ISI Visual Inspection)
PT Liquid Penetrant Inspection MT Magnetic Particle Inspection RT Radiographic Inspection UT Ultrasonic Inspection VT-1 ISI Visual Inspection VT-3 ISI Visual Inspection (General Condition of Components and Supports)
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 47 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 8.1.6 Procedure The procedures to be used for the examinations were selected by the NDE Level III, for the inspection methods discussed in Section 3 of this plan. The designation "TBD" (to be determined) is used to indicate cases where the procedure is in the process of being written.
8.1.7 Material Type/Grade The following abbreviations are used to indicate the type of material to be examined:
CS Carbon Steel SS Stainless Steel IN Inconel 8.1.8 Diameter The nominal pipe size (NPS) is listed for all valves and piping welds up to 24-inch NPS. The nominal inside diameter is listed for all vendor supplied piping larger than 24-in NPS. The actual outside diameter is listed for all other piping welds.
The nominal outside diameter is listed for examinations of bolts and studs.
For integrally-welded supports or cladding, the smaller weld or area dimension is listed in this category.
8.1.9 Thickness The dimension listed for component or piping welds is the nominal thickness at the weld.
The overall length of bolts or studs is listed in this category when applicable.
The dimension listed for support attachment welds is the thickness of the attachment base material.
8.1.10 Calibration Block The calibration block(s) to be used for the UT examinations were selected by the NDE Level III, from the calibration block listing shown in Section 10 of this plan. The designation "TBD" is used to indicate cases where the calibration block is still being designed and / or fabricated.
8.1.11 Comments Additional information about the specified examination shall be included here when needed.
8.2 Examination Listings 8.2.1 The schedules for all examinations are specified in the following:
CISI-1462.10-0040-UNIT 1, 4th ISI Interval Schedule CISI-1462.10-0040-UNIT 2, 4th ISI Interval Schedule 8.2.1 Unless otherwise specified in the above documents, examinations may be performed in any refueling outage within the specified Inspection Period.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 48 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 9.0 Requests for Relief from ASME Code Requirements Each request for relief from a requirement of the ASME Section XI Code specified in Section 1 of this plan shall be submitted by the Station Regulatory Affairs Section to the Nuclear Regulatory Commission for approval.. The list below contains all requests for relief that affect Inservice Inspection at Catawba Nuclear Station. For a listing of requests for relief pertaining to topics other than Inservice Inspection, contact the Catawba Nuclear Station Regulatory Affairs Section.
Serial Number Description Units Affected Date RFR Submitted Date SER Approved Comments 14-CN-002 Continued Use of High Density Polyethylene (HDPE) Material in Nuclear Safety Related Piping Application.
1 and 2 09/15/2014 06/19/2015
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 49 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 10.0 Calibration Standards 10.1 Ultrasonic Calibration Standards 10.1.1 Calibration standards are prepared for each UT examination listed in this plan. All calibration standards are designed in accordance with the requirements of ASME Section XI.
10.1.2 Catawba Fourth ten year inspection interval intermediate Reactor Pressure Vessel examinations shall be performed using the calibration blocks listed in the Inservice Inspection Plan.
10.1.3 Calibration standards for UT examination shall be selected per the Calibration Block Listing below. The number of the calibration standard used shall be recorded on the inspection data.
10.1.4 Procedure NDE-600 is written to meet the requirements of Appendix VIII and does not require the use of a calibration block. In cases where NDE-600 is specified for use, the calibration block field shall show Component. NDE-600 is for the examination of similar metal piping welds e.g., stainless to stainless pipe welds and carbon to carbon pipe welds.
10.2 Eddy Current Calibration Standards Eddy Current calibration standards are maintained by the Nuclear NDE Inspection Services.
Eddy Current Examinations for Steam Generator tubing are scheduled and performed per the Catawba Improved Technical Specifications.
10.3 Calibration Block Listing For the specific calibration block listing assigned to the examination see the summary number details in the unit schedules for all examinations in the following:
CISI-1462.10-0040-UNIT 1, 4th ISI Interval Schedule CISI-1462.10-0040-UNIT 2, 4th ISI Interval Schedule
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 50 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 11.0 Inservice Inspection Reference Drawings - Unit 1 The following is a list of ISI NDE Reference Drawings used as a reference for Catawba Unit 1 for the Fourth Interval Inservice Inspection Plan. These drawings are color-coded in accordance with Section 2.0 of the ISI Plan.
These ISI NDE Reference Drawings are stored electronically and can be found in the Nuclear Fusion Electronic Document Management System (EDMS).
System Drawing No.
Revision 1
Class 12 Class 22 Class 32 Reactor Coolant System (NC)
CN-ISIN4-1553-1.0 0
X X
CN-ISIN4-1553-1.1 0
X X
X Reactor Coolant System (NC)
CN-ISIN4-1553-1.2 0
X Reactor Coolant System (NC)
CN-ISIN4-1553-1.3 0
X Chemical and Volume Control System (NV)
CN-ISIN4-1554-1.0 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-1554-1.1 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-1554-1.2 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-1554-1.3 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-1554-1.4 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-1554-1.5 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-1554-1.6 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-1554-1.7 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-1554-1.8 0
X Boron Thermal Regeneration System (NR)
CN-ISIN4-1555-1.1 0
X Boron Recycle System (NB)
CN-ISIN4-1556-1.0 0
X X
Boron Recycle System (NB)
CN-ISIN4-1556-1.1 0
X Boron Recycle System (NB)
CN-ISIN4-1556-1.2 0
X Boron Recycle System (NB)
CN-ISIN4-1556-1.3 0
X Boron Recycle System (NB)
CN-ISIN4-1556-1.4 0
X Boron Recycle System (NB)
CN-ISIN4-1556-1.6 0
X Boron Recycle System (NB)
CN-ISIN4-1556-2.0 0
X Containment Air Return Exchange & Hydrogen Skimmer System (VX)
CN-ISIN4-1557-1.0 0
X ICE Condenser Refrigeration System (NF)
CN-ISIN4-1558-2.0 0
X Containment Hydrogen Sample& Purge System (VY)
CN-ISIN4-1559-1.0 0
X Residual Heat Removal System (ND)
CN-ISIN4-1561-1.0 0
X X
Residual Heat Removal System (ND)
CN-ISIN4-1561-1.1 0
X X
Safety Injection System (NI)`
CN-ISIN4-1562-1.0 0
X X
Safety Injection System (NI)
CN-ISIN4-1562-1.1 0
X X
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 51 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 System Drawing No.
Revision 1
Class 12 Class 22 Class 32 Safety Injection System (NI)
CN-ISIN4-1562-1.2 0
X X
Safety Injection System (NI)
CN-ISIN4-1562-1.3 0
X X
Safety Injection System (NI)
CN-ISIN4-1562-1.4 0
X Containment Spray System (NS)
CN-ISIN4-1563-1.0 0
X Annulus Ventilation System (VE)
CN-ISIN4-1564-1.0 0
X Liquid Radwaste System (WL)
CN-ISIN4-1565-1.1 0
X Liquid Radwaste System (WL)
CN-ISIN4-1565-1.4 0
X Liquid Radwaste System (WL)
CN-ISIN4-1565-1.5 0
X Liquid Radwaste System (WL)
CN-ISIN4-1565-2.0 0
X X
Liquid Radwaste System (WL)
CN-ISIN4-1565-2.1 0
X Liquid Radwaste System (WL)
CN-ISIN4-1565-2.2 0
Liquid Radwaste System (WL)
CN-ISIN4-1565-2.4 0
X Liquid Radwaste System (WL)
CN-ISIN4-1565-2.6 0
X Waste Gas System (WG)
CN-ISIN4-1567-1.0 0
X X
Waste Gas System (WG)
CN-ISIN4-1567-1.1 0
X X
Waste Gas System (WG)
CN-ISIN4-1567-1.2 0
X Waste Gas System (WG)
CN-ISIN4-1567-1.3 0
X X
Waste Gas System (WG)
CN-ISIN4-1567-1.4 0
X Equipment Decontamination System (WE)
CN-ISIN4-1568-1.0 0
X X
Containment Valve Injection Water System (NW)
CN-ISIN4-1569-1.0 0
X X
Spent Fuel Cooling System (KF)
CN-ISIN4-1570-1.0 0
X X
Spent Fuel Cooling System (KF)
CN-ISIN4-1570-1.1 0
X Refueling Water System (FW)
CN-ISIN4-1571-1.0 0
X Nuclear Sampling System (NM)
CN-ISIN4-1572-1.0 0
X Nuclear Sampling System (NM)
CN-ISIN4-1572-1.1 0
X Nuclear Sampling System (NM)
CN-ISIN4-1572-1.2 0
X Nuclear Sampling System (NM)
CN-ISIN4-1572-1.4 0
X Component Cooling System (KC)
CN-ISIN4-1573-1.0 0
X Component Cooling System (KC)
CN-ISIN4-1573-1.1 0
X Component Cooling System (KC)
CN-ISIN4-1573-1.2 0
X Component Cooling System (KC)
CN-ISIN4-1573-1.3 0
X X
Component Cooling System (KC)
CN-ISIN4-1573-1.4 0
X X
Component Cooling System (KC)
CN-ISIN4-1573-1.5 0
X X
Component Cooling System (KC)
CN-ISIN4-1573-1.6 0
X
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 52 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 System Drawing No.
Revision 1
Class 12 Class 22 Class 32 Component Cooling System (KC)
CN-ISIN4-1573-1.7 0
X X
Component Cooling System (KC)
CN-ISIN4-1573-1.9 0
X Component Cooling System (KC)
CN-ISIN4-1573-2.0 0
X Component Cooling System (KC)
CN-ISIN4-1573-2.1 0
X Component Cooling System (KC)
CN-ISIN4-1573-2.2 0
X Component Cooling System (KC)
CN-ISIN4-1573-2.3 0
X Nuclear Service Water System (RN)
CN-ISIN4-1574-1.0 0
X Nuclear Service Water System (RN)
CN-ISIN4-1574-1.1 0
X Nuclear Service Water System (RN)
CN-ISIN4-1574-1.2 0
X Nuclear Service Water System (RN)
CN-ISIN4-1574-1.4 X
Nuclear Service Water System (RN)
CN-ISIN4-1574-1.5 0
X Nuclear Service Water System (RN)
CN-ISIN4-1574-2.0 0
X Nuclear Service Water System (RN)
CN-ISIN4-1574-2.1 0
X Nuclear Service Water System (RN)
CN-ISIN4-1574-2.2 0
X Nuclear Service Water System (RN)
CN-ISIN4-1574-2.4 0
X Nuclear Service Water System (RN)
CN-ISIN4-1574-2.5 0
X Nuclear Service Water System (RN)
CN-ISIN4-1574-2.8 0
X Containment Purge System (VP)
CN-ISIN4-1576-1.0 0
X Auxiliary Building Ventilation System (VA)
CN-ISIN4-1577-1.2 0
X Fuel Handling Area Ventilation System (VF)
CN-ISIN4-1577-2.0 0
X Control Room Area Ventilation System (VC)
CN-ISIN4-1578-1.0 0
X Control Area Chilled Water System (YC)
CN-ISIN4-1578-2.0 0
X Control Area Chilled Water System (YC)
CN-ISIN4-1578-2.1 0
X Control Area Chilled Water System (YC)
CN-ISIN4-1578-2.2 0
X Control Area Chilled Water System (YC)
CN-ISIN4-1578-2.3 0
X Control Area Chilled Water System (YC)
CN-ISIN4-1578-2.4 0
X Control Area Chilled Water System (YC)
CN-ISIN4-1578-2.5 0
X Steam Generator Blow Down System (BB)
CN-ISIN4-1580-1.0 0
X Ground Water Drainage System (WZ)
CN-ISIN4-1581-1.0 0
X Steam Generator Wet Lay Up Recirculation System (BW)
CN-ISIN4-1584-1.0 0
X Containment Air Release And Addition System (VQ)
CN-ISIN4-1585-1.0 0
CN-ISIN4-1591-1.1 0
X X
Auxiliary Feedwater System (CA)
CN-ISIN4-1592-1.0 0
X Auxiliary Feedwater System (CA)
CN-ISIN4-1592-1.1 0
X X
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 53 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 System Drawing No.
Revision 1
Class 12 Class 22 Class 32 Auxiliary Feedwater System (CA)
CN-ISIN4-1592-1.2 0
X Main Steam System (SM), Main Steam Vent to Atmosphere System (SV)
CN-ISIN4-1593-1.0 0
X Main Steam to Auxiliary Equipment System (SA) Main Steam By-Pass to Condenser System (SB)
CN-ISIN4-1593-1.1 0
X X
Steam Supply to FDWP Turbine System (SP) FDWP Turbine Exhaust System (TE)
CN-ISIN4-1593-1.2 0
X Main Steam System (SM)
CN-ISIN4-1593-1.7 0
X Main Steam System (SM)
CN-ISIN4-1593-1.8 0
X Fire Protection System (RF)
CN-ISIN4-1599-2.1 0
X Fire Protection System (RF)
CN-ISIN4-1599-2.2 0
X Makeup Demineralized Water System (YM)
CN-ISIN4-1601-3.1 0
X Instrument Air System (VI)
CN-ISIN4-1605-1.4 0
X Instrument Air System (VI)
CN-ISIN4-1605-1.14 0
X Station Air System (VS)
CN-ISIN4-1605-2.1 0
X Breathing Air System (VB)
CN-ISIN4-1605-3.2 0
X Diesel Generator Engine Cooling Water System (KD)
CN-ISIN4-1609-1.0 0
X Diesel Generator Engine Lube Oil System (LD)
CN-ISIN4-1609-2.0 0
X Diesel Generator Engine Lube Oil System (LD)
CN-ISIN4-1609-2.2 0
X Diesel Generator Engine Fuel Oil System (FD)
CN-ISIN4-1609-3.0 0
X Diesel Generator Engine Fuel Oil System (FD)
CN-ISIN4-1609-3.1 0
X Diesel Generator Engine Starting Air System (VG)
CN-ISIN4-1609-4.0 0
X Diesel Generator Engine Starting Air System (VG)
CN-ISIN4-1609-4.1 0
X Diesel Generator Engine Air Intake & Exhaust System (VN)
CN-ISIN4-1609-5.0 0
X Diesel Generator Engine Crank Case Vacuum System (ZD)
CN-ISIN4-1609-6.0 0
X Diesel Generator Engine Room Sump Pump System (WN)
CN-ISIN4-1609-7.0 0
X 1 The ISI NDE Boundary Drawings revision number provides a baseline for the development of the ISI Plan. As such, the revision numbers listed need not be updated as each ISI NDE Boundary Drawings is revised.
2 Class 1, 2, and 3 components shown on these drawings are subject to change. Please refer to the specific drawings listed to determine the scope of Class 1, 2, and 3 components shown on these drawings.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 54 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 12.0 Inservice Inspection Reference Drawings - Unit 2 The following is a list of ISI NDE Reference Drawings used for Catawba Unit 2 for the Fourth Interval Inservice Inspection Plan. These drawings are color-coded in accordance with Section 2.0 of the ISI Plan.
These ISI NDE Reference Drawings are stored electronically and can be found in the Nuclear Fusion Electronic Document Management System (EDMS).
System Drawing No.
Revision1 Class 12 Class 22 Class 32 Reactor Coolant System (NC)
CN-ISIN4-2553-1.0 0
X X
CN-ISIN4-2553-1.1 0
X X
X Reactor Coolant System (NC)
CN-ISIN4-2553-1.2 0
X Reactor Coolant System (NC)
CN-ISIN4-2553-1.3 0
X Chemical and Volume Control System (NV)
CN-ISIN4-2554-1.0 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-2554-1.1 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-2554-1.2 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-2554-1.3 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-2554-1.4 0
X Chemical and Volume Control System (NV)
CN-ISIN4-2554-1.5 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-2554-1.6 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-2554-1.7 0
X X
Chemical and Volume Control System (NV)
CN-ISIN4-2554-1.8 0
X Boron Thermal Regeneration System (NR)
CN-ISIN4-2555-1.1 X
Boron Recycle System (NB)
CN-ISIN4-2556-2.0 0
X Containment Air Return Exchange & Hydrogen Skimmer System (VX)
CN-ISIN4-2557-1.0 0
X ICE Condenser Refrigeration System (NF)
CN-ISIN4-2558-2.0 0
X Containment Hydrogen Sample& Purge System (VY) CN-ISIN4-2559-1.0 0
X Residual Heat Removal System (ND)
CN-ISIN4-2561-1.0 0
X X
Residual Heat Removal System (ND)
CN-ISIN4-2561-1.1 0
X X
Safety Injection System (NI)`
CN-ISIN4-2562-1.0 0
X X
Safety Injection System (NI)
CN-ISIN4-2562-1.1 0
X X
Safety Injection System (NI)
CN-ISIN4-2562-1.2 0
X X
Safety Injection System (NI)
CN-ISIN4-2562-1.3 0
X X
Safety Injection System (NI)
CN-ISIN4-2562-1.4 0
X Containment Spray System (NS)
CN-ISIN4-2563-1.0 0
X Annulus Ventilation System (VE)
CN-ISIN4-2564-1.0 0
X
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 55 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 System Drawing No.
Revision1 Class 12 Class 22 Class 32 Liquid Radwaste System (WL)
CN-ISIN4-2565-2.0 0
X X
Liquid Radwaste System (WL)
CN-ISIN4-2565-2.1 0
X Liquid Radwaste System (WL)
CN-ISIN4-2565-2.2 0
X Liquid Radwaste System (WL)
CN-ISIN4-2565-2.4 0
X Liquid Radwaste System (WL)
CN-ISIN4-2565-2.6 0
X Equipment Decontamination System (WE)
CN-ISIN4-2568-1.0 0
X X
Containment Valve Injection Water System (NW)
CN-ISIN4-2569-1.0 0
X X
Spent Fuel Cooling System (KF)
CN-ISIN4-2570-1.0 0
X X
Spent Fuel Cooling System (KF)
CN-ISIN4-2570-1.1 0
X Refueling Water System (FW)
CN-ISIN4-2571-1.0 0
X Nuclear Sampling System (NM)
CN-ISIN4-2572-1.0 0
X Nuclear Sampling System (NM)
CN-ISIN4-2572-1.1 0
X Nuclear Sampling System (NM)
CN-ISIN4-2572-1.2 0
X Nuclear Sampling System (NM)
CN-ISIN4-2572-1.4 0
X Component Cooling System (KC)
CN-ISIN4-2573-1.0 0
X Component Cooling System (KC)
CN-ISIN4-2573-1.1 0
X Component Cooling System (KC)
CN-ISIN4-2573-1.2 0
X Component Cooling System (KC)
CN-ISIN4-2573-1.3 0
X X
Component Cooling System (KC)
CN-ISIN4-2573-1.4 0
X X
Component Cooling System (KC)
CN-ISIN4-2573-1.5 0
X X
Component Cooling System (KC)
CN-ISIN4-2573-1.7 0
X X
Component Cooling System (KC)
CN-ISIN4-2573-2.0 0
X Component Cooling System (KC)
CN-ISIN4-2573-2.1 0
X Component Cooling System (KC)
CN-ISIN4-2573-2.2 0
X Component Cooling System (KC)
CN-ISIN4-2573-2.3 0
X Nuclear Service Water System (RN)
CN-ISIN4-2574-2.0 0
X Nuclear Service Water System (RN)
CN-ISIN4-2574-2.1 0
X Nuclear Service Water System (RN)
CN-ISIN4-2574-2.2 0
X Nuclear Service Water System (RN)
CN-ISIN4-2574-2.4 0
X Nuclear Service Water System (RN)
CN-ISIN4-2574-2.5 0
X Nuclear Service Water System (RN)
CN-ISIN4-2574-2.7 0
X Containment Purge System (VP)
CN-ISIN4-2576-1.0 0
X Fuel Handling Area Ventilation System (VF)
CN-ISIN4-2577-2.0 0
X
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 56 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 System Drawing No.
Revision1 Class 12 Class 22 Class 32 Steam Generator Blow Down System (BB)
CN-ISIN4-2580-1.0 0
X Steam Generator Wet Layup Recirculation System (BW)
CN-ISIN4-2584-1.0 0
X Containment Air Release And Addition System (VQ)
CN-ISIN4-2585-1.0 0
CN-ISIN4-2591-1.1 0
X X
Auxiliary Feedwater System (CA)
CN-ISIN4-2592-1.0 0
X Auxiliary Feedwater System (CA)
CN-ISIN4-2592-1.1 0
X X
Auxiliary Feedwater System (CA)
CN-ISIN4-2592-1.2 0
X Main Steam System (SM), Main Steam Vent to Atmosphere System (SV)
CN-ISIN4-2593-1.0 0
X Main Steam to Auxiliary Equipment System (SA)
Main Steam By-Pass to Condenser System (SB)
CN-ISIN4-2593-1.1 0
X X
Steam Supply to FDWP Turbine System (SP) FDWP Turbine Exhaust System (TE)
CN-ISIN4-2593-1.2 0
X Main Steam System (SM)
CN-ISIN4-2593-1.7 0
X Main Steam System (SM)
CN-ISIN4-2593-1.8 0
X Instrument Air System (VI)
CN-ISIN4-2605-1.5 0
X Breathing Air System (VB)
CN-ISIN4-2605-3.2 0
X Diesel Generator Engine Cooling Water System (KD) CN-ISIN4-2609-1.0 0
X Diesel Generator Engine Lube Oil System (LD)
CN-ISIN4-2609-2.0 0
X Diesel Generator Engine Lube Oil System (LD)
CN-ISIN4-2609-2.2 0
X Diesel Generator Engine Fuel Oil System (FD)
CN-ISIN4-2609-3.0 0
X Diesel Generator Engine Fuel Oil System (FD)
CN-ISIN4-2609-3.1 0
X Diesel Generator Engine Starting Air System (VG)
CN-ISIN4-2609-4.0 0
X Diesel Generator Engine Starting Air System (VG)
CN-ISIN4-2609-4.1 0
X Diesel Generator Engine Air Intake & Exhaust System (VN)
CN-ISIN4-2609-5.0 0
X Diesel Generator Engine Crank Case Vacuum System (ZD)
CN-ISIN4-2609-6.0 0
X Diesel Generator Engine Room Sump Pump System (WN)
CN-ISIN4-2609-7.0 0
X 1 The ISI NDE Boundary Drawings revision number provides a baseline for the development of the ISI Plan. As such, the revision numbers listed need not be updated as each ISI NDE Boundary Drawings is revised.
2 Class 1, 2, and 3 components shown on these drawings are subject to change. Please refer to the specific drawings listed to determine the scope of Class 1, 2, and 3 components shown on these drawings.
Catawba Nuclear Station Units 1 and 2 4rd Interval Inservice Inspection Plan Page 57 of 57 CISI-1462.10.0040-ISI Plan, Rev. 1 13.0 Miscellaneous Information and Attachments 13.1 This section is for future use. The original issue of this document did not have information that was needed for this section.