ML20112A999

Rev 0 to Vol 1 of Inservice Insp Plan for Catawba Nuclear Station

ML20112A999
Person / Time
Site:	Catawba
Issue date:	01/08/1985
From:	Cherry J DUKE POWER CO.
To:
Shared Package
ML20112A980	List: ML20112A979 ML20112A999
References
PROC-850108, NUDOCS 8501100176
Download: ML20112A999 (34)

Text

- ..

o INSERVICE INSPECTION PLAN f

CATAWA NUCLEAR STATION UNITS 1 & 2 LOCATION: YORK COUNT /, SOUTH CAROLINA COMERCIAL SERVICE DATE: MAY, 1985 (UNIT 1 ESTIMATED)

SEPTEMBER, 1986 (UNIT 2 ESTIMATED)

OWNER: DUKE POWER COMPANY 422 S. CHURCH ST.

CHARLOTTE, N. C. 28242 VOLUME 1 REVISION 0 O

PREPARED BY (7. / m /- Y- II REVIEWED BY /~ 7" 7 I ~

APPROVED BY

/ /~ DATE I

hkDO O

OO COPY NO. ASSIGNED TO X

q CONTROLLED UNCONTROLLED LJ INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 1 l C/6550029 l

TABLE OF CONTENTS

.(] SECTION TITLE REVISION Volume 1

1. . Applicable Codes and Standards for the Inservice 0 Inspection of Catawba Units 1 & 2

-2. System Boundaries Subject to Inspection 0

3. Inspection Methods and Procedures to be Used for 0 Inservice Inspection

4. Description of Inservice Inspection Plan for 0 ASME Class 1 Items

5. Description of Inservice Inspection Plan for 0 ASME Class 2 Items

6. Description of Inservice Inspection Plan for 0 ASME Class 3 Items

7. Description of Inservice Inspection Plan for 0 Class MC Components

8. Description of Augmented Inservice Inspection 0 Plan n)

L

9. Description of Examination Listings and Schedules 0

10. Requests for Relief From ASME Code Requirements 0

11. Calibration Standards 0 Volume 2 Detailed Inspection Plans for Catawba Unit 1 Appendix A Catawba Unit 1 Inservice Inspection Examination Listing N/A*

And Schedule Appendix B Catawba Unit 1 Inservice Inspection Reference Drawings N/A*

Volume 3 Detailed Inspection Plans for Catawba Unit 2 Appendix A Catawba Unit 2 Inservice Inspection Examination Listing N/A*

And Schedule Appendix B- Catawba Unit 2 Inservice Inspection Reference Drawings N/A*

(] -

• Volumes 2 & 3 are in preparation and will be issued at a later date.

. INSERVICE INSPECTION PLAN ~ REV. O CATAWBA NUCLEAR STATION PAGE 1 C/6550029

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0 CONTROLLED DISTRIBUTION G

V Copy No. Assigned To Original J. O. Barbour

] 1 C. B. Cheezem 2- J. W. Willis (Catawba) j 3 T. E.' Smith (Lynchburg) 4 R. J. Patterson (Catawba) 5 B. A. Carelock (Maintenance Engineering) t I

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1.0 Applicable Editions and Addenda'of ASME Boiler and Pressure Vessel-Code -

_ hs Section XI In accordance with the requirements of Paragraph 50.55a(g) of 10CFR Part 50, the Inservice Inspection of Units 1 & 2, of the Catawba Nuclear Station will be performed in accordance with the 1980 edition of ASME Section XI, including all addenda through Winter 1981 (hereafter

-referred to asSection XI), to the extent practicable within the limitations of design, geometry and materials of construction of the component. Examinations of Class 3 components included in examination Category D-B will be selected in accordance with Table IWD-2500-1 of the 1980 Edition of ASME Section XI, as allowed by paragraph 50.55a(g)(4)(iv) of 10CFR50.

1.1 Additional Codes and Standards Used Inspections performed in addition to those required by Section XI are described in Section 8 of this Plan. The following codes and standards apply to these inspections.

1.1.1 Reactor coolant pump flywheels will be inspected as required by USNRC Regulatory Guide 1.14, Revision 1, and the Technical Specifications for. Catawba Nuclear Station.

1.1.2 Steam Generator Tubing will be inspected as required by ASME Section XI and the Technical Specifications for Catawba Nuclear (3 Station.

q).

1.1.3 Reactor vessel welds will be inspected in accordance with USNRC Regulatory Guide 1.150, Revision 0, to the extent committed by Duke Power Company.

1.1.4 Augmented inspections on certain systems or components will be performed in accordance with other editions or addenda of ASME Section XI as identified in the governing commitment.

1.2 Code Cases Applicable to the ASME Boiler and Pressure Code Section XI The following code cases will be used for the first interval Inservice Inspection program at Catawba:

1.2.1 Code Case N-98: Ultrasonic Examination - Calibration Block Tolerances. (This code case is approved for use under Regulatory Guide 1.147 Revision 2.)

1.2.2 Code Case N-234: Time Between Ultrasonic Calibration Checks.

(This code case is approved for use under Regulatory Guide 1.147 Revision 2.)

1.2.3 Code Case N-356: Certification Period for Level III NDE Personnel. (This code case has not received generic approval

- for use under Regulatory Guide 1.147 Revision 2.)

.I%)J INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 1 C/6550029

2.0 System Boundaries Subject to Inspection U The boundaries of Class 1 and 2 nonexempt systems are shown on the system flow diagrams in Volume 2 (Appendix B) for Unit 1, Volume 3 (Appendix B) for Unit 2. Unless otherwise noted, systems designated as Class A are equivalent to Class 1, Class B is equivalent to Class 2, and Class C is equivalent to Class 3.

2.1 Components Exempted From Examination 2.1.1 Class 1 component connections, piping, associated valves, and supports for portions of systems which are one inch nominal pipe size and smaller are exempted from surface and volumetric examination, except for steam generator tubing, as allowed u'y ASME Section XI, Paragraph IWB-1220(b).

2.1.2 Class 2 components in systems where the design pressure is equal to or less than 275 psig and the design temperature is equal to or less than 200 F are exempted from surface and volumetric examination, as allowed by ASME Section XI, Paragraph IWC-1220(b).

2.1.3 Class 2 component connections (including nozzles in vessels and pumps), piping, associated valves, and vessels and their attachments that are 4 in. nominal pipe size and smaller are exempted from surface and volumetric examination, as allowed by-gq ASME Section XI, Paragraph IWC-1220(c).

U 2.1.4 Integral Attachments to Class 3 components of 4 inch nominal pipe size and smaller are exempted from VT-3 examination (except for auxiliary feedwater system), as allowed by ASME Section XI, Paragraph IWD-1220.1.

2.1.5 Integral attachments to Class 3 components exceeding 4 inch nominal pipe size are exempted from VT-3 examination provided:

a. The system's function is not required for support of residual heat removal, containment heat removal, or emergency core cooling; and

b. The components operate at a pressure of 275 psig or less and a temperature of 200 F or less.

2.1.6 Embedded or inaccessible portions of containment vessels, parts, and appurtenances with welds that met the requirements of IWE-1221 during construction are exempted as allowed by ASME

.Section XI, Paragraph IWE-1220 (b).

2.2 Examination Boundaries The flow diagrams contained in Volume 2 (Appendix B) for Unit 1 and Volume 3 (Appendix B) for Unit 2 (Controlled Distribution only) are v

INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 1 C/6550029

color coded to identify the inspection required on each portion of the

O system. The code used is described beio :

Red' - Class 1 system, not exempted Yellow - Class 2 system, not exempted

- Uncontrolled copias of this Plan will not contain the color-coded flow diagrams.

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S 3.0 Inspection Methods and Procedures to Be Used for Inservice Inspection '

O ..

Inservice Inspection of Catawba Units 1 & 2 will be performed using ws procedures which comply with the requirements of the applicable codes referenced in Section 1 of this plan. Volumetric, surface, and visual

-methods of inspection will be used as required.

3.1 svolumetric Inspection  ;

m Volumetric ~Ir:pection will be performed by the manual ultrasonic method in most' cases. Inspection of reactor vessel welds will be performed using .an automated ultrasonic inspection device. Main steam and feedwater system welds will be examined by radiography.

Steam generator tubing will be examined using the eddy current method.

m A specific examination procedure is referenced for each volumetric inspection listed in Section 9 of this plan. Procedures'beginning with "ISI" are found in the Babcock and Wilcox Inservice Inspection Manual for Catawba Nuclear Station. These inspections will be performed by Babcock and Wilcox. All other procedures are found in Duke Power

" Company'NDE Manual. These inspections will be performed by Duke Power Company.

3. 2 - . Surface Inspection j V

W f Surface inspection will be performed using either the liquid penetrant

.or magnetic particle. method. The liquid _ penetrant method will be used

' ~ for all-surface inspections on stainless steel and may be used on carbon steel. The magnetic particle method will only be used on carbon steel. L Liquid penetrant inspection will be performed using the solvent removable, color contrast method. Magnetic particle examination will be~

. prepared using /either the color contrast, dry pow 0r method, or the

-fluorescent particle method. Magnetization will be accomplished using either an alternating current yoke or a hal f-wave rectified direct current prod machine.

'f A_ specific examination procedure is referenced for each surface inspection listed in Section 9 of this Plan. Procedures beginning with "ISI" are found in the Babcock L and' Wilcox Inservice Inspection Manual for ' Catawba Nuclear Station. These inspections _ will be performed by Babcock and Wilcox.- All other- procedures are found in the Duke' Power Company NDE Manual. These inspections will be performed by Duke Power.

Company.

-3.3 Visual Inspection The inservice visual inspections will be performed using direct methods-where practical. Remote visual examination, using video monitors, 'may

be used in some cases.

10 11NSERVICE INSPECTION PLAN REV. 0

. CATAWBA NUCLEAR STATION PAGE 1 C/6550029

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A s pecific examination procedure 'is referenced forL each visual

( inspection listed in Section 9 of this Plan. Procedures beginning with "ISI" are found in the Babcock and Wilcox Inservice Inspection Manual for Catawba Nuclear Station. These inspections will be performed by Babcock and Wilcox. All other procedures are found in the Duke -Power Company Quality Assurance Manual. These inspections will be performed by Duke Power Company.

3.4 . Inspection Procedures The following procedures will be used in the Inservice Inspection of Catawba Units 1 & 2:

PROCEDURE NO. TITLE

-ISI-50 Technical Procedure Describing Surface Requirements of Welds, Adjacent Base Metal, and Components for NDE 151-55 Technical Procedure for Sulfur Content Analysis ISI-56 Technical Procedure for Halogen Content Analysis 151-83 Measurement of Ultrasonic Instrument Performance Characteristics 15I-104 Ultrasonic Examination of Ligaments Between Threaded

(] Holes and of Studs and Bolts One Inch and Larger in v Diameter 15I-105 Ultrasonic Examination of Reactor Vessel Closure Nuts 151-114 Ultrasonic Examination of Calibration Blocks Prior to Drilling of Calibration Holes .

'ISI-117 Ultrasonic Examination of Reactor Coolant Pump Motor Flywheel 151-119 Ultrasonic Examination of Stainless Steel and Nickel Base Alloy Weld Seams 151-120 Ultrasonic Examination of Piping and Vessel Welds Joining Similar and Dissimilar Materials 151-125 Ultrasonic Examination for Intergranular Stress

' Corrosion Cracking in Stainless Steel or Nickel Base Alloy Piping ISI-130 Ultrasonic Examination of Vessel Welds and Nozzle Inside Radius Sections ISI-131 Remote Ultrasonic Examination Using the ARIS Device O

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PROCEDURE NO. TITLE O' ISI-240 Penetrant Examination of Weld and Base Materials, Including Studs and Nuts ISI-270: Wet or Dry Methods of Magnetic Particle Examination of Welds, Studs, Bolts, and Pump Motor Flywheels ISI-350 Visual Examination of Welds and Surface Conditions ISI-353 Visual Examination of Pipe Hangers, Supports, and Restraints ISI-362 Identification and Layout of Welds and System ^

Components ISI-423 Multifrequency Eddy Current Examination of .750" 0D x .044" Wall RSG Tubing in Westinghouse Steam Generators ISI-424 Multifrequency Eddy Current Examination of .750" OD x .044" Wall RSG Tubing for Detection of Tube Wear at Support Plates

• ISI-425 Eddy Current Evaluation of Tubing by the Absolute Multicoil (8 x 1) Technique for Detection of Tube n Wear at Support Plates C ISI-460 -Technical Procedure for the Evaluation of Eddy Current Data of Nuclear Grade Steam Generator Tubing ISI-462 Technical Procedure for the Evaluation of Eddy Current Data for Debris and Sludge in Steam Generators ISI-463 Technical Procedure for the Evaluation of Eddy Current Data Generated for the Multielement Probe 151-464 Technical Procedure for the Evaluation of Eddy Current Data of Nuclear Grade Steam Generator Tubing for Wear Fretting ISI-467 Technical Procedure for the Evaluation of Eddy Current Data of Nuclear Grade Steam Generator Tubing for Intergranular Attack NDE-12 General Radiography Procedure for Preservice and Inservice Inspection (1980)

NDE-25 Magnetic Inspection Technique for Preservice and Inservice Inspection (1980) Yoke Method O

INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 3 C/6550029

PROCEDURE NO. TITLE l O^ -

NDE-26 Wet Nonfluorescent and Fluorescent Magnetic Particle i

Examination Techniques for Examination of Pressure Retaining Bolting NDE-35 Liquid Penetrant Examination Technique (Color Contrast, Solvent Removable Method) for Preservice and Inservice Inspection (1980)

NDE-37 Liquid Penetrant Examination Technique (color contrast, High Temperature)

NDE-44 Ultrasonic Examination of Bolts and Studs for Preservice and Inservice Inspection QCL-13_ ISI Visual Examination, VT-1 QCL-14 ISI Visual ~ Examination, VT-3 and VT-4 QCL-15 ISI Visual Examination, VT-2 APP-1 Flaw Indication Characterization The latest revision of each procedure that has been . approved by Duke Power Company for Catawba Nuclear Station will be used. Duke Power n

U approval of Babcock and Wilcox procedures will be indicated by the

' signature of the Quality Assurance Manager, Operations on the title page-of the Babcock and Wilcox Inservice Inspection Manual for Catawba Nuclear Station.

r-U~

INSERVICE. INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 4 C/6550029

l 4.0 Inservice Inspection Plan for ASME Class 1 Items The Inservice Inspection of ASME Class 1 items shall be performed in accordance with the requirements of Paragraph IWB-2100 of- ASME Section XI. Specific examination listings and schedules are described in Section 9 of this Plan.

4.1 Examination Categories and Requirements The examination categories to be used are those listed in Table IWB-2500-1-of ASME Section XI. Specific examinations will be identified by an Item Number composed of the item number assigned in Table IWB-2500-1 of Section XI, plus an additional number to uniquely identify that examination.

IWB-2500-1 Item Component To Be Examined Comments Reactor Vessel Shell Welds-B1.11 Circumferential B1.12 Longitudinal Head Welds Bl.21 Circumferential B1.22 Meridional O B1.30 Sheii-to-rienge weid 81.40 Head-to-Flange Weld Repair Welds B1.51 Beltline region .None Pressurizer Shell-to-Head Welds B2.11 Circumferential B2.12 Longitudinal Head Welds 82.21 Circumferential B2.22 Meridional Steam Generators (Primary Side)

Head Welds 82.31 Circumferential B2.32 Meridional None B2.40 Tubesheet-to-Head Weld (3

V INSERVICE' INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 1 i C/6550029

IWB-2500-1

((). Item . 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 83.120 Nozzle Inside Radius Section Steam Generators (Primary Side)

B3.130 Nozzle-to-Vessel Welds None

.B3.140 Nozzle Inside Radius Section Partial Penetration Welds B4.11 Vessel Nozzles 84.12 Control Rod Drive Nozzles 84.13 Instrumentation Nozzles Pressurizer B4.20 Heater Penetration Welds 85.10 Reactor Vessel Nominal Pipe Size > 4 in.

Nozzle-to-Safe End Butt Welds

() B5.11 Nominal' Pipe Size < 4 in.

Nozzle-to-Safe End Butt Welds None B5.12 Nozzle-to-Safe End Socket. None Welds Pressurizer B5.20 Nominal Pipe Size > 4 in.

Nozzle-to-Safe End Butt Welds B5.21 Nominal Pipe Size < 4 in.

Nozzle-to-Safe End Butt Welds B5. 22 Nozzle-to-Safe End Socket Welds None O

INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 2 C/6550029

==.

IWB-2500-1 Item Component To Be Examined Comments l((])

Steam Generator 85.30 Nominal Pipe Size > 4 in.

Nozzle-to-Safe End Butt Welds 85.31 Nominal Pipe Size < 4 in.

Nozzle-to-Safe End Butt Welds 85.32. Nozzle-to-Safe End Socket None Welds Piping B5.50 Nominal Pipe Size > 4 in.

Dissimilar Metal Butt Welds B5.51 Nominal Pipe Size < 4 in.

Dissimilar Metal Butt Welds B5.52 Dissimilar Metal Socket Welds None Reactor Vessel B6.10 Closure Head Nuts B6.20 Closure Studs, in place B6.30 Closure Studs, when removed

\

B6.40 Threads in Flange B6.50 Closure Washers, Bushings Pressurizer B6.60 Bolts and Studs B6.70 Flange Surface,.when connection disassembled B6.80 Nuts, Bushings, and Washers Steam Generators B6.90 Bolts and Studs 86.100 Flange Surface, when connection disassembled B6.110 Nuts, Bushings, and Washers Piping B6.150 Bolts and Studs B6.160 Flange Surface, when connection disassembled B6.170 Nuts, Bushings, and Washers Pumps B6.180 Bolts and Studs O

INSERVICE INSPECTION PLAN REV. 0 CATAWBA NUCLEAR STATION PAGE 3 C/6550029

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b IW8-2500-1

-O Item Component To Be Examined Comments B6.'190 Flange Surface, when connection disassembled B6.200 Nuts, Bushings, and Washers Valves B6.210 Bolts and Studs B6.220- Flange Surface, when connection

. disassembled B6.230 Nuts, Bushings, and Washers Reactor Vessel B7.10' Bolts, Studs, and Nuts Pressurizer B7.20 Bolts, Studs, and Nuts Steam Generators 87.30 Bolts, Studs, and Nuts Piping B7.50 Bolts, Studs, and Nuts Pumps

( B7.60 Bolts, Studs, and Nuts Valves 87.70 Bolts, Studs, and Nuts CR0 Housings B7.80 Bolts, Studs, and Nuts Reactor Vessel Attachments whose base material B8.10 Integrally Welded Attachments design thickness is 5/8" or greater Pressurizer Attachments whose base material B8.20 Integrally Welded Attachments design thickness is 5/8" or greater Steam Generator Attachments whose base material 88.30 Integrally Welded Attachments design thickness is 5/8" or greater Piping Nominal Pipe Size > 4 in.

B9.11 Circumferential Welds 89.12: Longitudinal Welds Nominal Pipe Size < 4 in.

-B9.21 Circumferential l . 89.22 Longitudinal INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION '

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'IWB-2500-1 Item Component To Be Examined Comments Branch Pipe Connection Welds B9.31 Nominal Pipe' size > 2 in.

'89.32 Nominal Pipe size < 2 in.

B9.40 Socket Welds Piping Attachments whose base material

-B10.10 Integrally Welded Attachments design thickness is 5/8" or greater Pumps . Attachments whose base material

'810.20 Integrally Welded Attachments design thickness is 5/8" or greater Valves Attachments whose base material'

'B10.30 Integrally Welded Attachments design thickness is 5/8" or greater Pumps B12.20 Pump Casing

.B12.30 Valves, Nominal Pipe Size

< 4 in.

Valve Body Welds B12.31 Valves, Nominal Pipe Size

' Os. ~

> 4.in.

VaTve Body Welds:

B12.40 Valve Body, > 4'in.

Nominal Pipe Size 4

Reactor Vessel

-B13.10 Vessel Interior.

^

Reactor Vessel B13.30 Core Support Structure Reactor Vessel B14.10 Welds in CRD Housing-Reactor Vessel B15.10 Pressure Retaining Boundary B15.11 . Pressure Retaining Boundary Pressurizer '

B15.20 . Pressure Retaining Boundary B15.21 Pressure Retaining Boundary INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 5 C/6550029

m IWB-2500-1 Item -Component To Be Examined Comments

~- Q Steam Generators

'B15.30 Pressure Retaining Boundary B15.31 Pressure Retaining Boundary Piping B15.50 Pressure Retaining Boundary B15.51 Pressure Retaining Boundary Pumps B15.60 Pressure Retaining Boundary B15.61 Pressure Retaining Boundary Valves B15.70' Pressure Retaining Boundary

, B15.71 Pressure Retaining Boundary B16.20 Steam Generator Tubing in U-Tube Design n Component Supports V F1.1 (a) Mechanical Attachments, Supports of nonexempt Class 1 Including Bolting components (See par. 2.1)

(b) Welded Attachments (c) _ Component Displacement Settings of Guide and i Stops Misalignment of Supports; Assembly of Support Items (d) Spring Type Supports Constant Load Type Supports Supports of nonexempt Class 1 Shock Absorbers. components (See par. 2.1)

Hydraulic and Mechanical Type Snubbers 4.2 Weld Selection for Inservice Inspection Welds 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 will be applied. Class 1 welds that exceed' the stress criteria given in Table IWB-2500-1 are listed below.

O v

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4.2.1 Reactor Coolant System (NC) h~ Unit 1 Weld Number Piping Isometric Flow Diagram 1NC40-08 CN-1NC-40 CN-1553-1.0 1NC42-01 CN-1NC-42 CN-1553-1.0 INC43-11 CN-1NC-43 CN-1553-1.0 1NC51-01 CN-1NC-51 CN-1553-1.0 INC55 CN-1NC-55 CN-1553-1.0 INC56-01 CN-1NC-56 CN-1553-1.0 1NC62-01 CN-1NC-62 CN-1553-1.0 1NC69-01 CN-1NC-69 CN-1553-1.0 1NC73-01 CN-lhC-73 CN-1553-1.0 1NC82-01 CN-1NC-82 CN-1553-1.0

=INC88-01 CN-1NC-88 CN-1553-1.1 1NC88-02 CN-1NC-88 CN-1553-1.'1 1NC88-03 CN-1NC-88 CN-1553-1.1 1NC88-09 CN-1NC-88 CN-1553-1.1 INC88-11 CN-1NC-88 CN-1553-1.1 INC88-12 CN-1NC-88 CN-1553-1.1 1NC190-24 CN-1NC-190 CN-1553-1.1 4.2.2 Chemical and Volume Control System (NV)

() Unit 1 Weld Number Piping Isometric Flow Diagram INV201-01 CN-1NV-201 CN-1554-1.0 INV201-02 CN-1NV-201 CN-1554-1.0 INV310-01 CN-1NV-310 CN-1554-1.0 1NV310-02 'CN-1NV-310 CN-1554-1.0 O

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5.0 Inservice Inspection Plan For'ASME Class 2 Items 0

The Inservice Inspection of ASME Class. 2 items shall be performed in accordance with the requirements of Paragraph IWC-2500 of ASME Section

XI. . Specific examinationL listings and schedules are described in Section 9 of this Plan.

5.1 Examination Categories and Requirments The. examination -categories to .be used are those listed in Table IWC-2500-1 of ASME Section XI. Specific examinations will be identified by an Item Number, composed of _ the Ites Number assigned in Table IWC-2500-l'of Section XI, plus an additional number to uniquely identify that examination. -Class 2-items to be inspected include:

IWB-2500-1 Item Component To Be Examined Comments C1.10 Shell Circumferential. Welds C1.20 Head Circumferential-Welds-

-C1.30 .Tubesheet-to-Shell Weld

'C2.10- Nozzles'in-Vessels-<- 'in.

Nominal Thickness C2.20 ' Nozzles in Vessels >. in. ,

Nominal Thickness-C2.21 -Nozzle-to-shell (or head) weld C2.22 Nozzle inside radius- Nozzles >12" NPS section Pressure Vesse'1s Attachments whose base material C3.10 Integrally Welded design thickness'is 3/4" or

. Attachments greater Piping Attachments whose base material

~C3.40 Integrally Welded design: thickness.is 3/4" or Attachments greater Pumps Attachments whose base material-iC3.70 Integrally Welded design thickness is 3/4" or Attachments . greater Valves Attachments whose base material C3.100 Integrally Welded- design' thickness is 3/4" or Attachments greater 4~ INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 1 C/6550029

/

T' N

-S IWB-25001 1 .

Item Component To Be Examined

.h .

Comments Pressure Vessels l C4.10 ' Bolts and Studs a

Piping y,

J Bolts and Studs

.C4.20 None

., Pops C4.30 Bolts and Studs None

~

' ~

Valves -

'y C4.40 Bolts and Studs ' None Piping Welds < in.

4 Nominal Walt Thickness

!F C5.11 Circumferential weld C5.12 . Longitudinal weld

5. 9

'~

Piping Welds > in.

m.

• Nominal Wa',1 Thickness N ' 3 ::, . C5.21; Circumfereni.ial weld y .

r

,. C5.22 Longitudindigweld i c!M

. ,[ W'.. Pipe Bran'ch Connections

.C5.'31 ' Circumferential weld hg Pumps ,

": C6.10- Pump-Casing Welds None n.

,1 ;

Valves . .

v u r.

C6.26 / Valve Body Welds - None Pressure Vessels j[ C7.10. Pressure Retaining Components

~

C7. lb Pressure Retai'ning Coniconents u

% '- Piping . . . .

.C7.20 Pressure Retaining Comphnents a

fc C7.21- Pressure Retaining Components

w.

.s-. . ;..

.n o* - , a

' '.;, g .

. Pumps s C7.30'W Pressure Retaining Components

..j. . C7.31  : Pressure, Retaining Cocponents

+

,e i -

'U Valves -

4 d*T') m

C7.40 Pressure Retaining Components

.. . INSERVICE INSPECTION PLAN 'v REV. 0

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IWB-2500-1 Item Component To Be Examined Comments

[]

C7.41 Pressure Retaining Components Component Supports F1.2 (a) Mechanical Attachments Supports of nonexempt Class 2 Including Bolting components (See par. 2.1)

(b) Welded Attachments (c) Component Displacement; Settings of Guides and Stops; Misalignment of Supports; Assembly of Support Items (d) Spring Type Supports Constant Load Type Sup- Supports of nonexempt Class 2 ports Shock Absorbers components (See par. 2.1)

Hydraulic and Mechanical Type Snubbers 5.2 Weld Selection for Inservice Inspection q Welds shall be selected for Inservice Inspection in accordance with

, b Article IWC-2000 of Section XI. The selection criteria for each category of Table IWC-2500-1 will be applied. Class 2 welds that exceed the stress criteria given in Table IWC-2500-1 are listed below.

5.2.1 Auxiliary Feedwater System (CA)

Unit 1 Weld Number Piping Isometric Flow Diagram 1CA66-11 CN-1CA-66 CN-1592-1.1 1CA67-16 CN-1CA-67 CN- 1592-1.1 1CA70-01 CN-1CA-70 CN-1592-1.1 1CA72-01 CN-1CA-72 CN-1592-1.1 1CA73-05 CN-1CA-73 CN-1592-1.1

(.

'V INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 3 C/6550029

k 4

5 4

e

! 5.2.2 Safety Injection System (NI)

.O Unit 1 Weld Numoer Piping Isometric Flow Diagram

1NI7-08 CN-1NI-7 CN-1562-1.3 j INI24-15 CN-INI-24 CN-1562-1.3 i~

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. 6. 0 ' Inservice' Inspection Plan for ASME Class 3 Items .

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(' The' Inservice Inspection of ASME Class 3 items shall be performed in accordance with the requirements of Paragraph IWD-2400 of ASME Section XI. Specific examination ~ listings and schedules. are described in

.Section 9 of this Plan.

i 6.1 Examination Categories and Requirements Examination categories will -be those contained in Table IWD-2500-1 of 4

ASME 'Section XI. Class 3 inspections are composed of the following categories:

IWB-2500-1 Item Component To Be Examined Comments D'.10 1 Pressure Retaining Components

,- D1.20 Integral Attachment -

Component Support and Restraints

' D1.30- Integral Attachment -

Mechanical .and Hydraulic Snubbers n D1.40 Integral Attachment -

(.) Spring Type Supports 01.50: Integral Attachment.-

Constant Load Type Supports 01.60. Integral Attachmenti -

Shock Absorbers D2.10 Pressure Retaining Components 1D2.20- Integral Attachment -

Component Support and Restraints D2.30 Integral Attachment -

Mechanical and Hydraulic Snubbers D2.40- Integral Attachment --

Spring Type Supports

.D2.50 Integral Attachment -

Constant Load-Type Supports' Q

INSERVICE INSPECTION PLAN . REV. 0 CATAWBA NUCLEAR STATION PAGEL1 i C/6550029 l

s IWB-2500 - O- ite- - co ao" eat to se exe i ed ce "ts D2.60 Integral Attachment -

Shock Absorbers D3.10 Pressure Retaining Components

• D3.20 Integral Attachment -

Component Support and Restraints D3.30.. Integral Attachment -

Mechanical.and Hydraulic Snubbers D3.40 Integral Attachment -

Spring Type Supports ,

03.50 Integral Attachment -

. Constant Load Type Supports D3.60 .Iritegral Attachment -  !

Shock Absorbers j Component Supports -

F1.3 (a) Mechanical Attachments Supports of nonexempt Class 3 s .- including Bolting components (See par. 2.1)

(b) Component Displacement;-

-Settings of Guides and Stops; Misalignment of-

. Supports; Assembly of Support Items

~ (c) Spring-Type Supports Constant Load-Type- Supports of nonexempt Class 3 Supports Shock Absorb- components'(See par. 2.1) ers Hydraulic ~and Mechanical Type Snubbers h

' INSERVICE INSPECTION PLAN REV.:0 CATAWBA NUCLEAR STATION - PAGE 2 e

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V 7.0- Inservice Inspection for Class MC Components

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The Inservice Inspection of ASME Class MC items shall be performed in accordance with the requirements of paragraph IWE-2400 of ASME. Section ,

XI. Specific examination listing and schedules are described in Section I

9 of this Plan.

7.2 Examination Categories and Requirements Examination categories will be those contained in Table IWE-2500-1 of ASME Section XI. MC Class inspections are composed of the following categories:

IWE-2500-1 Item Component To Be Examined Comments E1.10 Shell Welds E1.20 Flange Welds E1.30 Nozzle-to-Shell Welds

.E1.40 Insert Plate Welds E1.50 Vent System Welds E2.10 Reinforcing Structure Welds E2.20~ Attachment Welds E3.10 Containment Penetration Welds E4.10 Airlock Welds E4.20 Equipment Hatch Welds E5.10 Seals E5.20 Gaskets E6.10 Integral Attachment Welds E7.10 Dissimilar Metal Welds E8.10 Bolted Connections.

E8.20 Bolted Connections E9.10- Pressure Retaining Boundary' See Request for Relief CNS-001 E9.20 Containment Penetration See Request for Relief CNS-001 Bellows.

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INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 1 C/6550029

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i IWB-2500-1

h. Ites Component To Be Examined Comments E9.30-- 'Airlocks See Request for Relief CNS-001 E9.40- Seals and Gaskets See Request for Relief CNS-001 i

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j. 8.0 Augmented Inservice Inspection Plan V Augmented Inservice Inspection shall be performed as required in Section 1 of this Plan. Specific examination listings and schedules are described in Section 9 of this Plan.

8.1 Examination Categories and Requirements

. Items requiring augmented inservice are described in the. following paragraphs. Each inspection will be assigned a unique Item Number.

8.1.1 Reactor Coolant Pump Flywheels The entire volume of the flywheel shall be volumetrically examined by the ultrasonic method, and the exposed surface area shall be examined by the magnetic particle method. These examinations are required by USNRC Regulatory Guide 1.14 Revision 1.

8.1.2 Steam Generator Tubing As a minimum, the examination of Steam Generator tubing shall comply with USNRC Regulatory Guide 1.83, Revision 1 and the applicable Catawba Nuclear Station Technical Specifications.

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8.1.3 Augmented Inservice Inspection to Protect Against Postulated Pipe Failures Augmented Inservice Inspection shall comply with Final Safety Analysis . Report, Section 6.6.8, for Catawba Nuclear Station.

r INSERVICE INSPECTION PLAN' REV. 0

. CATAWBA ~ NUCLEAR STATION' . PAGE 1 C/6550029

o 9.0 Detailed Listing of Examinations for Catawba Units 1 and 2 O- All ASME Class 1, 2, and 3 systems and components have been reviewed to determine the inservice examination requirements for Catawba Units 1 &

2. Examination Listings and Schedules referenced by this section were written in accordance with the criteria found in Sections 3, 4, 5, 6, 7, and 8 of this Plan.

9.1 Examination Information The following information is listed for each examination where applicable:

9.1.1 Item Number The Item Number for each examination is composed of three sections. The first two sections of the item number for ASME Class 1, Class 2, Class 3, or Class MC items are the same as the item numbers assigned in Table IWB-2500-1, 1WC-2500-1, 1WC-2500-1, or IWE-2500-1 of ASME Section XI.

The first two sections of the item number for Augmented Inspections will be chosen as follows:

G01.001 Reactor Coolant Pump Flywheel Examinations.

C02.001 Steam Generator Tube Examinations on

/q Preheater Section V G03.001 Postulated Pipe Failures The last section of the Item Number is a three . or four character sequence to uniquely identify that inspection.

9.1. 2 ID Number-The ID Number is chosen 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:

9.1.2.1 The first character of each ID Number indicates the Unit to which the examination applies.

1 9.1.2.2 The Unit Number is followed by two or three letters to indicate the component or system to be examined. The abbreviations used are:

RPV Reactor Pressure Vessel PZR Pressurizer SGA Steam Generator A c SGB Steam Generator B INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 1 C/6550029

SGC Steam Generator C 1

- (%)- SGD Steam Generator D l RCP Reactor Coolant Pump  ;

ACC Safety Injection Accumulator Tank WAC Upper Head Injection Water Accumulator Tank NAC Upper Head Injection Nitrogen Accumulator Tank CA Auxiliary Feedwater System CF Main Feedwater System FW Refueling Water System KC Component Cooling 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 RV Containment Ventilation Cooling Water System SA Auxiliary Steam System SM Main Steam System SV Main Steam Vent to Atmosphere VQ Containment Air Release and Addition System WL Liquid Waste Recycle System 9.1. 2'. 3 The remainder of the ID Number will indicate the exact weld or component to be examined, as shown on the Reference Drawings. Additional information will be included in the comments space when necessary to positively identify the area to be examined.

Abbreviations were used to indicate the following types of welds:

Safe-End Welds - ID Number ends with "SE" Longitudinal Seam in Fitting - ID Number ends with "L" Westinghouse Butt Weld - ID Number containing "W" Westinghouse Branch Pipe Weld - ID Number containing "WN" 9.1.3 Drawing Numbers At least one Duke _ Drawing Number is listed for- each examination, if available. Drawing numbers beginning with "CNM" are vendor's component drawings. Drawing numbers beginning with "CN " followed by a four digit number are system flow diagrams, and those beginning "CN " followed- by a.

one-digit number and a two-letter system designation (see par.

9.1.2.2) are system piping isometrics.

O INSERVICE-INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 2 C/6550029

r j q 9.1.4 Inspection Required V The following abbreviations are used to describe the type of inspection required for each item: l PT Liquid Penetrant Inspection MT Magnetic Particle Inspection RT Radiographic Inspection UT Ultrasonic Inspection ET Eddy Current Inspection VT1 Visual Inspection General Condition VT2 Visual Inspection Hydrostatic Test Condition VT3 Visual Inspection General Condition of Components and Supports VT4 Visual Inspection Operability of Components or Devices VT Hanger Inspection under QCL-14 (includes VT-3 and VT-4 as applicable) 9.1. 5 Procedure The inspection procedure is listed for each item to be inspected. The procedures are chosen from those in Paragraph 3.4 of this Plan.

9.1.6 Material Type

~ b, . The following abbreviations are used to indicate the type of material to be examined:

CS Carbon Steel SS Stainless Steel IN Inconel 9.1.7 Diameter or Size The actual outside diameter of the weld is listed for pressure vessel welds less than 100 inches in diameter. No entry is made in this category if the weld diameter.is 100 inches or larger.

s 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 Westinghouse - 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

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. bolts and studs.

For integrally - welded supports or cladding, the smaller weld

-- or area dimension is listed in this category.

INSERVICE INSPECTION PLAN REV. O CATAWBA NUCLEAR STATION PAGE 3 C/6550029

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4 9.1. 8 Thickness or Length

-.O The- dimension listed for component or piping welds is the nominal thickness at the weld.

The overall length is listed of bolts or studs is listed in ,

this category when applicable.

The _ larger dimension of. support attachment welds or cladding areas is listed in this category.

9.1.9 Calibration Block The calibration standard to be used for each ET 'or UT

examination is listed in this category. Calibration standards are chosen from those shown in Section 10 of this Plan.

9.1.10 Comments Additional information about the specified examination will be included here when needed.

9.2 Examination Listings

'The -detailed examination listing and schedule for Catawba Units 1 & 2

are found in Volume 2 and 3 of this plan.

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10.0 Requests for Relief from ASME Code Requirements

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Each request for relief from a requirement of the ASME Code specified in Section 1. of this Plan .will be submitted by the Licensing section of Nuclear Production to the Nuclear Regulatory Commission -for approval. A copy of each approved request for relief will be included in this section of the Inservice Inspection Plan.

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Serial No. CNS-001 Page 1 of 2

. (_)s DUKE POWER COMPANY

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Request For Relief From h inservice inspection Requirement Station: Catawba Unit: 1&2 R3ferencs Code: .ASME Boiler and Pressure Vessel Code,Section XI, 1980 Edition through Winter 1981 Addenda

1. Component for which exemption is requested:

a. Nan:e and identi fication Number: Containment System

b. Function: Maintain Containment Integrity .

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c. ASME Section ll1 Code Class: Class MC

d. Valve Category: N/A

11. Reference Code Requirement that has been determined to be impractical:

Table IWE-2500-1; Category E-P; Items E9.11, E 9.20, E9.30, and E9.40 Visual Examination, VT-2

,.qlli. Basis for Requesting Relief:

('~/ Duke Power has always performed these tests by using Nuclear Production oersonnel_and performing the tests in accordance with station Technical Specifications. The test personnel and their supervision are qualified in accordance with ANSI N18.1. Having additional personnel qualified in

~accordance with ASME Section XI or requiring that the existing test per-sonnel be qualified in accordance with ASME Section XI will not improve

Serial No. CNS-001 Page 2 of 2

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111. Basis for Requesting Relief (cont.)

the' existing process. It would however generate additional administra-tive cost or result in additional radiation exposure.

IV. Alternate Examination:

The items listed in Section II will be tested in accordance'with the station Technical Specification and 10CFR50 Accendix J, using Nuclear

(~'i Production personnel, qualified in accordance'with the station Technical

' '#, Specification. This will provide assurance that the intent of ASME

- Secti6n XI is satisfied.

V.. ~lmplementation Schedule:

These tests will be performed at the times specified by the station

- Technical Specifications.and after repair,-replacement, or codification to the pressure retaining boundary.

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4 11.0 Calibration Standards' O ' Calibration Standards are being prepared for each UT or ET inspection

! listed in Section 9 of this Plan. All calibration standards are designed in accordance with the requirements of Section XI,1980 edition including addenda through Winter 1981.

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