ML052500494

Inservice Inspection Report and Steam Generator Outage Summary Report for End-of-Cycle 15 Refueling Outage

ML052500494
Person / Time
Site:	Catawba
Issue date:	08/30/2005
From:	Jamil D Duke Energy Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML052500494 (304)

Text

Duke D.M. JAMIL

_UwPower Vice President Duke Power Catawba Nuclear Station 4800 Concord Road / CN0I VP York, SC 29745-9635 803 831 4251 803 831 3221 fax August 30, 2005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Corporation Catawba Nuclear Station, Unit 1 Docket Number 50-413 Inservice Inspection Report and Steam Generator Outage Summary Report for End of Cycle 15 Refueling Outage Please find attached the subject reports which provide the results of the inservice inspection effort and the steam generator inspection effort associated with the subject outage.

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

If you have any questions concerning this material, please call L.J. Rudy at (803) 831-3084.

Very truly yours, Vr- UO-9wo D.M. Jamil LJR/s Attachments Catawba Nudear Station20th www. dukepower. corn Annivarry 1985-2005

Document Control Desk Page 2 August 30, 2005 xc (with attachments):

W.D. Travers, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 E.F. Guthrie, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station S.E. Peters, Project Manager (addressee only)

U.S. Nuclear Regulatory Commission Mail Stop 0-8 G9 Washington, D.C. 20555-0001

REPORT INSERVICE INSPECTION CATAWBA - UNIT 1 2005 REFUELING OUTAGE EOC 15 (OUTAGE 7)

NRC DOCUMENT CONTROL

K-'

FORM NIS-1 OWNER'S DATA REPOR*F FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner: Duke Energv Corporation. 526 South Church Street Charlotte. NC 28201-1006 (Name and Address of Owner)

2. Plant: Catawba Nuclear Station, 4800 Concord Road. York, SC 29745 (Name and Address of Plant)

3. Plant Unit: I 4. Owner Certificate of Authorization (if required) N/A

5. Commercial Service Date: 6/29/85 6. National Board Number for Unit 130

7. Components Inspected:

Component or Manufacturer Manufacturer State or National Appurtenance Installer Installer Serial Province No. Board No.

No.

Section 1.1 in the attached report.

K>

Note: Supplemental sheets in form of lists. sketches, or drawings may be used provided (1) size is 81/2 in. x 11 in.,

(2) information in items 1 through 6 on this data report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

Total number of pages contained in this report 264

FORM NIS- 1 (Back)

8. Examination Dates December 31, 2003 A to June 6,2005

9. Inspection Period Identification: Third Period

10. Inspection Interval Identification: Second Interval

11. Applicable Edition of Section XI 1989 Addenda None

12. Date/Revision of Inspection Plan: September 9, 1999/ Revision 2

13. Abstract of Examinations and Test. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. See Sections 2.0,3.0 and 6.0

14. Abstract of Results of Examination and Tests. See Sections 4.0 and 6.0

15. Abstract of Corrective Measures. See Subsection 4.3 We certify that a) the statements made in this report are correct b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI, and c) corrective measures taken conform to the rules of the ASME Code,Section XI.

Certificate of Authorization No. (if applicable) N/A Expiration Date N/A Date h Signed Duke Energy Corp. By :t Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of NC employed by

• The Hartford Steam Boiler Inspection and Insurance Comnany of Connecticut have inspected the components described in this Owners' Report during the period 1? 3 i -03 to Scb .and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in the Owners' Report in accordance with the Inspection Plan and as required by the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, test, and corrective measures described in this Owners' Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection

& commissions Cft A/ tL 6 Ins tor's Signature National Board, State, Province, and Endorsements Date _ -_( _ S __-o

• The Hanford Steam Boiler Inspection & Insurance Company of Connecticut 200 Ashford Center North Suite 205 Atlanta, GA. 30338 (800) 417-3721 www.hsbct.com

<-I INSERVICE INSPECTION REPORT CATAWBA - UNIT 1 2005 REFUELING OUTAGE EOC15 (OUTAGE 7)

Location: 4800 Concord Road, York, South Carolina 29745 NRC Docket No. 50-413 National Board No. 130 Commercial Service Date: June 29,1985 Owner: Duke Energy Corporation 526 South Church Street Charlotte, NC 28201-1006 Revision 0 Prepared By:

Reviewed By:

LI( . I t2,, Date X11il 4M:-Zo Approved By: -L (Date

DISTRIBUTION LIST

1) Duke Energy Corporation Quality Assurance Technical Services (QATS) (Original)

2) Duke Energy Corporation Inspection and Welding Services (IWS) Catawba

3) NRC Document Control

4) The Hartford Steam Boiler Inspection and Insurance Company of Connecticut c/o R. N. McGill (ANII)

Catawba Nuclear Station

TABLE OF CONTENTS Section Title Revision 1.0 General Information 0 2.0 Second Ten-Year Interval Inspection Status 0 3.0 Final Inservice Inspection Plan 0 4.0 Results of Inspections Performed 0 5.0 Owners Report for Repair / Replacement Activities 0 6.0 Pressure Testing 0

1.0 General Information This report describes the Inservice Inspection of Duke Energy Corporation's Catawba Nuclear Station Unit 1 during the 2005 Refueling Outage, also referred to as EOC 15 (Outage 7), which is the last outage in the Third Inspection Period of the Second Ten Year Interval.

Included in this report is the inspection status for each examination category, the final inservice inspection plan, the inspection results for each item examined, and corrective actions taken when reportable conditions were found. In addition, there is an Owners Report for Repair/ Replacement Section included for completed NIS-2 documentation of repairs and replacements.

1.1 Identification Numbers Manufacturer State or National Item Manufacturer or Installer Province Board or Installer Serial No. No. No.

Reactor Vessel Westinghouse 30743 N/A N/A Pressurizer Westinghouse DCPT-1911 N/A W18589 Steam Generator Babcock and 770101 N/A 151 1A Wilcox, Inc.

Steam Generator Babcock and 769304 N/A 150 1B Wilcox, Inc.

Steam Generator Babcock and 769302 N/A 147 1C Wilcox, Inc.

Steam Generator Babcock and 769303 N/A 149 1D Wilcox, Inc.

Reactor Coolant lonics, Inc. 1S-86P764 N/A 584 Pump 1A Reactor Coolant lonics, Inc. 2S-86P764 N/A 585 Pump 1B Reactor Coolant Ionics, Inc. 3S-86P764 N/A 330 Pump 1C Reactor Coolant lonics, Inc. 4S-86P764 N/A 331 Pump 1D I I Refueling Outage EOC 15 (Outage 7) Page 1 of 5 Catawba Unit 1 Revision 0 Section 1 August 15, 2005

Identification Numbers (Continued Manufacturer Manufacturer State or National K-,,~ Item or Installer or Installer Province Board Serial No. No. No.

Reactor Coolant Duke Power Co. C-1 NC N/A 126 System Safety Injection Duke Power Co. C-1 NI N/A 128 System Chemical and Duke Power Co. C-1 NV N/A 127 Volume Control System _ _ _a Auxiliary Duke Power Co. C-1CA N/A 121 Feedwater System Feedwater Duke Power Co. C-1 CF N/A 120 System Refueling Water Duke Power Co. C-1 FW N/A 91 System .

Main Steam Duke Power Co. C-1SA N/A 114 Supply to Auxiliary Equipment System Main Steam Duke Power Co. C-1SM N/A 122 System Main Steam Vent Duke Power Co. C -1SV N/A 96 to Atmosphere System Containment Spray Duke Power Co. C-INS N/A 118 System Steam Generator Duke Power CO. C-1 BB N/A 111 Blowdown System .

Steam Generator Duke Power Co. C-1 BW N/A 104 Wet Lay Up Re-circulation System Diesel Generator Duke Power Co. C-1 FD N/A 100 Fuel Oil System Component Duke Power Co. C-1 KC N/A 129 Cooling System Residual Heat Duke Power Co. C-1 ND N/A 115 Removal System I I II Turbine Exhaust Duke Power Co. C-1TE N/A 113 System I I Refueling Outage EOC 15 (Outage 7) Page 2 of 5 Catawba Unit 1 Revision 0 Section 1 August 15, 2005

Identification Numbers (Continued)

I\> Manufacturer Manufacturer State or National Item or Installer or Installer Province Board Serial No. No. No.

Diesel Generator Duke Power Co. C-1VN N/A 98 Starting Air System Diesel Generator Duke Power Co. C-1 KD N/A 99 Cooling Water System Spent Fuel Cooling Duke Power Co. C-1 KF N/A 103 System l Diesel Generator Duke Power Co. C-1 LD N/A 105 Lube Oil System Nuclear Sampling Duke Power Co. C-1 NM N/A 124 System Containment Duke Power Co. C-1NW N/A 125 Penetration Valve Injection Water System Nuclear Service Duke Power Co. C-1 RN N/A 117 Water System Diesel Generator Duke Power Co. C-1VG N/A 95 Starting Air System Liquid Waste Duke Power Co. C-1WL N/A 119 Recycle System Control Area Chil- Duke Power Co. C-1YC N/A 106 led Water System Seal Water Pall Trinity Micro 1A 29652 N/A 15626 Injection Filter Corporation 1B 29653 N/A 15627 Volume Control Lamco 452 N/A 183 Tank Industries Inc.

Seal Water Heat Atlas Industrial 3620 N/A 2976 Exchanger Manufacturing Company Regenerative Heat Joseph Oat 2255-1A1 N/A 869 Exchanger Corporation Residual Heat Joseph Oat 1A 2267-3A N/A 846 Removal Heat Corporation 1B 2267-3B N/A 847 Exchanger Containment Spray Joseph Oat 1A 2636C N/A 3456 Heat Exchanger Corporation 1B 2620 N/A 3430 Refueling Outage EOC 15 (Outage 7) Page 3 of 5 Catawba Unit 1 Revision 0 Section 1 August 15, 2005

Identification Numbers (Continued)

Manufacturer State or National Item Manufacturer or Installer Province Board or Installer Serial No. No. No.

Excess Letdown Atlas Industrial 3196 N/A 2574 Heat Exchanger Manufacturing Company Residual Heat Ingersol - Rand 1A 077645 N/A 231 Removal Pump 1B 077646 N/A 232 Containment Spray Bingham - 1A 230340 N/A 213 Pump Willamette 1B 230341 N/A 214 Safety Injection Pacific Pumps 1A 49359 N/A 232 Pump 1B 49360 N/A 233 Centrifugal Pacific Pumps 1A 49778 N/A 256 Charging Pump 1B 49779 N/A 259 Seal Water Return Pall Trinity Micro 29006 N/A 15098 Filter Corporation 1.2 Personnel, Equipment and Material Certifications All personnel who performed or evaluated the results of inservice inspections during the time frame bracketed by the examination dates shown on the NIS-1 Form were certified in accordance with the requirements of the 1989 Edition of ASME Section Xl with no addenda including Appendix- VII for ultrasonic inspections. In addition, ultrasonic examiners were qualified in accordance with ASME Section Xl, Appendix Vill, and 1995 Edition with the 1996 Addenda through the Performance Demonstration Initiative (PDI).

The appropriate certification records for each inspector, calibration records for inspection equipment, and records of materials used (i.e. NDE consumables) are on file at Catawba Nuclear Station or copies may be obtained by contacting the Duke Energy Corporate Office in Charlotte, North Carolina The copies of the certification records for Washington Group and Atlantic Group inspectors can be obtained by contacting the Duke Energy Corporate Office in Charlotte, North Carolina.

The certification records for WesDyne inspectors and the calibration records of WesDyne inspection equipment are included in the WesDyne Catawba Nuclear Power Plant Unit 1 10 Year Reactor Vessel Inservice Examination Report, on file at The Duke Energy Corporate Office in Charlotte, North Carolina.

Refueling Outage EOC 15 (Outage 7) Page 4 of 5 Catawba Unit 1 Revision 0 Section 1 August 15, 2005

_) 1.3 Reference Documents The following reference documents apply to the inservice inspections performed during this report period. A copy may be obtained by contacting the ISI Plan Manager at Duke Energy's Corporate Office in Charlotte, North Carolina.

Duke Energy Corporation, Catawba Nuclear Station, Unit 1 Docket Number 50-413, Request for Relief Serial Number (to be filed later), Limited Weld Coverage during End-of-Cycle 15 Refueling Outage.

PIP #C-05-01591 Pipe Support damage on 6" 1A KC Miniflow Line Engineering Calculation #CNC-1201.01-00-0025 Evaluation of 1EOC15 ISI Indication in RV Nozzle 1D Hot Leg Weld PIP #G-05-00271 ASME Section XI Class 2 Examinations on Seal Water Return Filter 1.4 Augmented and Elective Examinations Augmented and elective examination information found within this Inservice Inspection Owners Summary Report is not required by the ASME Section XI Code or; therefore, it is exempt from ANII review, verification, and/or record certification.

1.5 Responsible Inspection Agency The Hartford Steam Boiler Inspection and Insurance Company of Connecticut are responsible for the third party inspections required by ASME Section Xl.

Authorized Nuclear Inservice Inspector(s)

Name: R. N. McGill Employer: The Hartford Steam Boiler Inspection & Insurance Company of Connecticut Business 200 Ashford Center North Address: Suite 205 Atlanta, GA 30338-4860 (800) 417-3721 www.hsbct.com Refueling Outage EOC 15 (Outage 7) Page 5 of 5 Catawba Unit 1 Revision 0 Section 1 August 15, 2005

KJ 2.0 Second Ten Year Interval Inspection Status The completion status of inspections required by the 1989 ASME Code Section Xl, no addenda; is summarized in this section. The requirements are listed by the ASME Section Xl Examination Category as defined in Table IWB-2500-1 for Class 1 Inspections, Table IWC-2500-1 for Class 2 Inspections, and IWF-2500-1 (Code Case N-491 applies) for Class 1, 2 and 3 Component Supports.

Augmented and Elective Inspections are also included.

Class 1 Inspections Examination Description Inspections Inspections Percentage Deferral Category Required Completed Completed Allowed' B-A Pressure Retaining Welds in 14 14 100% Yes Reactor Vessel B-B Pressure Retaining Welds in 5 5 100% No Vessels Other than Reactor Vessels B-D Full Penetration Welds of 36 36 100% Partial Nozzles in Vessels B-E Pressure Retaining Partial Penetration Welds in Reference Section 6.0 Of This Report Vessels B-F Pressure Retaining 38 38 100% No Dissimilar Metal Welds B-G-1 Pressure Retaining Bolting 244 244 100% Yes Greater than 2 Inch Diameter B-G-2 Pressure Retaining Bolting 2 20 20 100% No Inches and Less in Diameter B-H Integral Attachments for 5 5 100% No Vessels B-J Pressure Retaining Welds in 225 225 100% No Piping Refueling Outage EOC 15 (Outage 7) Page 1 of 4 Catawba Unit 1 Revision 0 Section 2 August 15, 2005

2- Class 1 Inspections (Continued)

Examination Description Inspections Inspections Percentage Deferral Category Required Completed Completed Allowed B-K-1 Integral Attachments for None N/A N/A N/A Piping, Pumps and Valves B-L-1 Pressure Retaining Welds in None N/A N/A N/A Pump Casings B-L-2 Pump Casings 0 0 0%* Yes B-M-1 Pressure Retaining Welds in 1 1 100% Yes Valve Bodies B-M-2 Valve Bodies 5 5 100% Yes B-N-1 Interior of Reactor Vessel 3 3 100% No B-N-2 Integrally Welded Core 2 2 100% Yes Support Structures and Interior Attachments to Reactor Vessels B-N-3 Removable Core Support 1 1 100% Yes K) Structures B-0 Pressure Retaining Welds in 3 3 100% Yes Control Rod Housings B-P All Pressure Retaining Components Reference Section 6.0 of this Report B-Q Steam Generator Tubing See note below F-A Class 1 Component 72 72 100% No Supports F01.010, F01.01 1, F01.012, F01.040 & F01.050 (Code Case N-491)

Note: Steam Generator Tubing is examined and documented by the Steam Generator Maintenance Group of the Nuclear Services Division as required by the Station Technical Specifications and Is not Included in this report.

1Deferral of Inspection to the end of the Interval, as allowed by ASME Section Xl Table IWB-2500-1.

These examination categories are exempt from percentage requirements per IWB-2412 (a),

Inspection Program B.

• No pumps were disassembled during the Second Inspection Interval.

Refueling Outage EOC 15 (Outage 7) Page 2 of 4 Catawba Unit 1 Revision 0 Section 2 August 15, 2005

KJ Class 2 Inspections Examination Description Inspections Inspections Percentage Category R Completed Completed C-A Pressure Retaining Welds 24 24 100%

in Pressure Vessels (See Note 1 below)

(See Note 3 on Page 4)

C-B Pressure Retaining Nozzle 9 7 77.78%

Welds in Vessels (See Note 2 below)

(See Note 3 on Page 4)

C-C Integral Attachments for 55 55 100%

Vessels, Piping, Pumps and Valves C-D Pressure Retaining Bolting None N/A N/A Greater than 2 in. In Diameter C-F-1 Pressure Retaining Welds 257 257 100%

in Austenitic Stainless Steel or High Alloy Piping K)p C-F-2 Pressure Retaining Welds 55 55 100%

in Carbon or Low Alloy Steel Piping C-G Pressure Retaining Welds 20 20 100%

in Pumps and Valves C-H All Pressure Retaining Components REFERENCE SECTION 6.0 OF THIS REPORT F-A Class 2 Component 270 270 100%

Supports F01.020, (See Note 3 F01.021, F01.022, on Page 4)

F01.040 & F01.050 (Code Case N-491)

Note 1: 12 Regenerative Heat Exchanger welds were not examined during the Second Inspection Interval. See Request for Relief f 03-001 and SER, dated February 17, 2005. A copy of Request for Relief #03-001, dated May 22,2003 and the Safety Evaluation Report (SER), dated February 17, 2005 are included in this section of the report.

Note 2: Weld ID. Numbers 1ANSHX-3-N1 and 1ANSHX-3-N2 were not examined during EOC15, due to the installation of a new 1A NS Heat Exchanger during EOC15.

Refueling Outage EOC 15 (Outage 7) Page 3 of 4 Catawba Unit 1 Revision 0 Section 2 August 15, 2005

K-

~ote 3: 100.% of the required examinations have been performed for the required inspections initially 1dentified in the-Ten Year Inservice Inspection Plan. One (1) late identified component (The Chemical and Volume Control System Seal Water Return Filter) was discovered not to have been included in the Non-Exempt Class 2 Examination Schedule. PIP # G-05-00271 was generated to document this omission and a corrective action assigned to include the required examinations. The Chemical and Volume Control System Seal Water Return Filter required inspections will be scheduled and performed in accordance with PIP #G-05-00271. A copy of the PIP is included in this section of the report.

Augmented/Elective Inspections Description Percentage Complete Postulated Pipe Failure - Main Steam System 100% of requirements for Outage 7/EOC1 5 NI Cold Leg Accumulator Welds subject to 100% of requirements for Outage 7/EOC1 5 Unanalyzed Thermal Transients VI Refueling Outage EOC 15 (Outage 7) Page 4 of 4 Catawba Unit 1 Revision 0 Section 2 August 15, 2005

1:

Duke GARY R. PETERSON

?E Powere Vice President Catawba Nuclear Station A Duke Energy Company Duke Power CNOI VP / 4800 Concord Rd.

York, SC 29745 803 831 4251 803 831 3221 fax grpeters @duke -energy. corn May 22, 2003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 Request for Relief Number 03-001 Relief from Volumetric Examination Requirements on Regenerative Heat Exchangers Pursuant to 10 CFR 50.55a(a)(3)(ii), please find attached Request for Relief 03-001. This request seeks relief from Section XI requirements of the ASME Boiler and Pressure Vessel Code, 1989 Edition with no Addenda.

Specifically, this request seeks relief from performing volumetric examinations on the Unit 1 and Unit 2 Regenerative Heat Exchangers as required by Table IWC-2500-1, Examination Category C-A, Pressure Retaining Welds in Pressure Vessels, because compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Catawba is requesting NRC review and approval of this request at your earliest convenience. The NRC has previously reviewed and approved a similar request for McGuire Nuclear Station, Units 1 and 2 on December 2, 1999 (TAC Numbers MA3756 and MA3757).

The attachment to this letter contains all technical information necessary in support of this request for relief.

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

If you have any questions concerning this material, please call L.J. Rudy at (803) 831-3084.

www.duke-energy.com

Document Control Desk Page 2

-= May 22, 2003 V X lyp s Gary R. Peterson LJR/s Attachment xc (with attachment):

L.A. Reyes, Regional Administrator U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 E.F. Guthrie, Senior Resident Inspector U.S. Nuclear Regulatory Commission Catawba Nuclear Station R.E. Martin, Senior Project Manager (addressee only)

U.S. Nuclear Regulatory Commission Mail Stop 08-H12 Washington, D.C. 20555-0001

Document Control Desk Page 3

.May 22, 2003 bxc (with attachment):

G.D. Gilbert L.J. Rudy RK?1Rhy~ne,,

A.J. Hogge, Jr.

K.E. Nicholson R.N. McGill RGC File Document Control File 801.01 ELL-ECO50 NCMPA-1 NCEMC PMPA SREC.

KJ

Request Relief C Page 1 of7 Proposed Rclief in Accordance with 10 CFR 50.55a (a)(3)(ii)

Inservice Inspection Hardship Duke Energy Corporation Catawba Nuclear Station - Unit 1 and 2 Second 10-Year Interval - Inservice Inspection Plan (CNS-1 began on June 29,1995 and CNS-2 began on August 19, 1996)

ASME Section XI Code - 1989 Edition with No Addenda 1 11.11.

I IV. V. VI. vn.

1.1). System / Code Requirement from Which Relief Is Basis for Reliet Alternate Justlflcatlon for the Implementntlon Schedule Number Component for Requested: 100I of the weld length Examinations or Granting of Relief Which Reliet Is Exam Category Tesdng Requested: Item No.

Area o( Weld to be Fig. No.

Examined I REUIHX-SlII . Regenerative Hetat Exam Calegqry C-A See Paragraph 'A" See Paragraph 'B" See Paragraph "C" See Paragraph "D" HI)M E~xchanger Head-to- Item No. C01.020007 (Unit I)

Shell Weld iwc-2500MI(a) . .

2REUIHX-S111- Regenerative Heat E.Exam Category C-A See Paragraph "A" See Paragraph "B" See Paragraph C" See Paragraph 'D" 111)1 1ichangef Head-to- -. Item No. CO1.020.004 (Unit 2)

Shell Weld

• IWC.2500-1(J)

IRE(iHX-SlIl- Regenerative Heat . Exam Categoty C-A See Paragraph A See Paragraph "B" See Paragraph" C" See Paragraph -D"

. I,- 4 . ! ". ItD2 Exchanger Head-to.- . Item No. COI.020.008 (Unit I)

.1%. .,.

Shell Weld IWC-250041(a)  ; .

. . w" . 2REGHX-Slll- Regenerative Heat Exam Category C-A E See Paragraph 'A" See Pantgraph 'B" See Paragraph "C" See Paragraph "D1-HD2 Exchanger Ilead-to-  : . Item No. C01.020.005 (Unit 2)

Shell Weld IWC-25004t(a)

I REGHX-SH2- Regenerative Heat Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph "C" See Panrgraph -D"

1 HDI Exchanger Head-to . Item No. CO1.020.009 (Unit 1)

Shell Weld  : WC-250041(a) - .

2REGHX-SH2- Regenerative Heat Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph 'C" See Paragraph 'D-HDI Exchanger Head-to Item No. CO.020.006 (Unit 2)

Shell Weld IWC-2500-1(a) .

I REGHX-S112- Regenerative Heat Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph "C" See Panrgraph *D 1ID2 Exchanger Hed-to- Item No. CO1.020.010 (Unit I)

Shell Weld - wc-2500-I(2)

(C C Request Relief 0 Page 21JL 1 1.1). System / Code Requirement from Which Relief is Basis for Reliet Alternate Justifleatlon for the Implementation Schedule Number Component for Requested: 100% of the weld length Examinations or Granting of Relief Which Relief Is Exam Category . Testing Requested: Item No.

Area or Wcid to be Fig. No.

Examined 2REGHX-S112. Regenerative Heat Exam Category C.A See Paragraph "A" See Paragraph -B" See Paragraph "C' See Paragraph 'D" 111)2 Efxchanger lIcad-to- I.: Item No. COI.020.007 (Unit 2)

Shell Weld IWC-2500-1(a)

I Re(.i;IX Si 13. Regenerative Heat Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph "C" See Paragraph "D" 111)1 I!xchanger Ilead-to- Item No. COI.020.011 (Unit I)

Shell Weld IWC-2500-1(a) .

2REGHX-Si13- Regenerative Heat Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph 'C" See Paragraph 'D" HDI Exchanger Head-to- Item No. C01.020.008 (Unit 2)

Shell Weld* IWC-2500.1(a)

I REGHX-SH3- Regenerative Heat Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph 'C" See Paragraph -D" HD2 Exchanger Head-to- Item No. C01.020.012 (Unit I)

Shell Weld IWC-2500-I(s) .

2REGHX-SH3- Regenerative Heat Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph 'C' See Paragraph 'D" HD2 Exchanger Head-to- i.. Item No. COI.020.009 (Unit 2)

Shell Weld IWC-2500-1(n)

I REGHX-SHI - Regenerative Heat . Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph IC" See Paragraph D" TS . Exchanger Item No. C01.030.002 (Unit l)

Tubeshect-to-Shell 4 IWC-2500-2 W eld :_._.:_._._._.-

2REGHX-SIII- Regenerative Heat Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph 'C See Paragraph ID" TS Exchanger Item No. COI.030.002 (Unit 2)

Tubeshect'to-Shel IWC-2500-2 .

I REG;HXSI12. Regenerative lHeat. - Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph ' See Paragraph -D" T1S Exchanger r Item No. C01.030.003 (Unit I)

Tubesheet-to-Shell IWC-2500-2

_._._*_.Weld 2RC(;HX-SII2- Regenerative Heat Exam Category C-A See Paragraph A" See Paragraph 'B" See Paragraph'C See Paragraph ID" tS Exchanger Item No. C01.030.003 (Unit 2)

Tubeshect-io-Shell IWC-2500-2

____________ W eld :_::  ; .. ___._.

IREGIIX-Si13- Regenerative Heat Exam Category C-A See Paragraph 'A' See Paragraph 'B" See Paragraph 'C" See Paragraph I'D" TS Exchanger I.tem No. COL.030.004 (Unit 1)

TubeshectloShell - *i - IWC-2500-2 W eld __ ___._-_:__ ___;__ _.

2REGHX.S113- Regenerative Heat Exam Category C-A See Paragraph "A" See Paragraph 'B" See Paragraph 'C" See Paragraph 'D" tS Exchanger .f Item No. CO1.030.004 (Unit 2)

Tubesheet-to-Sheli ' IWC-2500-2

__ Weld

• __

( ( Request RelicI 0c Page 3 of 7 I.D. System / Code Requirement from Which Relief Is Basis tor Reliet Alternate Justification for the Implementation Schedule Number Component for Requested: 100% ot the weld length ExamInations or Granting ot Relet Which Relief Is Exam Category Testing Requemted: Item No.

Area or Weld to be Fig. No.

Examined I REGIIX-tS- Regencrative Heat Exam Category C-A See Paragraph "A See Paragraph B" See Paragraph "C" See Paragraph "D-Sill Exchanger Item No. COI.030.00S (Unit 1)

Tuheshect-tnShell IWC-2500-2 Weld 2RE(;HIX- T.. Regenerative Heat Exam Category C-A See Paragraph A See Paragraph B" See Paragraph "C" See Paragraph -D" Sill Exchanger Item No. C01.030.005 (Unit 2)

Tubeshect-to.Shell IWC-2500-2 Weld .

I REGIIX TS. Regenerative Heat Exam Category C-A See Paragraph IAN See Paragraph "B" See Paragraph "C" See Paragraph ID" S112 Exchanger Item No. COI.030.006 (Unit I)

Tubesheet-to-Shell

• IWC-2500-2 Weld 2REGHX TS- Regenerative Heat Exam Category C-A See Paragraph "A' See Paragraph "B" See Paragraph "C" See Paragraph 'D" S112 Exchanger Item No. C0I.030.006 (Unit 2)

Tubeshect-to-Shell IWC-2500-2 Weld I REGHX- TS. Regenerative Heat Exam Category C-A See Paragraph "A" See Paragraph "B" See Paragraph IC" See Paragraph "D" SH3 Exchanger Item No. C01.030.007 (Unit I)

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i 2RE(;HX- TS- Regenerative Heat Exam Category C.A See Paragraph "A" See Paragraph "B" See Paragraph "C" See Paragraph "D" SH3 Exchanger Item No. COI.030.007 (Unit 2)

Tubesheet-to-Shell IWC-2500-2 Weld .

Request Relief 03-001 Page 4 of 7 IV. Basis for Relief Paragraph A:

Due to high radiation dose rates in the area of the Regenerative Heat Exchanger, it is station management's request that these welds not be examined. To complete the examination(s) on the Regenerative Heat Exchanger, an estimated 9,975 mrem of exposure would be received for each unit.

Listed below is a break down of the examination tasks and their respective estimates as developed by the Catawba ALARA Staff and Inservice Inspection Coordinator. The estimates assume'dose rates atfthe time of the examination will be comparable to dose rates measured during previous outages. -.

The average radiation level in the vicinity of the regenerative heat exchanger is 700 mrem per hour. To achieve this dose rate, the letdown line must be isolated prior to peroxide injection (induced crud burst). Also a successful flush of the letdown line and Regenerative Heat Exchanger using water from the Reactor Make-up Water Storage Tank would be required. Both of these initiatives are routinely performed each &itage.

• --I- **

-*4;-;w:'...  ; .. e Activity Man-Hours Average Dose Rate Activity

' .. Exposure Estimate (mrem)

Erect/ Remove Scaffold 3 700 . 2,0oo Remove / Restore Insulation 2.5 700 1,750 Weld Prep (assumes no grinding) 2.5 700 1,750 NDE 6 700 iaoo RP Support 0.25 700 175 Estimated Exposure Total - '  :,9,975 The use of temporary shielding in the area of the heat exchanger has been considered. however; jreliminary evaluations using typical methods and materials suggest that the amount of exposure incurred during-installation and removal would be equal to or greater than the amount of exposure saved. ;

In addition, structural steel supporting the heat exchangers would hae to be remo to facn ." ;l.e'; :

examination process on 6 of the 12 welds or perform a limited coverage examination' The stfiz shown above does not include removal and replacement of aniy structural stel. - :: -

Given there is no alternative volumetric or surface exam available due to similar radiation concerns, in lieu of implementing the requirements of Examination Category C-A. it is proposed that the Pressure Testing currently being performed under Examination Category C-H. "All Pressure Retaining Components" (Visual Examination. VT-2) be considered as a basis for approval of this request.

V. Alternate Examinations or Testing Paragraph B:

None

Request Relief 03-001 Page 5 of 7 VI. Justification for the Granting or Relief Paragraph C:

Approval of the alternative testing provided by this relief request would significantly reduce unnecessary radiological exposure to plant personnel when complying with the volumetric examination requirements, without decreasing the confidence level in the operability of the Regenerative Heat Exchanger.

The alternative testing would not result in a reduction of the level of q ality and safety for the following reasons:

1. The Regenerative Heat Exchanger and associated system piping, having been designed and constructed to meet the Class 2 requirements of the 1974 edition of ASME Section m, have a low probability of failure throughout their design life. It was fabricated frir austenitic stainless steel (Type 304 1 316). This material is resistant to base and weld eal degradation of the heat exchanger in the primary reactor coolant environmen.&.Th 12 welds fcireachAunit of Catawba arc not dissimilar metal welds and thus are not subjected to pnmnary water stress corrosion crackingassociated with other materials. Oxygen levels in the primary system are strictly limited, thereby greatly reducing the susceptibility to intergrannular stress corrosion cracking. 'Furthermore, ther&has been no industry operating experience that has identified these stainless materials as susceptible to significant corrosion in the primary water environment.

2. Thermal fatigue has been considered in the design of the heat exchanger. No thermal cycling, stratification, or striping conditions have everGn identified to Invlidaitthqualification of the heat exchanger. While flow induced vibration of the connected ltidown piping h'as been observed in the past, the structural integrity of the twelve shell to head and tubesheet welds is not affected.

Vibrational forces originating at the orifices are attenuated at the HX by the configuration and distance between the orifices and HX. Furthermore, past modifications have minimized the vibration levels in the letdown piping. Based on industry operating and plant specific experience, there are no known degradation mechanisms identified for these welds.

3. Catawba Technical Specifications place conservative limits on the amount of reactor c6olainei-tikage allowed during system operation/'The reactor coolant leak dete'tions'ysterm is in piace to detect any variation in the reactor coolant inventory. including the water present in boththe tube and shell side of the Regeuierative Heat Exchanger, as well as its associated piping. Any weld failure v-ould be detected by the reactor coolant leak detection system, and procedures and automatic system actions are in place to ensure that the heat exchanger would be isolated. I; '-- 4jCg .t. T

4. 'RcgencrativeHeat Exchanger is'isolablcfrom the r from't'control foom and/or receives automatic closure signals . -eshd sidel of the heat cxchanger rectr*

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is isolable from thef torcoolant system bytwo fail clos erd gate valves in seris.

These valves are provided a safety signal to automatically close on a Pressurizer Low-Level setpoint, which would be present with a significant leak from a Regenerative HX Shell-to-Head or Shell-to-Tubesheet weld failure. The tube side is isolable from the high pressure charging system by two motor operated gate valves in series, which are controlled from the Control Room and/or automatically close on a Safety Injection Signal (SS). which would be present with a significant IX weld leak. Regenerative Heat Exchanger is located inside the Containment Buildinrg. which is' designed to contain any leakage.

5. Visual examinations associated with Pressure Testing of the Regenerative Heat Exchangers during the latest refueling outages for Unit I (EOC 12) and Unit 2 (EOCl I ) did not identify any evidence of weld leakage. - ; - - -

Request Relief 03-001 Page 6 of 7 VII. Implementation Schedule Paragraph D:

During the second 10-year inspection interval, the Regenerative Heat Exchanger Pressure Testing examinations are scheduled and will be performed in accordance with the requirements of Table IWC-2500-1, Examination Category C-H, 'All Pressure Retaining Components". The Pressure Testing examination schedules are shown below.

Catawba Unit I Test Zone Inspection Date End of Cycle Period Leak Test 1NV-001I-B 01103/98 10 I' Period LeakTest 1NV-O01L-B 11/19/00 12 ':. 2aPeriod HydroTest 1NV-OO1H-B ,ToBe Done 14 and 15 -d 3d Period Catawba Unit 2 Test Zone Inspection Date End of Cycle Period Leak Test 2NV-OOIL-B 10/1898 9 -'IPeriod Leak Test 2NV-OOlL-B 10/20/01 11 2 Period Hydro Test 2NV-OOIH-B To Be Done 13 and 14 3V Period VIII. Other Information Catawba Unit 1 Examination Category C-A There are twenty-six (26) weldsthat make up th total population fdr this examination category, all*of which are scheduled for examination during the current 10-year inspection interval. WVith the'elimination of -

twelve (12) Regenerative Heat Exchanger weld examinations sought by this relief reiquest. the Table IWC-2412-1 code requirement to complete 100% of the total number of examinations within a category by the end of an interval will not be met. ,. ,.

Excluding the twelve (12) Regenerative Heat Exchanger welds, the remaining fourteen (14) I. weld examinations will b e'rformed in this category. 'Basedon theoriginag categor otal ppulation, the 'end o interval completion percentage will be (26-12) /26 =14 /26 _ 53.85%, not,100 % as required inTable-i:

IWC-2412-1.

Relief is requested from the above requirements of Paragraph IWC-2412 and Table 1PVC-2412-1.

Catawba Unit 2 Examination Category C-A There arc twenty-nine (29) welds that make up the total population for this examination category, all of which arc scheduled for examination during the current 10-year inspection interval. With the elimination of twelve (12) Regenerative Heat Exchanger weld examinations sought by this relief request. the Table IWC-2412- Icode requirement to complete 100% of the total numberof examinations uithin a category by the end of an interval will not be met.

Excluding the twelve (12) Regenerative Heat Exchanger welds. the remaining seventeen (17)j weld

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• Request Relief 03-001 Pagc7of7 examinations will be performed in this category. Based on the original category total population, the end of K> interval completion percentage will be (29-12) / 29 =17 1 29 = 58.62%, not 100 % as required in Table IWC-2412-1.

Relief is requested from the above requirements of Paragraph rWC-2412 and Table IWC-2412-1.

The following individuals contributed to the development of this relief request.

Roy Riddle (ALARA Specialist, Catawba) developed dose estimates for Regienrative Heat Exchanger.

Hugh Mason and Bill Callaway (Plant Engineering, Catawba) contributed justification for granting of relief.

Andy Hogge and Jimmy Cherry (Inservice Inspection Plan Management, GO) developed the relief request and addressed code requirements.

Attachments:

1. Sub-Assembly and Details Drawing of Regenerative Heat Exchanger (Catawba Unit 1)

2. Sub-Assembly and Details Drawing of Regenerative Heat Exchanger (Catawba Unit 2).

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UNITED STATES NUCLEAR REGULATORY COMMISSION 0 BUS ° WASHINGTON, D.C. 20555-0001 ' _  ::u February 17, 2005 1 -

Mr. D. M. Jamil _ I-Vice President REGUI.At' CC.

Catawba Nuclear Station Duke Energy Corporation 4800 Concord Road York, SC 29745

SUBJECT:

CATAWBA NUCLEAR STATION, UNITS 1 AND 2 RE: REQUEST FOR RELIEF 03-001, SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN (TAC NOS. MB9141 AND MB9142)

Dear Mr. Jamil:

By letters dated May 22, 2003, and September 8, 2004, Duke Energy Corporation, the licensee for Catawba Nuclear Station (Catawba), Units 1 and 2, submitted a request for relief, Relief Request No.03-001, from the requirements of the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section XI, 1989 Edition with no addenda. Specifically, the licensee requested relief associated with the Code-required 100 percent volumetric examination of the regenerative heat exchanger head-to-shell and tubesheet-to-shell welds. The licensee's proposed alternative is to perform visual VT-2 examinations during Code-required system leakage tests in lieu of the volumetric examinations for the second 10-year inservice inspection (ISI) intervals at Catawba, Units 1 and 2.

The Nuclear Regulatory Commission (NRC) staff, with technical assistance from its contractor, the Pacific Northwest National Laboratory, has reviewed the information provided for this relief request. The enclosed Safety Evaluation contains the NRC staff's evaluation and conclusions.

Based on the information provided in the relief request, the NRC staff concludes -that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, the proposed alternative is authorized pursuant to Title 10 of the Code of Federal Regulations, Section 50.55a(a)(3)(ii) for the second ISI intervals at Catawba, Units 1 and 2.

Sincerely,

\ Jo n A. Nakoski, Chief, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-413 and 50-414

Enclosure:

As stated cc w/enc: See next page

Catawba Nuclear Station, Units 1 & 2 Page 1 of 2 ANAL cc:

Mr. Lee Keller, Manager North Carolina Electric Membership Corp.

Regulatory Compliance P.O. Box 27306 Duke Energy Corporation Raleigh, North Carolina 27611 4800 Concord Road York, South Carolina 29745 Senior Resident Inspector U.S. Nuclear Regulatory Commission Ms. Lisa F. Vaughn 4830 Concord Road Duke Energy Corporation York, South Carolina 29745 Mail Code - PB05E 422 South Church Street Mr. Henry Porter, Assistant Director P.O. Box 1244 Division of Waste Management Charlotte, North Carolina 28201-1244 Bureau of Land and Waste Management Dept. of Health and Environmental Control Ms. Anne Cottingham, Esquire 2600 Bull Street Winston and Strawn Columbia, South Carolina 29201-1708 1400 L Street, NW Washington, DC 20005 Mr. R.L. Gill, Jr., Manager Nuclear Regulatory Issues North Carolina Municipal Power and Industry Affairs Agency Number 1 Duke Energy Corporation 1427 Meadowwood Boulevard 526 South Church Street P.O. Box 29513 Mail Stop EC05P Raleigh, North Carolina 27626 Charlotte, North Carolina 28202 County Manager of York County Saluda River Electric York County Courthouse P.O. Box 929 York, South Carolina 29745 Laurens, South Carolina 29360 Piedmont Municipal Power Agency Mr. Peter R. Harden, IV, Vice President 121 Village Drive Customer Relations and Sales Greer, South Carolina 29651 Westinghouse Electric Company 6000 Fairview Road Ms. Karen E. Long 12th Floor Assistant Attorney General Charlotte, North Carolina 28210 North Carolina Department of Justice P.O. Box 629 Ms. Mary Olson Raleigh, North Carolina 27602 Director of the Southeast Office Nuclear Information and Resource Service NCEM REP Program Manager 729 Haywood Road, 1-A 4713 Mail Service Center P.O. Box 7586 Raleigh, North Carolina 27699-4713 Asheville, North Carolina 28802

." I Catawba Nuclear Station, Units 1 & 2 Page 2 of 2 cc:

Mr. T. Richard Puryear Owners Group (NCEMC)

Duke Energy Corporation 4800 Concord Road York, South Carolina 29745 Mr. Richard M. Fry, Director Division of Radiation Protection NC Dept. of Environment, Health, and Natural Resources 3825 Barrett Drive Raleigh, North Carolina 27609-7721 Mr. Henry Barron Group Vice President, Nuclear Generation and Chief Nuclear Officer P.O. Box 1006-EC07H Charlotte, NC 28201 -1006 Diane Curran Harmon, Curran, Spielbergy &

Eisenberg, LLP 1726 M Street, NW Suite 600 Washington, DC 20036

. ,UNITED STATES A NUCLEAR REGULATORY COMMISSION.

WASHINGTON, D.C. 20555-0001 h~ .

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF NUMBER 03-001 CATAWBA NUCLEAR STATION, UNITS I AND 2 DUKE ENERGY CORPORATiON DOCKET NOS. 50-413 AND 50-414

1.0 INTRODUCTION

The Nuclear Regulatory Commission (NRC) staff, with technical assistance from its contractor, the Pacific Northwest National Laboratory (PNNL), has reviewed and evaluated the information provided by Duke Energy Corporation (Duke, the licensee) in its letter dated May 22, 2003, that proposed its Second 10-Year Interval Inservice (ISI) Inspection Program Plan Request for Relief No.03-001 for Catawba Nuclear Station (Catawba), Units 1 and 2. The licensee provided additional information by letter dated September 8,2004.

2.0 REGULATORY EVALUATION

ISI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code Class 1, 2*, and 3 components is performed in accordance with Section Xl of the ASME Code and applicable addenda as required by Title 10 of the Code of FederalRegulations (10 CFR) Section 50.55a(g), except where specific relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). 10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if: (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code, Section Xl, "Rules for Inservice Inspection (ISI) of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable Code of record for the second Enclosure

10-year ISI for Catawba, Units 1 and 2 is the 1989 Edition of the ASME B&PV Code, Section Xl. The Catawba, Unit 1 second 10-year ISI interval began dKJune 29, 1995, and Catawba, Unit 2 second 10-year ISI interval began on August 19, 1996.

3.0 TECHNICAL EVALUATION

The ASME Code, Examination Category C-A, Items C1.20 and C1.30, requires essentially 100 percent volumetric examination, as defined by Figures IWC-2500-1 and -2, of the length of Class 2 head circumferential and tubesheet-to-shell welds for the regenerative heat exchanger.

The licensee proposed to eliminate the Code-required 100 percent volumetric examination of the Catawba, Units 1 and 2 regenerative heat exchanger head-to-shell and tubesheet-to-shell welds because of the high radiation exposure that the examiners receive. An estimated 9.975 man-rem of exposure would be received for each unit. Furthermore, Duke proposed that the pressure testing currently being performed under Examination category C-H, "AII Pressure Retaining Components" Visual Examination, VT-2 and monitoring of these vessels for leakage during normal plant operations be considered as a basis for approval of its request for relief.

The regenerative heat exchanger and associated system piping, designed and constructed to meet the Class 2 requirements of the 1974 edition of ASME Section 1II,have a low probability of failure throughout their design life. The regenerative heat exchanger was fabricated from austenitic stainless steel (Type 304/316) and is resistant to base and weld metal degradation in the primary reactor coolant environment. The licensee strictly limits oxygen levels and contaminants in the primary system, thereby greatly reducing the susceptibility to stress corrosion cracking. Industry operating experience does not indicate that these stainless materials are susceptible to significant corrosion in the primary water environment.

The Catawba Technical Specifications place limits on the amount of reactor coolant leakage allowed during system operation, and Catawba has a system in place to detect any variation in the reactor coolant inventory, including the water present in both the tube and shell side of the regenerative heat exchanger, as well as its associated piping. Therefore, any weld failure would be detected by the reactor coolant leak detection system, and procedures and automatic system actions are in place to ensure that the heat exchanger would be isolated. The regenerative heat exchanger is isolable from the reactor coolant system by valves operated from the control room and/or automatic closure signals. The licensee performs the Code-required system leakage test and the VT-2 visual examination each outage. During the latest refueling outages for Unit 1 (EOC12) and Unit 2 (EOC11), the VT-2 visual examinations did not reveal any evidence of leakage.

The NRC staff determined that, based on its review of the licensee's submittal, to require the licensee to perform the ASME Code-required examinations on the subject components of the regenerative heat exchanger would be a hardship without a compensating increase in quality and safety. Furthermore, the NRC staff determined that the licensee's proposed alternative provides reasonable assurance of the continued structural integrity of the regenerative heat exchangers for both Catawba, Units 1 and 2.

4.0 CONCLUSION

The Catawba, Units 1 and 2 Request for Relief No.03-001 from the Code requirements has been reviewed by the NRC staff, with the assistance of its contractor, PNNL.

The attached Technical Letter Report provides PNNL's evaluation of these requests for relief.

The NRC staff has reviewed the TLR and adopts the evaluations and recommendations for authorizing the licensee's request for relief.

For Request for Relief 03-001, the NRC staff has concluded that compliance with the Code requirements would result in a hardship or unusual difficulty without a compensating increase in quality and safety. The alternative proposed by the licensee provides reasonable assurance of the continued leak tightness or structural integrity of the subject component. Therefore, Request for Relief 03-001, is authorized pursuant to 10 CFR 50.55a(a)(3)(ii) for the second 10-year ISI interval at Catawba, Units 1 and 2. All other requirements of the ASME Code, Section Xl for which relief has not been specifically requested remain applicable, including third party review by the Authorized Nuclear Inservice Inspector.

Attachment:

As stated Principal Contributor: T. McLellan

~KJ Date: February 17, 2005

Iv- .UNITED STATES NUCLEAR REGULATORY COMMISSION

,3WASHINGTON, D.C. 20555-0001 TECHNICAL LETTER REPORT i

ON THE SECOND 10-YEAR INTERVAL INSERVICE INSPECTION REQUEST FOR RELIEF 03-001 DUKE ENERGY CORPORATION CATAWBA NUCLEAR STATION. UNITS 1 AND 2 DOCKET NUMBERS: 50-413 AND 50-414

1.0 INTRODUCTION

By letter dated May 22, 2003, the licensee, Duke Energy Corporation, submitted Request for Relief 03-001 from requirements of the American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of NuclearPower Plant Components. In response to an NRC Request for Additional Information, the licensee provided clarification and component drawings in a letter dated September 8, 2004. This request was submitted as part of the inservice inspection (ISI) program for the second 10-year inservice inspection (ISI) intervals at Catawba Nuclear Station, Units 1 and 2 (Catawba 1-2).

The Pacific Northwest National Laboratory (PNNL) has evaluated the subject request for relief in the following section.

2.0 REGULATORY REQUIREMENTS Inservice inspection of the ASME Code Class 1, 2, and 3 components is to be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (B&PV Code), and applicable addenda, as required by Title 10 of the Code of Federal Regulations (10 CFR) Part 50.55a(g), except where specific relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). The regulation at 10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the U.S. Nuclear Regulatory Commission (NRC), if the licensee demonstrates that (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports).shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection (ISI) of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section Xl of the ASME Code, which was incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The code of record for Attachment

June 29, 1995 (Unit 1) and August 19, 1996 (Unit 2), is the 1989 Edition of Section XI of the ASME Boiler and Pressure Vessel Code.

3.0 EVALUATION The information provided by Duke Energy Corporation in support of the request for relief from Code requirements has been evaluated and the basis for disposition is documented below.

3.1 Request for Relief 03-001. Examination Category C-A. Items C1.20 and C1.30.

Pressure Retaining Welds in Pressure Vessels. Regenerative Heat Exchanger Code Requirement: Examination Category C-A, Items C1.20 and C1.30, require essentially 100% volumetric examination, as defined by Figures IWC-2500-1 and -2, of the length of Class 2 head circumferential and tubesheet-to-shell welds. "Essentially 100%," as clarified by ASME Code Case N-460, is greater than 90% coverage of the examination volume, or surface area, as applicable.

Licensee's Proposed Alternative to Code: Based on the hardship of examining these welds, the licensee has proposed an alternative, in accordance with 10CFR50.55a(a)(3)(ii), to the Code-required 100% volumetric examination of Catawba 1-2 regenerative heat exchanger head-to-shell and tubesheet-to-shell welds. The licensee's alternative is to perform visual VT-2 examinations during Code-required system leakage tests in lieu of the volumetric examinations.

Licensee's Basis for Alternative (as stated):

Due to high radiation dose rates in the area of the regenerative heat exchanger, it is station managements' request that these welds not be examined. To complete the examinations on the regenerative heat exchanger, an estimated 9.975 man-rem of exposure would be received for each unit.

Listed below is a break-down of the examination tasks and their respective estimates (of exposure] as developed by the Catawba ALARA Staff and Inservice Inspection Coordinator. The estimates assume dose rates at the time of examination will be comparable to dose rates measured during previous outages.

The average radiation level in the vicinity of the regenerative heat exchanger is 700 millirem per hour. To achieve this dose rate, the letdown line must be isolated prior to peroxide injection (induced crud burst). Also, a successful flush of the letdown line and regenerative heat exchanger using water from the reactor make-up water storage tank would be required. Both of these initiatives are routinely performed each outage.

Activity Man- Average Activity Exposure Hours Dose Rate Estimate (mrem)

Erect/Remove scaffold .700 2100 Remove/Restore Insulation 2.5 700 1750 Weld Prep (assumes no 2.5 700 1750 grinding)

NDE 6 700 4200 RP Support 0.25 700 175 Estimated Total Exposure 9975 The use of temporary shielding in the area of the heat exchanger has been considered.

However, preliminary evaluations using typical methods and materials suggest that the amount of exposure incurred during installation and removal would be equal to or greater than the amount of exposure saved.

In addition, structural steel supporting the heat exchangers would have to be removed to facilitate the examination process on 6 of the 12 welds, or perform a limited coverage examination. The estimate shown above does not include removal and replacement of any structural steel.

Given there is no alternative volumetric or surface exam available due to similar radiation concerns, in lieu of implementing the requirements of Examination Category C-A, it is proposed that the pressure testing currently being performed under Examination category C-H, 'All Pressure Retaining Components" (Visual Examination, VT-2) be considered as a basis for approval of this request.

Approval of the alternative testing provided by this relief request would significantly reduce unnecessary radiological exposure to plant personnel when complying with the volumetric examination requirements, without decreasing the confidence level in the operability of the Regenerative Heat Exchanger.

The alternative testing would not result in a reduction of the level of quality and safety for the following reasons:

1. The Regenerative Heat Exchanger and associated system piping, having been designed and constructed to meet the Class 2 requirements of the 1974 edition of ASME Section Ill, have a low probability of failure throughout their design life. It was fabricated from austenitic stainless steel (Type 304/316). This material is resistant to base and weld metal degradation of the heat exchanger in the primary reactor coolant environment. The 12 welds for each unit of Catawba are not dissimilar metal welds and thus are not subjected to primary water stress corrosion cracking associated with other materials. Oxygen levels in the primary system are strictly limited, thereby greatly reducing the susceptibility to intergranular stress corrosion cracking. Furthermore, there has been no industry operating eyperience that has identified these stainless materials as susceptible to significant corrosion in the primary water environment.

2. Thermal fatigue has been consid&ed in the dersign of the heat exchanger. No thermal cycling, stratification, or striping conditions have ever been identified to invalidate the qualification of the heat exchanger. While flow induced vibration of the connected letdown piping has been observed in the past, the structural integrity of the twelve shell to head and tubesheet welds is not affected. Vibrational forces originating at the orifices are attenuated at the HX by the configuration and distance between the orifices and HX. Furthermore, past modifications have minimized the vibration levels in the letdown piping. Based on industry operating and plant specific experience, there are no known degradation mechanisms identified for these welds.

3. Catawba Technical Specifications place conservative limits on the amount of reactor coolant leakage allowed during system operation. The reactor coolant leak detection system is in place to detect any variation in the reactor coolant inventory, including the water present in both the tube and shell side of the Regenerative Heat Exchanger, as well as its associated piping. Any weld failure would be detected by the reactor coolant leak detection system, and procedures and automatic system actions are in place to ensure that the heat exchanger would be isolated.

4. Regenerative Heat Exchanger is isolable from the reactor coolant system by valves either operated from the control room and/or automatic closure signals. The shell side of the heat exchanger is isolable from the reactor coolant system by two fail closed, air operated gate valves in series. These valves are provided a safety signal to automatically close on a Pressurizer Low-Level setpoint, which would be present with a significant leak from a Regenerative HX Shell-to-Head or Shell-to-Tubesheet weld failure. The tube side is isolable from the high pressure charging system by two motor operated gate valves in series, which are controlled from the Control Room and/or automatically close on a Safety Injection Signal (SS), which would be present with a significant HX weld leak. Regenerative Heat Exchanger is located inside the Containment Building, which is designed to contain any leakage.

5. Visual examinations associated with Pressure Testing of the Regenerative Heat Exchangers during the latest refueling outages for Unit 1 (EOC12) and Unit 2 (EOC1 1) did not identify any evidence of weld leakage.

Response to Request for Additional Information (as stated):

ASME Section Xl, Paragraph IWC-1222(b), applies to component connections nominal pipe size four inches and smaller (including nozzles, socket fittings, and other connections) in vessels, piping, pumps, valves, and other components. Chemical and Volume Control System piping welded to the Regenerative Heat Exchanger Nozzles is three inches in diameter. Therefore, these nozzle-to-shell welds are exempt from volumetric and/or surface examination requirements per IWC-1222.

All Category C-A welds identified in Request for Relief 03-001 were volumetrically inspected by radiography during vessel fabrication. A weld repair Was performed by the vessel manufacturer on the Catawba Unit 1 vessel, shell number 2, girth weld number 2.

The repair was limited to one area contained within one four-inch RT film interval (4-5).

In addition, a weld repair was performed on the Catawba Unit 2 vessel, shell number 3, girth weld number 1. The repair *ftislimited to.one area contained within two four-inch film intervals (4-5 and 5-6). The weld repair areas were re-examined by radiography and found to be acceptable. The remaining welds on the Catawba Unit 1 and 2 vessels were found to be radiographically acceptable during the fabrication process without performing weld repair activities.

All other Category C-A welds on Class 2 vessels have been reviewed and confirmed to be examined in accordance with Code requirements.

The regenerative heat exchanger is isolable from the Reactor Coolant System by valves either operated from the control room or by valves that receive automatic closure signals. The shell side of the heat exchanger is isolable from the Reactor Coolant System by two fail-closed, air operated gate valves in series. These valves are provided a safety signal to automatically close on a pressurizer low level, which would be present with a significant leak from a regenerative heat exchanger shell-to-head or shell-to-tubesheet weld failure. The tube side is isolable from the high pressure charging system by two motor operated gate valves in series, which are controlled from the control room and/or which automatically close on a safety injection signal. A safety injection signal would occur with a significant heat exchanger weld leak.

Evaluation: The Code requires that essentially 100% of the length of all Class 2 vessel shell-to-head and tubesheet-to-shell welds be volumetrically examined once during each ISI interval. This includes examination of 24 welds on the regenerative heat exchangers (RHXs) at Catawba 1-2 (12 welds per heat exchanger at each unit). However, because of the manner in which these heat exchangers operate, particulates from the reactor coolant system accumulate in low-flow regions of the vessels during normal service conditions. This causes the vessels and surrounding area to become highly radioactive.

To require the licensee to examine the subject heat exchanger welds would present a significant hardship due to excessive personnel radiation exposure.

The RHXs at Catawba 1-2 are Class 2 and consist of a shell and tube design with three separate vessels stacked vertically and piped in series. The licensee considers all three vessels to be one heat exchanger. Each component possesses a head-to-shell and shell-to-tubesheet weld on either end, for a total of 12 welds per heat exchanger. The RHX is part of the plant chemical and volume control system, and is designed to recover heat from the letdown stream by reheating the charging stream during normal operation.

The letdown stream flows through the shell of the regenerative heat exchanger and the charging stream flows through the tubes. The unit is made of austenitic stainless steel, and is of all-welded construction. Other than the subject shell-to-head and tubesheet-to-shell welds, no other welds are required by Code to be examined by volumetric or surface methods. This is because Class 2 inlet and outlet nozzle welds on the RHXs are less than NPS 4-inches in diameter, which are exempt from all examinations except visual VT-2 during pressure tests. The licensee estimates that approximately 10 man-Rem of radiation exposure will be incurred during examination of these welds on each heat exchanger at Catawba 1-2. This is due to activities associated with the examination such as erection and removal of scaffolding, insulation removal and replacement, surface preparation of the welds, and the actual examination process.

Several potential forms of egradation have been considered for these welds, however, no aggressive mechanisms can be identified that may challenge the structural integrity of the RHXs, based on materials of construction and operating environments. It is concluded that, once the subject shell and head welds have been thoroughly examined during preservice or prior inservice inspections, failure probabilities are very low, and that exposure of plant personnel to the high levels of radiation to support continued volumetric examinations is unwarranted.

In addition, the RHXs can be quickly isolated from the primary coolant system by valves if leakage is detected. Furthermore, in a brief review of international databases' and readily available literature to-date, no service-induced pressure boundary failures have been experienced for shell and/or head welds on this type of RHX. Therefore, Duke's proposal to continue to perform visual VT-2 examinations during system leakage tests, and to monitor these vessels for leakage during normal plant operations, provides reasonable assurance that the RHXs will continue to function as designed at Catawba 1-2.

To require the Code volumetric examinations of the subject RHX shell welds would subject the licensee to a significant hardship, with no compensating increase in quality or safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), it is recommended that the licensee's proposed alternative found in Request for Relief 03-001 be authorized for the second interval at Catawba 1-2.

4.0 CONCLUSION

S For Request for Relief 03-001, it has been shown that compliance with the Code requirements would result in a hardship or unusual difficulty with no compensating increase in quality or safety. The alternative proposed by the licensee provides reasonable assurance of the continued leakage or structural integrity of the subject component. Therefore, for Request for Relief 03-001, it is recommended that the licensee's alternative be authorized pursuant to 10 CFR 50.55a(a)(3)(ii) for the second interval at Catawba 1-2.

1. Databases searched include:

NUREGICR-5779 (1992). a survey of operating experience with non-power cycle heat exchangers performed by Oak Ridge National Laboratory based on three data sources: 1)LERs through 1991. 2) the Nuclear Plant Reliability Data System (NPRDS) which is now the Equipment Performance and Information Exchange (EPIX). and 3) Nuclear Power Experience.

PIPExpTO, a commercially available database which lead in 2002 to the establishment of the OECD/Nuclear Energy Agency Pipe Failure Data Exchange (OPDE) project. As an international cooperative effort, OPDE is supported by 12 countries and 19 organizations as a forum for component failure data exchange and analysis.

EGG-SSRE-9639 (1991). This report by the Idaho National Engineering Laboratory (INEL) provides leak and rupture frequency estimates for heat exchanger shells. The estimates are based on reviews of information extracted from nuclear power experience. The raw data provided in an appendix to the report shows zero heat exchanger pressure boundary failures.

\9 Problem In estigation Process GeneralOffice

\ J ki II G-05-00271 0 4 R-1 _

Problem Identification Discovered Time/Date: 10:07 08/11/2005 Occurred Time/Date:

Unit(s) Affected:

Unit Mode %Power Unit Status Remarks System(s) Affected:

Affected Equipment (No Equipment Affected) location or Problem:

Bldg: Column Une: Elev:

Location Remarks:

Method Used to Discover Problem:

Brief Problem

Description:

equired ASME Section XI Class 2 examinations were not performed on the Seal Water Return Filter during the Second 10 Year Inspection K<_,al.

Detail Problem

Description:

During the Catawba Unit I Second 10 Year Inspection Interval Plan Development, it was determined that the Seal Water Return Filter was not a part of the NV System portion of ECCS. Therefore, this piece of equipment was originally evaluated to the Non-ECCS requirements of the ASME Section XI Code, 1989 Edition, Subsection IWC-1222 and wvas scheduled to be examined. During the first period in the inspection interval, all Class 2 Equipment was re-evaluated and the exemptions clarified in the 1989 Addenda as stated in ISTE-004 were applied. By applying these exemption clarifications, the Seal Water Return Filter was exempted and removed from the examination schedule. Later in the inspection interval, the NV Systern ECCS and Non-ECCS boundaries were redefined thus making the Seal Water Return Filter part of the ECCS boundary. With this change in definition came a new set of exemptions contained in Subsection IWC-1221 and due to the size of the inlet and outlet lines, the Seal Water Return Filter could no longer be exempted. During the re-assessment of the ECCS boundaries, the required exams for the Seal Water Return Filter were not added to the examination schedule.

(Created for 1 C Cherry)

Originated By: TDM8384: MYERS, TIMOTHY D Team: RKR8391 Group: ISI Date: 08/11/2005 Other Units/Components/Systems/Areas Affected(YNMU): N Industry Plants Affected(Y.N.IJ): U Immediate Corrective Actions:

Immediate Corrective Action Documents / Work Orders:

Indiv Team GrouR Date lerm Identified By: TDM8384 RKR8391 [Si 08/11/2005

<,lem Entered By: TDM8384 RKR8391 IS1 08/1112005 Page 1 PiP No: G-05-00271 0811712005 16:00 08/1712005 16:00 PageI PIPNo:GC-05-00271

Problem Investigation Process GeneralOffice

&y: 4 Root Cause performed? No OEP No:

Other Report Nos:

Event Codes:

U Other. Describe in Screening Remarks.

Screening Remarks:

This PIP documents the changes required in the second interval ISI Plan required due to a redefinition of the ECCS Boundary.

Last Updated By: TDM8384: MYERS, TIMOTHY D Team: RKR8391 Group: ISI Date: 08/1 12005 Explanation for 'OTHER' Event Code Assignments:

Responsible Groups(s) for Problem Evaluation: Responsible Group for Present Operability: N/A Responsible Group for Report Support Info: N/A Responsible Group for Reportability: N/A Responsible Group for Overall PIPApproval: ISI INSERVICE INSPECTION reened By: TDM8384 RKR8391 SI 08/11/2005 PresentOperability Responsible Group: Status:

Sys/Cornp Operable? (Y,NC,E,I):

Required Mode:

Comments:

No Current Signatures For This Section Reportabilitv Responsible Group: Status:

Problem Reportable(YN,E):

Reportable Per:

Comments:

No Current Signatures For This Section Investigation Report:

Page 2 PIPNo: G-05-00271 08/17/2005 16:00 081171200 Page2 PlP]Vo:GC-05-00271

Problem Investigation Process GeneralOffice

. onsible Group: Act Date:

Investigator: Group:

Due Date:

Date Due to VP or Sta. Mgr:

Date Regulatory or Agency Rpt Due:

Date Investigation Report Approved:

NRC Cause Codes:

Report Support Info:

Responsible Group: Status:

No Current Signatures For This Section Problem Evaluation en_

Problem Evaluation From: N/A rrectiveActions CA Seq. No: 1 ISI Closed ISI U P R Proposed Corrective Action:

Initiate Plan Addendum for the second interval Catawba Unit 1 ISI Plan to add the required examinations for the Seal Water Return Filter.

(Entered for J E Cherry)

Rinated By: TDM8384: MYERS, TIMOTHY D Team: RKR8391 Group. 1SI Date: 08/11 2005 Approval Assigned To: RKR8391 RKR8391 ISI 08/11/2005 Ready For Approval: TDM8384 RKR8391 IS 08117/2005 Approved By: TDM8384 RKR8391 ISI 08/17/2005 Ceneral:Outage: Mode:

Other Tracking Processes Type Number Text Actual Corrective Action:

Priority: 2 Actual CAC: Status: ReadyForAccept Due Date: 08/31/2005 I AssignedTo: AJH8300 RKR8391 ISI 08/11/2005 0817t2oo5 16:00 Page3 PIPNo: G-05-00271

Problem Investigation Process General Office II re.I

\_. Date: 08/31/2005 1 Finaland Overall PIPApproval Responsible Group: SI Status: Screened e i lAssigned To: 151 08/11/20O05 Any Supplemental Concurrence Signatures Above Do Not Affect PIP Closure.

Closure Document Type Closure Document No Attachments Generic Applicability Responsible Group: Status:

GO PIP No:

Arsessment Remarks:

No Current Signatures For This Section FailurePreventionInvestigation No FPI Records for this PIP.

Remarks No Remarks for this PIP.

Maintenance Rule No Maintenance Rule Records for this PIP.

End of the Document for PIP No: G-5-271 The status of this PIP is: Screened The duration of this PIP was: 0 days Page 4 PIP No: G.O5-00271 08/1712005 16:00 0811712005 16:00 Page4 PWIP o G05400271

'J 3.0 Final Inservice Inspection Plan The final Inservice Inspection Plan shown in this section lists all ASME Section Xl Class 1, ASME Section Xl Class 2, and Augmented inspections credited for this report.

The information shown below is a field /description for the reporting format included in this section of the report:

Item Number ASME Section Xl Tables IWB-2500-1 (Class 1), IWC-2500-1 (Class 2), IWF-2500-1 (Class 1 and Class 2), and Augmented Requirements ID Number = Unique Identification Number ISO / Dwg Numbers = Location and/or Detail Drawings Proc = Examination Procedures Insp Req = Examination Technique - Magnetic Particle, Dye Penetrant, etc.

Material / Sch = General Description of Material Dia / Thk - Diameter / Thickness Cal Blocks = Calibration Block Number Comments - General and/or Detail Description Refueling Outage EOC 15 (Outage 7) Page 1 of 1 Catawba Unit 1 Revision 0 Section 3 August 15, 2005

EOC 15

(

CATEGORY B-A, Pressure Retaininq Welds in C

DUKE ENERGY- .. )RPORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Reactor Vessel Inservice Inspection Database Management System Plan Report jW~hl elds Catawba 1 Page 1 Inservice Inspection Plan for Interval 2 Outage 7 08/04t2005 ITEM NUMBER ID NUIMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Circumferential ****

B01.011.001 I RPV-W03 CNM 1201.01.51

• UT CS 0.000 PDI.01 Circ Weld 02 to 03 Lower Head to Shell Circumferential NC 5.300 'Use WesDyne Procedure PDIlISI254.

Class A RPV Lower Head to Shell 801.011.002 1RPV-W04 CNM 1201.01-51 UT CS 0.000 PDI-01 Circumferential Weld 03 to 04 Shell to Shell Circumferential NC 8.600 *Use WesDyne Procedure PDI-ISI-254.

Class A RPV Shell to RPV Shell B01.011.003 1RPV-W05 CNM 1201.01.51 ^ UT CS 0.000 PDI-01 Circumferential Weld 04 to 05 Shell to Shell Circumferential NC 8.600 *Use WesDyne Procedure PDI-ISI-254.

Class A RPV Shell to RPV Shell 801.011.004 1RPV-WO6 CNM 1201.01-51 ^ UT CS 0.000 PDI-01 Circumferential Weld 05 to 0 Shell to Nozzle Belt Circumferential NC 8.600 'Use WesDyne Procedure P5J ISI 254.

Class A Shell to Nozzle Belt Total Bo1.011 Items: 4

(

EOC 15 CATEGORY B-A. Pressure Retaining Welds in DUKE ENERG. APORATION INSERVICE INSPECTION PLAN MANAGEMENT

(

Reactor Vessel Inservice Inspection Database Management System Plan Report Mead Welds Catawba 1 Page 2 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISOIDWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Circumferential ****

B01.021.001 1RPV-WO1 CNM 1201.01-51 UT CS 0.000 PDI-01 Circ Weld 01 to02 Lower Head Circumferential NC 5.300 *Use WesDyne Procedure PDI-ISI-254.

Class A RPV Lower Head to RPV Lower Head Total B01.021 Items: 1

• • • • Merldional ****

801.022.001 1RPV-W02-01 CNM 1201.01-51

• UT CS 0.000 PDI-01 Meridional Weld PC 02 302 Deg Lower Head Longitudinal NC 5.300 *Use WesDyne Procedure PDI-ISI-254.

Class A RPV Lower Head to RPV Lower Head B01.022.002 1RPV-W02-02 CNM 1201.01-51

• UT CS 0.000 PDI-01 Meridional Weld PC 02 242 Deg. RPV Lower Head Longitudinal NC 5.300 *Use WesDyne Procedure P*ISI-254.

Class A RPV Lower Head to RPV Lower Head B01.022.003 1RPV-W02-03 CNM 1201.01-51

• UT CS 0.000 PD1-01 Merldional Weld PC 02 182 Deg. RPV Lower Head Longitudinal NC 5.300 *Use WesDyne Procedure PDI-lSI-254.

Class A RPV Lower Head to RPV Lower Head B01.022.004 1RPV-W02-04 CNM 1201.01-51

• UT CS 0.000 PDI-01 Meridional Weld PC 02 122 Deg. RPV Lower Head Longitudinal NC 5.300 *Use WesDyne Procedure PDI-ISI-254.

Class A RPV Lower Head to RPV Lower Head B01.022.005 1RPV-W02-05 CNM 1201.01-51 UT CS 0.000 PDI-01 Meridional Weld PC 02 62 Deg. RPV Lower Head Longitudinal NC 5.300 'Use WesDyne Procedure PDI-ISI-254.

Class A RPV Lower Head to RPV Lower Head B01.022.006 1RPV-W02-06 CNM 1201.01-51

• UT CS 0.000 PD1-01 Meridional Weld PC 022 Deg. RPV Lower Head Longitudinal NC 5.300 'Use WesDyne Procedure PDI-ISI-254.

Class A RPV Lower Head to RPV Lower Head Total B01.022 Items: 6

EOC 15 (

DUKE ENERG( APORATION CATEGORY B-A, Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Reactor Vessel Inservice Inspection Database Management System Plan Report Shell-to-Flanae Weld Catawba 1 Page 3 Inservice Inspection Plan for Interval 2 Outage 7 0810412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REO MAT/SCH DIANTHK CAL BLOCKS COMMENTS

• • • • Shell-to-Flange ****

B01.030.001 1RPV-W07 CNM 1201.01-51

• UT CS 0.000 PDI-01 06 to 07 Nozzle Belt to Flange Circumferential NC CNM 1201.01-63 10.900 UT From Vessel ID Class A RPV Nozzle Belt to 'Use WesDyne Procedure PDI-ISI-254.

RPV Flange Total B01.030 Items: 1 Total B01 Items: 12

(

EOC 15 CATEGORY B-D. Full Penetration Welds of DUKE ENERGC ,RPORATION INSERVICE INSPECTION PLAN MANAGEMENT

(

Nozzels In Vessels Inservice Inspection Database Management System Plan Report Reactor Vessel Catawba 1 Page 4 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Nozzle-to-Vessel Welds B03.090.001 1RPV-W1l CNM 1201.01-51 UT CS 61.500 PDI-01 Inlet Nozzle B to Shell 67 Deg. Loop A Circumferential NC CNM 1201.01-64 10.900 UT From Vessel ID Class A RPV Inlet Nozzle to Use WesDyne Procedure PDI-ISI-254.

Shell B03.090.001A 1RPV-W11 CNM 1201.01-51

• UT CS 61.500 PDI-01 Inlet Nozzle B to Shell 67 Deg. Loop A Circumferential NC CNM 1201.01-64 10.900 UT From Nozzle ID Class A RPV Inlet Nozzle to *Use WesDyne Procedure PDI-ISI-254-NZ.

Shell B03.090.002 1RPV-W12 CNM 1201.01-51 UT CS 61.500 PDI-01 Inlet Nozzle C to Shell 113 Deg. Loop B Circumferential NC CNM 1201.01-64 10.900 UT From Vessel ID Class A RPV Inlet Nozzle to *Use WesDyne Procedure PAl-ISI-254.

Shell B03.090.002A 1RPV-W12 CNM 1201.01-51 UT CS 61.500 PDI-01 Inlet Nozzle C to Shell 113 Deg. Loop B Circumferential NC CNM 1201.01-64 10.900 UT From Nozzle ID Class A RPV Inlet Nozzle to *Use WesDyne Procedure PDI-ISI-254-NZ.

Shell B03.090.003 1RPV-W13 CNM 1201.01-51

• UT CS 61.500 PDI-01 Inlet Nozzle F to Shell 247 Deg. Loop C Circumferential NC CNM 1201.01-64 10.900 UT From Vessel ID Class A RPV Inlet Nozzle to *Use WesDyne Procedure PDI-ISI-254.

Shell B03.090.003A 1RPV-W13 CNM 1201.01-51

• UT CS 61.500 PDI-01 Inlet Nozzle F to Shell 247 Deg. Loop C Circumferential NC CNM 1201.01-64 10.900 UT From Nozzle ID Class A RPV Inlet Nozzle to *Use WesDyne Procedure PDI-ISI-254-NZ.

Shell B03.090.004 1RPV-W14 CNM 1201.01-51

• UT CS 61.500 PDI-01 Inlet Nozzle G to Shell 293 Deg. Loop D Circumferential NC CNM 1201.01-64 10.900 UT From Vessel ID Class A RPV Inlet Nozzle to *Use WesDyne Procedure PDI-ISI-254.

Shell B03.090.004A 1RPV-W14 CNM 1201.01-51

• UT CS 61.500 PDI-01 Inlet Nozzle G to Shell 293 Deg. Loop D Circumferential NC CNM 1201.01-64 10.900 UT From Nozzle ID Class A RPV Inlet Nozzle to *Use WesDyne Procedure PDI-ISI-254-NZ.

Shell

EOC 15 CATEGORY B-D, Full Penetration Welds of DUKE ENERGC( RPORATION C, INSERVICE INSPECTION PLAN MANAGEMENT Nozzels in Vessels Inservice Inspection Database Management System Plan Report Reactor Vessel Catawba 1 Page 5 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIATHK CAL BLOCKS COMMENTS B03.090.005 1RPV-W15 CNM 1201.01-51

• UT CS 52.900 PDI-01 Outlet Nozzle A to Shell 22 Deg. Loop A Circumferential NC CNM 1201.01-65 10.900 UT From Vessel ID Class A RPV Outlet Nozzle to 'Use WesDyne Procedure PDI-ISI-254.

Shell B03.090.005A 1RPV-W15 CNM 1201.01-51

• UT CS 52.900 PDI-01 Outlet Nozzle Ato Shell 22 Deg. Loop A Circumferential NC CNM 1201.01-65 10.900 UT From Nozzle ID Class A RPV Outlet Nozzle to Ref. Request For Relief Serial Number 93-02 Shell Ref. Request For Relief Serial Number 94-05

• Use WesDyne Procedure PDI-ISI-254-NZ.

B03.090.006 1RPV-W16 CNM 1201.01-51 UT CS 52.900 PDI-01 Outlet Nozzle D to Shell 158 Deg. Loop B Circumferential NC CNM 1201.01-65 10.900 UT From Vessel ID k Class A RPV Outlet Nozzle to 'Use WesDyne Procedure PlUISI-254.

Shell B03.090.006A 1RPV-W16 CNM 1201.01-51 UT CS 52.900 PDI-01 Outlet Nozzle D to Shell 158 Deg. Loop B Circumferential NC CNM 1201.01-65 10.900 UT From Nozzle ID Class A RPV Outlet Nozzle to Ref. Request For Relief Serial Number 93-02 Shell Ref. Request For Relief Serial Number 94-05

'Use WesDyne Procedure PDI-ISI-254-NZ.

B03.090.007 1RPV-W17 CNM 1201.01-51 UT CS 52.900 PDI-01 Outlet Nozzle E to Shell 202 Deg. Loop C Circumferential NC CNM 1201.01-65 10.900 UT From Vessel ID Class A RPV Outlet Nozzle to *Use WesDyne Procedure PDI-ISI-254.

Shell B03.090.007A 1RPV-W17 CNM 1201.01-51

• UT CS 52.900 PDI-01 Outlet Nozzle E to Shell 202 Deg. Loop C Circumferential NC CNM 1201.01-65 10.900 UT From Nozzle ID Class A RPV Outlet Nozzle to Ref. Request For Relief Serial Number 93-02 Shell Ref. Request For Relief Serial Number 94-05

'Use WesDyne Procedure PDI-ISI-254-NZ.

B03.090.008 1RPV-W18 CNM 1201.01-51 UT CS 52.900 PDI-01 Outlet Nozzle H to Shell 338 Deg. Loop D Circumferential NC CNM 1201.01-65 10.900 UT From Vessel ID Class A RPV Outlet Nozzle to *Use WesDyne Procedure PDI-ISI-254.

Shell B03.090.008A 1RPV-W18 CNM 1201.01-51

• UT CS 52.900 PDI-01 Outlet Nozzle H to Shell 338 Deg. Loop D Circumferential NC CNM 1201.01-65 10.900 UT From Nozzle ID Class A RPV Outlet Nozzle to Ref. Request For Relief Serial Number 93-02 Shell Ref. Request For Relief Serial Number 94-05

• Use WesDyne Procedure PDI-ISI-254-NZ.

EOC 15 (

DUKE ENERGIC APORATION CATEGORY B-D. Full Penetration Welds of INSERVICE INSPECTION PLAN MANAGEMENT Nozzels in Vessels Inservice Inspection Database Management System Plan Report Reactor Vessel Catawba 1 Page 6 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS Total B03.090 Items: 16

EOC 15 DUKE ENERG' .APORATION CATEGORY B-D. Full Penetration Welds of INSERVICE INSPECTION PLAN MANAGEMENT Nozzels In Vessels Inservice Inspection Database Management System Plan Report Reactor Vessel Catawba 1 Page 7 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER IDNUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Nozzle Inside Radius Section ****

803.100.001 1RPV-W11 CNM 1201.01-51 VT-1 CS 61.500 Inlet Nozzle B to Shell 67 Deg. Loop A Circumferential NC CNM 1201.01-64 10.900 An EVT-1 examaination shall be performed in lieu of Class A RPV Inlet Nozzle to UT per Code Case N-648-1.

Shell *Use WesDyne Procedure WDI.STD-088.

B03.100.002 1RPV-W12 CNM 1201.01-51 VT-1 CS 61.500 Inlet Nozzle C to Shell 113 Deg. Loop B Circumferential NC CNM 1201.01-64 10.900 An EVT-1 examaination shall be performed in lieu of Class A RPV Inlet Nozzle to UT per Code Case N-648-1. 1 Shell *Use WesDyne Procedure WDI.STD-088.

B03.100.003 1RPV-W13 CNM 1201.01.51

• VT-1 CS 61.500 Inlet Nozzle F to Shell 247 Deg. Loop C Circumferential NC CNM 1201.01.64 10.900 An EVT-1 examaination shall be performed in lieu of Class A RPV Inlet Nozzle to UT per Code Case N-648:1.

Shell *Use WesDyne Procedure WDI-STD-088.

B03.100.004 1RPV-W14 CNM 1201.01-51 VT-1 CS 61.500 Inlet Nozzle G to Shell 293 Deg. Loop D Circumferential NC CNM 1201.01-64 10.900 An EVT-1 examaination shall be performed in lieu of Class A RPV Inlet Nozzle to UT per Code Case N-648-1.

Shell *Use WesDyne Procedure WDI-STD-088.

803.100.005 1RPV-W15 CNM 1201.01-51

• VT-1 CS 52.900 Outlet Nozzle A to Shell 22 Deg. Loop A Circumferential NC CNM 1201.01-65 10.900 Ref. Request For Relief Serial Number 93-02 Class A RPV Outlet Nozzle to Ref. Request for Relief Serial Number 94-05 Shell An EVT-1 examaination shall be performed in lieu of UT per Code Case N-648-1.

• Use WesDyne Procedure WDI-STD-088.

B03.100.006 1RPV-W16 CNM 1201.01-51 ^ VT-1 CS 52.900 Outlet Nozzle Dto Shell 158 Deg. Loop B Circumferential NC CNM 1201.01-65 10.900 Ref. Request For Relief Serial Number 93-02 Class A RPV Outlet Nozzle to Ref. Request for Relief Serial Number 94-05 Shell An EVT-1 examaination shall be performed in lieu of UT per Code Case N-648-1.

• Use WesDyne Procedure WDI.STD-088.

B03.100.007 1RPV-W17 CNM 1201.01-51

• VT-1 CS 52.900 Outlet Nozzle E to Shell 202 Deg. Loop C Circumferential NC CNM 1201.01-65 10.900 Ref. Request For Relief Serial Number 93-02 Class A RPV Outlet Nozzle to Ref. Request for Relief Serial Number 94-05 Shell An EVT-1 examainatlon shall be performed in lieu of UT per Code Case N-648-1.

• Use WesDyne Procedure WDI-STD-088.

EOC 15 CATEGORY B-D, Full Penetration Welds of DUKE ENERG .JRPORATION INSERVICE INSPECTION PLAN MANAGEMENT

(

Nozzels In Vessels Inservice Inspection Database Management System Plan Report Reactor Vessel Catawba 1 Page 8 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS B03.100.008 1RPV-W18 CNM 1201.01-51 VT-1 CS 52.900 Outlet Nozzle H to Shell 338 Deg. Loop D Circumferential NC CNM 1201.01-65 10.900 Ref. Request For Relief Serial Number 93-02 Class A RPV Outlet Nozzle to Ref. Request for Relief Serial Number 94-05 Shell An EVT-1 examainatlon shall be performed in lieu of UT per Code Case N-648-1.

• Use WesDyne Procedure WDI-STD-088.

Total B03.100 Items: 8

EOC 15

(

CATEGORY B-D, Full Penetration Welds of DUKE ENERG$ APORATION INSERVICE INSPECTION PLAN MANAGEMENT Nozzels In Vessels Inservice Inspection Database Management System Plan Report Pressurizer Catawba 1 Page 9 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER IDINIUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS Nozzle-to-Vessel Welds **

B03.110.001A 1PZR-W1 CNM 1201.01-175/1 NDE-640 UT CS 24.500 50338 Pressurizer Surge Nozzle to Lower Head Weld Circumferential NC CNM 1201.01-175/2 NDE-820 2.550 Reference PIP #G-03-00289 Class A PZR Surge Nozzle to Lower Head B03.110.004A 1PZR-W4A CNM 1201.01-175/1 NDE-640 UT CS 15.000 50338 Pressurizer Safety Nozzle to Upper Head Weld Circumferential NC CNM 1201.01-175/2 NDE-820 1.900 X-Y Quadrant Class A PZR Safety Nozzle to Reference PIP #G.03-00289 Upper Head B03.110.005 1PZR-W4B CNM 1201.01-175/1 NDE-640 UT CS 15.000 50338 Pressurizer Safety Nozzle to Upper Head Weld Circumferential NC CNM 1201.01-175/2 NDE-820 1.900 W-X Quadrant Class A PZR Safety Nozzle to Upper Head B03.110.006A 1PZR-W4C CNM 1201.01-175/1 NDE-640 UT CS 15.000 50338 Pressurizer Safety Nozzle to Upper Head Weld Circumferential NC CNM 1201.01-175/2 NDE-820 1.900 W-Z Quadrant Class A PZR Safety Nozzle to Reference PIP #G-03-00289 Upper Head Total B03.1 10 Items: 4

EOC 15 (

CATEGORY B-D, Full Penetration Welds of DUKE ENERG .. APORATION INSERVICE INSPECTION PLAN MANAGEMENT Q

Nozzels In Vessels Inservice Inspection Database Management System Plan Report Pressurizer Catawba 1 Page 10 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Nozzle Inside Radius Section ****

B03.120.00A 1PZR-W1 CNM 1201.01-175/1 NDE-680 UT CS 24.500 CB-01-163 Pressurizer Surge Nozzle to Lower Head Weld Circumferential NC CNM 1201.01-175/2 2.550 (Inside Radius)

Class A PZR Surge Nozzle to Reference PIP #G-03-00289 Lower Head B03.120.004A 1PZR-W4A CNM 1201.01-175/1 NDE-680 UT CS 15.000 Pressurizer Safety Nozzle to Upper Head Weld CircumferentIal NC CNM 1201.01-175/2 3.750 50237D (Inside Radius)

Class A PZR Safety Nozzle to Reference PIP #G-03-00289 Upper Head B03.120.005 1PZR-W4B CNM 1201.01-175/1 NDE-680 UT CS 15.000 Pressurizer Safety Nozzle to Upper Head Weld Circumferential NC CNM 1201.01-175/2 3.750 50237D (Inside Radius)

Class A PZR Safety Nozzle to Upper Head B03.120.006A 1PZR-W4C CNM 1201.01-175/1 NDE-680 UT CS 15.000 Pressurizer Safety Nozzle to Upper Head Weld Circumferential NC CNM 1201.01-175/2 3.750 50237D (Inside Radius)

Class A PZR Safety Nozzle to Reference PIP #G-03-00289 Upper Head Total B03.120 Items: 4

EOC 15 CATEGORY B-D. Full Penetration Welds of DUKE ENERGC APORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Nozzels In Vessels Inservice Inspection Database Management System Plan Report WSteam Generators (Primary Side) Catawba 1 Page 11 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER IDNUMBER SYS ISO/DWG NUME3ERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Nozzle Inside Radius Section ****

B03.140.005 1SGC-INLET CNM 1201.01-609 NDE-680 UT CS 39.000 50235 Steam Generator IC Primary let Nozzle Circumferential NC CNM 1201.01-618 6.125 (Inside Radius Section) '

Class A B03.140.006 1SGC-OUTLET CNM 1201.01-609 NDE-680 UT CS 39.000 50235 Steam Generator 1C Primary Outlet Nozzle Circumferential NC CNM 1201.01-618 6.125 (Inside Radius Section) . .

Class A Total B03.140 Items: 2 Total B03 Items: 34

EOC 15 Q CATEGORY B-F, Pressure Retaining Dissimilar DUKE ENERG C APORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Metal Welds Inservice Inspection Database Management System Plan Report EReactor Vessel Catawba 1 Page 12 N Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS

• • • • NPS 4 or larger; Nozzle-to-Safe End Butt Welds **** I B05.010.001 1RPV-W11-SE CNM 1201.01-64 UT SS-CS 27.500 RV Inlet Nozzle Bto Safe End '7Deg. Loop A Circumferential NC CN-1 NC-024 2.200 UT from Nozzle Side Class A Nozzle to *NavShips Test Block S/N Dissimilar Safe End 045202

• • Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.012' B05.010.001A 1RPV-W11-SE CNM 1201.01-64 UT SS-CS 27.500

• RV Inlet Nozzle B to Safe End 67 Deg. Loop A Circumferential NC CN-1NC-024 2.200 UT from Pipe Side Class A Nozzle to 'NavShips Test Block S/N Dissimilar Safe End 045202 "Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.1 30.012A B05.010.001B 1RPV-W11-SE CNM 1201.01-64 NDE-35 PT SS-CS 27.500 RV Inlet Nozzle B to Safe End 67 Deg. Loop A Circumferential NC CN.1NC-024 2.200 Class A Nozzle to Dissimilar Safe End B05.010.002 1RPV-W12-SE CNM 1201.01-64 *^ UT SS-CS 27.500

• RV Inlet Nozzle C to Safe End 113 Deg. Loop B Circumferential NC CN-1 NC-022 2.200 UT from Nozzle Side Class A Nozzle to 'NavShips Test Block S/N Dissimilar Safe End 045202 "Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.004 805.010.002A 1RPV-W12-SE CNM 1201.01-64 UT SS-CS 27.500 ^ RV Inlet Nozzle C to Safe End 113 Deg. Loop B Circumferential NC CN-1 NC 022 2.200 UT from Pipe Side Class A Nozzle to *NavShips Test Block S/N Dissimilar Safe End 045202

• • Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.004A B05.010.002B 1RPV-W12-SE CNM 1201.01-64 NDE-35 PT SS-CS 27.500 RV Inlet Nozzle C to Safe End 113 Deg. Loop B Circumferential NC CN-1 NC-022 2.200 Class A Nozzle to Dissimilar Safe End B05.010.003 1RPV-W13-SE CNM 1201.01 64 UT SS-CS 27.500

• RV Inlet Nozzle F to Safe End 247 Dea. Loop C Circumferential NC CN-1NC-025 2.200 UT from Nozzle Side Class A Nozzle to *NavShips Test Block S/N 045202 Safe End **Use WesDyne Procedure PDI-ISI-254-SE

EOC 15 ( DUKE ENERG( .APORATION CATEGORY B-F. Pressure Retaininq Dissimilar INSERVICE INSPECTION PLAN MANAGEMENT Metal Welds Inservice Inspection Database Management System Plan Report

• Reactor Vessel Catawba 1 Page 13 N Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISOIDWG NUMBERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS I To be done with 805.130.016 B05.010.003A 1RPV-W13-SE CNM 1201.01-64 UT SS-CS 27.500 RV Inlet Nozzle F to Safe End 247 Deg. Loop C Circumferential NC CN-i NC-025 2.200 UT from Pipe Side Class A Nozzle to *NavShips Test Block SIN 045202 Dissimilar Safe End "Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.016A B05.010.0038 1RPV-W13-SE CNM 1201.01-64 NDE-35 PT SS-CS 27.500 RV Inlet Nozzle F to Safe End 247 Deg. Loop C Circumferential NC CN-1 NC-025 2.200 Class A Nozzle to Dissimilar Safe End B05.010.004 1RPV-W14-SE CNM 1201.01-64 ** UT SS-CS 27.500

• RV Inlet Nozzle G to Safe End 293 Deg. Loop D Circumferential NC CN-1 NC-023 2.200 UT from Nozzle Side Class A Nozzle to *NavShips Test Block S/N 045202 Dissimilar Safe End **Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.008 B05.010.004A 1RPV-W14-SE CNM 1201.01-64 UT SS-CS 27.500

• RV Inlet Nozzle G to Safe End 293 Deg. Loop D Circumferential NC CN-INC-023 2.200 UT from Pipe Side Class A Nozzle to 'NavShips Test Block S/N 045202 Dissimilar Safe End **Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.008A B05.010.0048 1RPV-W14-SE CNM 1201.01-64 NDE-35 PT SS-CS 27.500 RV Inlet Nozzle G to Safe End 293 Deg. Loop D Circumferential NC CN-i NC-023 2.200 Class A Nozzle to Dissimilar Safe End B05.010.005 1RPV-W15-SE CNM 1201.01-65 UT SS-CS 29.000 RV Outlet Nozzle A to Safe End 22 Deq. Loop A Circumferential NC CN-I NC-024 2.300 UT from Nozzle Side Class A Nozzle to Ref. Request For Relief Serial Number 93-02 Safe End Ref. Request for Relief Serial Number 94-05 Dissimilar

• NavShips Test Block S/N 045202

• • Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.009

EOC 15 ( DUKE ENERG( APORATION CATEGORY B-F, Pressure Retaining Dissimilar INSERVICE INSPECTION PLAN MANAGEMENT Metal Welds Inservice Inspection Database Management System Plan Report E~etr Vessel Catawba 1 b. Page 14 Inservice Inspection Plan for Interval 2 Outage 7 ll 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DINTHK CAL BLOCKS COMMENTS B05.010.005A 1RPV-W15-SE CNM 1201.01-65 UT SS-CS 29.000 o RV Outlet Nozzle A to Safe End 22 Deg. Loop A Circumferential NC CN-INC-024 2.300 UT from Pipe Side Class A Nozzle to Ref. Request For Relief Serial Number 93-02 Dissimilar Safe End Ref. Request for Relief Serial Number 94-05

• NavShips Test Block S/N 045202

• • Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.009A B05.010.006 1RPV-W16-SE CNM 1201.01-65 UT SS-CS 29.000 ^ RV Outlet Nozzle D to Safe End 158 Deg. Loop B Circumferential NC CN-1NC-022 2.300 UT from Nozzle Side Class A Nozzle to Ref. Request For Relief Serial Number 93-02 Dissimilar Safe End Ref. Request for Relief Serial Number 94.05

• NavShips Test Block S/N 045202 "Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.001 B05.010.006A 1RPV-W16-SE CNM 1201.01-65 UT SS-CS 29.000 ^ RV Outlet Nozzle D to Safe End 158 Deg. Loop B Circumferential NC CN-1NC-022 2.300 UT from Pipe Side Class A Nozzle to Ref. Request For Relief Serial Number 93-02 Dissimilar Safe End Ref. Request for Relief Serial Number 94-05

• NavShips Test Block SIN 045202

• • Use WesDyne Procedure PDI ISI-254-SE To be done with B05.130.001A B05.010.007 1RPV-W17-SE CNM 1201.01-65 UT Ss-CS 29.000 ^ RV Outlet Nozzle E to Safe End 202 Deg. Loop C Circumferential NC CN-1NC-025 2.300 UT from Nozzle Side Class A Nozzle to Ref. Request For Relief Serial Number 93-02 Dissimilar Safe End Ref. Request for Relief Serial Number 94-05

'NavShips Test Block S/N 045202 "Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.013 B05.010.007A 1RPV-W17-SE CNM 1201.01-65 UT SS-CS 29.000 RV Outlet Nozzle E to Safe End 202 Deg. Loop C Circumferential NC CN-1 NC-025 2.300 UT from Pipe Side Nozzle to Ref. Request For Relief Serial Number 93-02 Class A Safe End Ref. Request for Relief Serial Number 94-05 Dissimilar *NavShips Test Block S/N 045202

"*Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.013A

EOC 165 (

DUKE ENERGY'. .RPORATION CATEGORY B-F, Pressure Retaininct Dissimilar INSERVICE INSPECTION PLAN MANAGEMENT Metal Welds Inservice Inspection Database Management System Plan Report Reactor Vessel Catawba 1 P1 Page 15 N Inservice Inspection Plan for Interval 2 Outagi a7 0810412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS B05.010.008 1RPV-W18-SE CNM 1201.01-65 UT SS-CS 29.000 ^ RV Outlet Nozzle H to Safe End 338 Deg. Loop D Circumferential NC CN-1NC-023 2.300 UT from Nozzle Side Class A Nozzle to Ref. Request For Relief Serial Number 93-02 Dissimilar Safe End Ref. Request for Relief Serial Number 94-05

• NavShips Test Block S/N 045202

`*Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.005 B05.010.008A 1RPV-W18.SE CNM 1201.01-65 UT SS-CS 29.000 ^ RV Outlet Nozzle H to Safe End 338 Deg. Loop D Circumferential NC CN-1NC-023 2.300 UT from Pipe Side Class A Nozzle to Ref. Request For Relief Serial Number 93-02 Dissimilar Safe End Ref. Request for Relief Serial Number 94-05

• NavShips Test Block S/N 045202

^^Use WesDyne Procedure PDI-ISI-254-SE To be done with B05.130.005A Total B05.010 Items: 20

EOC 15 CATEGORY B-F, Pressure Retaining Dissimilar DUKE ENERGL.RPORATION INSERVICE INSPECTION PLAN MANAGEMENT P"

C Metal Welds Inservice Inspection Database Management System Plan Report ESteam Generator Catawba 1 Page 16 i Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REO MAT/SCH DIAITHK CAL BLOCKS COMMENTS NPS 4 or Larger; Nozzle-to-Safe End Butt Welds 805.070.005 1SGC-INLET-W5SE CNM 1201.01-609 PDI UT-10 UT SS-CS 31.000 5158172 Steam Generator iC Inlet Circumferential NC CNM 1201.01-617 2.750 5149697 Nozzle to Safe End Class A Term end Nozzle to Dissimilar Safe End B05.070.005A 1SGC.INLET-W5SE CNM 1201.01-609 NDE-35 PT SS-CS 31.000 Steam Generator IC Inlet Circumferential NC CNM 1201.01.617 2.750 Nozzle to Safe End Class A Term end Nozzle to Dissimilar Safe End 805.070.006 1SGC-OUT-W6SE CNM 1201.01.609 PDI.UT-10 UT SS-CS 31.000 5158172 Steam Generator IC Outlet Circumferential NC CNM 1201.01-617 2.750 5149697 Nozzle to Safe End Class A Term end Nozzle to Dissimilar Safe End B05.070.006A 1SGC-OUT-W6SE CNM 1201.01-609 NDE-35 PT SS-CS 31.000 Steam Generator iC Outlet Circumferential NC CNM 1201.01-617 2.750 Nozzle to Safe End Class A Term end Nozzle to Dissimilar Safe End Total B05.070 Items: 4

EOC 15 (6 CATEGORY B-F, Pressure Retaining Dissimilar DUKE ENERGY-,. -APORATION INSERVICE INSPECTION PLAN MANAGEMENT I'

Metal Welds Inservice Inspection Database Management System Plan Report Catawba 1 Page 17 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIANTHK CAL BLOCKS COMMENTS

• • • • NPS 4 or Larger; Dissimilar Metal Butt Welds ****

B05.130.001 1NC22-01 CN-1 NC-022 UT SS-CS 29.000

• Outlet Nozzle 0 158 Degrees Loop B Circumferential NC CN-1553-1.0 2.300 UT From Nozzle Side Class A Term end To Be Done With B05.010.006 Dissimilar Ref. Request For Relief Serial Number 93-02 Ref. Request for Relief Serial Number 94-05

• NavShips Test Block S/N 045202

• • Use WesDyne Procedure PDI-ISI-254-SE B05.130.001A 1NC22-01 CN-1NC-022 ^^ UT Ss-CS 29.000 Outlet Nozzle D 158 Degrees Loop B Circumferential NC CN-1553-1.0 2.300 UT From Pipe Side Class A Term end To Be Done With 605.010.006A Dissimilar Ref. Request For Relief Serial Number 93-02 Ref. Request for Relief Serial Number 94-05

• NavShIps Test Block S/N 045202 "Use WesDyne Procedure PDI-ISI-254-SE B05.130.004 1NC22-08 CN- NC-022 UT SS-CS 27.500 ^ Inlet Nozzle C 113 Degrees Loop B Circumferential NC CN-1553-1.0 2.200 UT From Nozzle Side Class A Term end To Be Done With B05.010.002 Dissimilar *NavShips Test Block S/N 045202

• • Use WesDyne Procedure PDI-ISI-254-SE B05.130.004A 1NC22-08 CN- NC-022 UT SS-CS 27.500 Inlet Nozzle C 113 Degrees Loop B Circumferential NC CN-1553-1.0 2.200 UT From Pipe Side Class A Term end To Be Done With B05.010.002A Dissimilar *NavShips Test Block S/N 045202 "Use WesDyne Procedure PDI-ISI-254-SE B05.130.004B 1NC22-08 CNA1NC-022 NDE-35 PT SS-CS 27.500 Inlet Nozzle C 113 Degrees Loop B Circumferential NC CN-1553-1.0 2.200 To Be Done With B05.010.002B Class A Term end Dissimilar B05.130.005 1NC23-01 CNA1NC-023 ** UT SS-CS 29.000

• Outlet Nozzle H 338 Degrees Loop D Circumferential NC CN.1553-1.0 2.300 UT From Nozzle Side Class A Term end To Be Done With 605.010.008 Ref. Request for Relief Serial Number 93-02 Dissimilar Ref. Request For Relief Serial Number 94-05

'NavShips Test Block S/N 045202

`Use WesDyne Procedure PDI-ISI-254-SE

EOC 15 DUKE ENERG ,APORATION CATEGORY B-F, Pressure Retaining Dissimilar INSERVICE INSPECTION PLAN MANAGEMENT Metal Welds Inservice Inspection Database Management System Plan Report N pno Catawba I *.Page 18 08/04/2005 N Inservice Inspection Plan for Interval 2 Outag e 7 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS B05.130.005A 1NC23-01 CN-1NC-023 UT SS-CS 29.000

• Outlet Nozzle H 338 Degrees Loop D Circumferential NC CN-1553-1.0 2.300 UT From Pipe Side Class A Term end To Be Done With B05.010.008A Dissimilar Ref. Request For Relief Serial Number 93-02 Ref. Request for Relief Serial Number 94-05

• NavShips Test Block S/N 045202 "Use WesDyne Procedure PDI-ISI.254-SE B05.130.008 1NC23-08 CN-INC-023 UT Ss-CS 27.500 Inlet Nozzle G 293 Degrees Loop D Circumferential NC CN-1553-1.0 2.200 UT From Nozzle Side Class A Term end To Be Done With B05.010.004 Dissimilar 'NavShips Test Block SIN 045202

• • Use WesOyne Procedure PDI.ISI-254-SE B05.130.008A 1NC23-08 CN-1NC-023 UT SS-CS 27.500 ^ Inlet Nozzle G 293 Degrees Loop D Circumferential NC CN-1553-1.0 2.200 UT From Pipe Side Class A Term end To Be Done With B05.010.004A Dissimilar *NavShips Test Block S/N 045202

• • Use WesDyne Procedure PDI-ISI-254-SE B05.130.008B 1NC23-08 CN-1NC-023 NDE-35 PT SS-CS 27.500 Inlet Nozzle G 293 Degrees Loop D Circumferential NC CN-1553-1.0 2.200 To Be Done With 805.010.0045 Class A Term end Dissimilar B05.130.009 1NC24-01 CN-1 NC.024 UT SS-CS 29.000 Outlet Nozzle A 22 Degrees Loop A Circumferential NC CN-1 553-1.0 2.300 UT From Nozzle Side Class A Term end To Be Done With 505.010.005 Dissimilar Ref. Request For Relief Serial Number 93-02 Ref. Request for Relief Serial Number 94.05

• NavShips Test Block S/N 045202

• • Use WesDyne Procedure PDI-ISI-254-SE B05.130.009A 1NC24-01 CN-1NC-024 UT SS-CS 29.000 Outlet Nozzle A 22 Degrees Loop A Circumferential NC CN-1553-1.0 2.300 UT From Pipe Side Class A Term end To Be Done With B05.010.005A Dissimilar Ref. Request For Relief Serial Number 93-02 Ref. Request for Relief Serial Number 94-05

'NavShips Test Block S/N 045202

• • Use WesDyne Procedure PDI-ISI-254-SE

F' EOC 15 DUKE ENERG CATEGORY B-F, Pressure Retaining Dissimilar INSERVICE INSPECTION PLAN MANAGEMENT

.APORATION C,

Metal Welds Inservice Inspection Database Management System Plan Report PIpln~q Catawba 1 Page 19 K - Inservice Inspection Plan for Interval 2 Outag ee7 08104/2005 ITEM NUMBER IDNUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MATlSCH DIA/iTHK CAL BLOCKS COMMENTS B05.130.012 1NC24-08 CN-i NC-024 ^^ UT SS-CS 27.500 Inlet Nozzle B 67 Degrees Loop A Circumferential NC CN-1553-1.0 2.200 UT From Nozzle Side Class A Term end To Be Done With B05.010.001 Dissimilar *NavShips Test Block S/N 045202 "Use WesDyne Procedure PDI-ISI-254-SE 605.130.012A 1NC24-08 CN-1NC-024 UT SS-CS 27.500 ^ Inlet Nozzle B 67 Degrees Loop A Circumferential NC CN-1553-1.0 2.200 UT From Pipe Side Class A Term end To Be Done With B05.010.001A Dissimilar *NavShips Test Block SIN 045202 "Use WesDyne Procedure PDI-ISI-254-SE B05.130.012B 1NC24-08 CN-1NC-024 NDE-35 PT SS-CS 27.500 Inlet Nozzle B 67 Degrees Loop A Circumferential NC CN-1553-1.0 2.200 To Be Done With B05.010.001B Class A Term end Dissimilar 605.130.013 1NC25-01 CN-1NC-025 UT SS-CS 29.000 ^ Outlet Nozzle E 202 Degrees Loop C Circumferential NC CN- 1553-1.0 2.300 UT From Nozzle Side Class A Term end To Be Done With B05.010.007 Dissimilar Ref. Request For Relief Serial Number 93-02 Ref. Request for Relief Serial Number 94-05

^NavShips Test Block SIN 045202 "Use WesDyne Procedure PDI-ISI-254-SE B05.130.013A 1NC25-01 CN-1 NCO025 ** UT SS-CS 29.000 Outlet Nozzle E 202 Degrees Loop C Circumferential NC CN-1553-1.0 2.300 UT From Pipe Side Class A Term end To Be Done With B05.010.007A Dissimilar Ref. Request For Relief Serial Number 93-02 Ref. Request for Relief Serial Number 94-05

^NavShips Test Block S/N 045202

• • Use WesDyne Procedure PDI-ISI-254-SE oe n n1 *^ I I M. EE-n ^ A e ^ I kLI.I-n- I- ^A- n I - rS Ova. i JU. I0 I 'NL0UZ o %iP4, I P,4LiU0 UI 001%00 r I.U U IiIUl i'ULZt1 r C4' UeUgreU LVUp Li Circumferential NC CN-1553-1.0 2.200 UT From Nozzle Side Class A Term end To be Done With B05.010.003

^NavShips Test Block S/N 045202 Dissimilar

"*UseWesDyne Procedure PDI-ISI-254-SE

EOC 15 ( (

DUKE ENERGY_'-,RPORATION CATEGORY B-F, Pressure Retaining Dissimilar INSERVICE INSPECTION PLAN MANAGEMENT Metal Welds Inservice Inspection Database Management System Plan Report PpiDn~q Catawba 1 Page 20 N- Inservice Inspection Plan for Interval 2 Outag e7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MATISCH DIA/THK CAL BLOCKS COMMENTS B05.130.016A 1NC25-08 CN-INC-025

• UT SS-CS 27.500

• Inlet Nozzle F 247 Degrees Loop C Circumferential NC CN-1553-1.0 2.200 UT From Pipe Side Class A Term end To be Done With B05.010.003A Dissimilar *NavShips Test Block S/N 045202

• • Use WesDyne Procedure PDI ISI-254-SE B05.130.016B 1NC25-08 CN-1 NC-025 NDE-35 PT SS-CS 27.500 Inlet Nozzle F 247 Degrees Loop C Circumferential NC CN-1 553-1.0 2.200 To be Done With B05.010.003B Class A Term end Dissimilar Total B05.130 Items: 20 Total B05 Items: 44

C EOC 15 CATEGORY B-G-1, Pressure Retaining Bolting.

DUKE ENERG(

DUKEk.

ENEGAPORATION INSERVICE INSPECTION PLAN MANAGEMENT 72T Greater than 2" In Diameter Inservice Inspection Database Management System Plan Report Steam Generators Catawba 1 Page 21 N Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

'** Nuts, Bushings, and Washers ****

B06.110.007 ISGD-MW-Y1-X2 CNM 1201.01-580 OAL-13 VT-1 CS 0.000 SG1D Manway Nuts (20)

NC 0.000 Primary Manway in Y1-X2 Quadrant (Inlet Side)

Class A 806.110.008 1SGD-MW-X2-Y2 CNM 1201.01-580 OAL-13 VT-1 CS 0.000 SG1D Manway Nuts (20)

NC 0.000 Primary Manway In X2-Y2 Quadrant (Outlet Side)

Class A Total B06.110 Items: 2 Total B06 Items: 2

EOC 15 (DUKE CATEGORY B-G-2, Pressure Retaininq Bolting.

ENERGL tCPORATION INSERVICE INSPECTION PLAN MANAGEMENT

(

2" And Less In Diameter Inservice Inspection Database Management System Plan Report Catawba I Page 22 I k Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• t-t Bolts, Studs, and Nuts ****

B07.050.056 INV614-MJ1 CN-1NV-614 OAL-13 VT-t CS 1.000 Flange Bolting NV CN-1554-1.5 5.750 4 Studs,8 Nuts Class A 807.050.057 1NV615-MJ1 CN-1NV-615 QAL-13 VT-1 CS 1.000 Flange Bolting NV CN 1554-1.5 7.250 8 Studs,16 Nuts Class A Total B07.050 Items: 2

EOC 15 (DUKE ENERG RPORATION

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CATEGORY B-G-2, Pressure Retaining Bolting. INSERVICE INSPECTION PLAN MANAGEMENT 2" And Less In Diameter Inservice Inspection Database Management System Plan Report Valves Catawba I Page 23 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS

• • • • Bolts, Studs, and Nuts ****

B07.070.023 1NI-125 CN-1 NI-240 QAL-13 VT-1 SS 1.250 8' Valve NI CNM 1205.00-059 0.000 16 Studs,16 Nuts Class A B07.070.024 INI-126 CN-INI-241 OAL-13 VT-1 SS 1.250 6' Valve NI CNM 1205.00-063 0.000 16 Studs,16 Nuts Class A Total B07.070 Items: 2 Total B07 Items: 4

EOC 15 CATEGORY B-J, Pressure Retaining Welds In DUKE ENERG$II APORATION INSERVICE INSPECTION PLAN MANAGEMENT

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Piping Inservice Inspection Database Management System Plan Report NPS 4 or Larger Catawba 1 Page 24 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIAJTHK CAL BLOCKS COMMENTS

• ^* Circumferential Welds B09.011.020 1NC30-2 CN-1NC-30 NDE-600 UT SS 6.000 Reference General Requirments Section 8.1.10 Circumferential NC CN-1553-1.0 160 0.719 50211 Depending on the examiners qualifications, Class A Pipe to Procedure PDI-UT-2 may be used in lieu of Elbow NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

B09.011.020A 1NC30-2 CN-1NC-30 NDE-35 PT Ss 6.000 Circumferential NC CN-1553-1.0 160 0.719 Class A Pipe to Elbow B09.011.021 1NC30-3 CN-1NC-30 NDE.600 UT SS 6.000 Reference General Requirments Section 8.1.10 Circumferential NC CN-1553-1.0 160 0.719 50211 Depending on the examiners qualifications, Class A Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

B09.011.021A 1NC30-3 CN-1NC-30 NDE-35 PT Ss 6.000 Circumferential NC CN-1553-1.0 160 0.719 Class A Elbow to Pipe B09.011.024 1NC32-2 CN-1NC-32 NDE-600 UT SS 10.000 *Reference General Requirments Section 8.1.10 Circumferential NC CN-1553-1.0 140 1.000 50209 Depending on the examiners qualifications, Class A Pipe to Procedure PDI-UT-2 may be used Inlieu of Elbow NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

B09.011.024A 1NC32-2 CN-1NC-32 NDE-35 PT SS 10.000 Circumferential NC CN-1553-1.0 140 1.000 Class A Pipe to Elbow B09.011.025 1NC32-3 CN-1NC-32 NDE-600 UT SS 10.000 Reference General Requirments Section 8.1.10 Circumferential NC CN-1553-1.0 140 1.000 50209 Depending on the examiner's qualifications, Class A Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

EOC 15 ( DUKE ENERGY-. jRPORATION c CATEGORY B-J. Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Piping Inservice Inspection Database Management System Plan Report WNPS 4 or Larger Catawba 1 Page 25 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISOIDWG NUMBERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS B09.011.025A 1NC32-3 CN-iNC-32 NDE-35 PT SS 10.000 Circumferential NC CN-1553-1.0 140 1.000 Class A Elbow to Pipe B09.011.026 1NC32-4 CN-INC-32 NDE-600 UT SS 10.000

• Reference General Requirments Section 8.1.10 Circumferential NC CN- 553-1.0 140 1.000 50209 Depending on the examinees qualifications, Class A Pipe to Procedure PDI-UT-2 may be used In lieu of Elbow NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

B09.011.026A 1NC32-4 CN-1 NC-32 NDE-35 PT SS 10.000 Circumferential NC CN-1553-1.0 140 1.000 Class A Pipe to Elbow 809.011.027 1NC32-6 CN-INC-32 NDE-600 UT SS 10.000 Reference General Requirments Section 8.1.10 Circumferential NC CN-1553-1.0 140 1.000 50209 Depending on the examiners qualifications, Class A Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

B09.011.027A 1NC32-6 CN-1NC-32 NDE-35 PT Ss 10.000 Circumferential NC CN-1553-1.0 140 1.000 Class A Elbow to Pipe B09.011.048 1NC286-1 CN-1NC-286 NDE-600 UT SS 6.000

• Reference General Requirments Section 8.1.10 Circumferential NC CN-1553-1.0 XXS 0.864 50281 Depending on the examineres qualifications, Class A UHI Adapter to Procedure PDI-UT-2 may be used in lieu of Pipe Cap NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

809.011.048A 1NC286-1 CN-i NC-286 NDE-35 PT Ss 6.000 Circumferential NC CN-1553-1.0 XXS 0.864 Class A UHI Adapter to Pipe Cap B09.011.156 1N132-3 CN- NI-32 NDE-600 UT SS 8.000 Reference General Reauirments Section 8.1.10 Circumferential NI CN-1562-1.2 160 0.906 50311 Depending on the examineres qualifications, Class A Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

EOC 15

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CATEGORY B-J, Pressure Retaining Welds In DUKE ENERGC ,RPORATION INSERVICE INSPECTION PLAN MANAGEMENT Piping Inservice Inspection Database Management System Plan Report NPS 4 or Larger Catawba 1 Page 26 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS B09.011.156A 1Nl32-3 CN-1 NI-32 NDE-35 PT SS 8.000 Circumferential NI CN-1562-1.2 160 0.906 Class A Elbow to Pipe B09.011.157 1N132-4 CN-1NI-32 NDE-600 UT SS 8.000 ^ Reference General Requirments Section 8.1.10 Circumferential NI CN-1562-1.2 160 0.906 50311 Depending on the examiners qualifications, Class A Pipe to Procedure PDI-UT-2 may be used Inlieu of Elbow NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

B09.011.157A 1N132-4 CN-1NI-32 NDE-35 PT SS 8.000 Circumferential NI CN-1562-1.2 160 0.906 Class A Pipe to Elbow B09.011.158 1N132-5 CN-1NI-32 NDE-600 UT SS 8.000

• Reference General Requirments Section 8.1.10 Circumferential NI CN-1562-1.2 160 0.906 50311 Depending on the examiners qualifications, Class A Elbow to Procedure PDI-UT-2 may be used in lieu of Pipe NDE.600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

B09.011.158A 1N132-5 CN-1NI-32 NDE-35 PT SS 8.000 Circumferential NI CN-1562-1.2 160 0.906 Class A Elbow to Pipe B09.011.192 1N1240-8 CN-1NI-240 NDE-600 UT SS 8.000

• Reference General Requirments Section 8.1.10 Circumferential NI CN-1562-1.2 160 0.906 50311 Depending on the examiners qualifications, Class A Pipe to Procedure PDI-UT-2 may be used In lieu of Elbow NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

B09.011.192A 1NI240-8 CN-1NI-240 NDE-35 PT SS 8.000 Circumferential NI CN-1562-1.2 160 0.906 Class A Pipe to Elbow B09.011.193 1N1240-10 CN-1NI-240 NDE-600 UT SS 8.000 *

• Reference General Requirments Section 8.1.10 Circumferential NI CN-1562-1.2 160 0.906 50311 Depending on the examineres qualifications, Class A Pipe to Procedure PDI-UT-2 may be used In lieu of Elbow NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

EOC 15

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CATEGORY B-J, Pressure Retaining Welds In DUKE ENERGC( oRPORATION INSERVICE INSPECTION PLAN MANAGEMENT Piping Inservice Inspection Database Management System Plan Report NPS 4 or Larger Catawba 1 Page 27 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER IDNUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS B09.011.193A 1N1240-10 CN-1NI-240 NDE-35 PT SS 8.000 Circumferential Ni CN-1562-1.2 160 0.906 Class A Pipe to Elbow B09.011.194 1NI240-11 CN-1NI-240 NDE-600 UT SS 8.000 Reference General Requirments Section 8.1.10 Circumferential NI CN-1562-1.2 160 0.906 50311 Depending on the examiner's qualificatIons, Class A Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

B09.011.194A 1N1240-11 CN-1NI-240 NDE-35 PT SS 8.000 Circumferential NI CN-1562-1.2 160 0.906 Class A Elbow to Pipe Total B09.011 Items: 26

EOC 15 ( DUKE ENERG. ,APORATION CATEGORY B6J, Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Piping Inservice Inspection Database Management System Plan Report Less Than NPS 4 Catawba 1 Page 28 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUIME3ERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Circumferential Welds

• B09.021.001 1NC22-12 CN-1 NC-22 NDE-35 PT SS 3.000 Circumferential NC CN-1 553-1.0 0.438 Class A Nozzle to Cap B09.021.002 1NC22-16 CN-1NC-22 NDE-35 PT SS 2.000 Circumferential NC CN-1553-1.0 0.344 Class A Pipe to Cap B09.021.009 1NC41-15 CN-1NC-41 NDE-35 PT SS 2.000 Circumferential NC CN-1553-1.0 160 0.344 Class A Pipe to Pipe B09.021.010 1NC42-1 CN-1NC-42 NDE-35 PT SS 1.500 Circumferential NC CN-1553-1.0 160 0.281 Class A Stress weld Nozzle to Pipe B09.021.011 1NC43-11 CN-1 NC-43 NDE-35 PT SS 1.500 Circumferential NC CN-1553-1.0 160 0.281 Class A Stress weld Nozzle to Pipe B09.021.012 1NC50-25 CN-1NC-50 NDE-35 PT SS 2.000 Circumferential NC CN-1553-1.0 160 0.344 Class A Pipe to Pipe B09.021.013 1NC50-26 CN- NC.50 NDE-35 PT SS 2.000 Circumferential NC CN-1553-1.0 160 0.344 Class A Pipe to Pipe B09.021.014 INC51-1 CN-1NC-51 NDE-35 PT SS 1.500 Circumferential NC CN-1553-1.0 160 0.281 Class A Stress weld Nozzle to Pipe

EOC 15 CATEGORY B-J, Pressure Retaining Welds In DUKE ENERG .,RPORATION C(

INSERVICE INSPECTION PLAN MANAGEMENT Piping Inservice Inspection Database Management System Plan Report Less Than NPS 4 Catawba 1 Page 29 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS B09.021.015 1NC56-1 CN-1 NC-56 NDE-35 PT SS 3.000 Circumferential NC CN-1 553-1.0 160 0.438 Class A Stress weld Valve 1NV-34 to Pipe B09.021.103 1NV310-1 CN-1NV-310 NDE-35 PT SS 3.000 Circumferential NV CN-1 554-1.0 160 0.438 Class A Stress weld Valve 1NV33 to Pipe B09.021.104 1NV310-2 CN-1NV-310 NDE-35 PT SS 3.000 Circumferential NV CN-1554-1.0 160 0.438 Class A Stress weld Pipe to Valve 1NV34 Total B09.021 Items: 11

EOC 15 ( DUKE ENERG, APORATION CATEGORY B-J, Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Pipinq Inservice Inspection Database Management System Plan Report

• Branch Plpe Connection Welds Catawba 1 Page 30 Inservice Inspectlon Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER IDNUMBER SYS ISOIDWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • NPS 4 or Larger ****

B09.031.002 1NC22-WN8 CN- INC-22 NDE-830 UT SS 29.500 50214 Reference RFR 04-CN-001 Branch NC CN-1553-1.0 140 2.200 Class A Branch to Pipe B09.031.002A 1NC22-WN8 CN-1NC-22 NDE-35 PT SS 29.500 Branch NC CN- 1553-1.0 140 2.200 Class A Branch to Pipe Total B09.031 Items: 2

• • • • Less Than NPS 4 ****

B09.032.051 1NI10-2 CN-1NI-10 NDE-35 PT SS 2.000 Branch NI CN-1562-1.3 160 0.344 Class A Pipe to Special Weld Branch B09.032.052 1NI147-3 CN-INI-147 NDE-35 PT SS 2.000 Branch NI CN-1562-1.3 160 0.344 Class A Pipe to Special Weld Branch Total B09.032 Items: 2

EOC 15

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CATEGORY B-J, Pressure Retaining Welds In DUKE ENERG(.jRPORATION INSERVICE INSPECTION PLAN MANAGEMENT C.

Piping Inservice Inspection Database Management System Plan Report Soeket Welds Catawba 1 Page 31 Inservice Inspection Plan for Interval 2 Outage 7 0810412005 ITEM NUMBER IDNUMBER SYS ISO/DWG NUMBERS PROC INSP REO MAT/SCH DIA1THK CAL BLOCKS COMMENTS

• • • • Socket ***

B09.040.001 1NC24-12 CN-1NC-24 NDE-35 PT SS 2.000 Socket NC CN-1553-1.0 160 0.344 Class A Welding Boss (Nozzle) to Inst. 1NCRD5440 B09.040.002 1NC41-36 CN-1NC-41 NDE-35 PT SS 2.000 Socket NC CN-1553-1.0 160 0.344 Class A Tee to Coupling Rest.

B09.040.003 1NC41-37 CN-1NC-41 NDE-35 PT SS 2.000 Socket NC CN-1553-1.0 160 0.344 Class A Tee to Pipe B09.040.004 1NC41-35 CN-1NC-41 NDE-35 PT SS 2.000 Socket NC CN-1553-1.0 160 0.344 Class A Tee to Pipe B09.040.005 1NC42-5 CN-1NC-42 NDE-35 PT SS 1.500 Socket NC CN-1553-1.0 160 0.281 Class A Elbow to Pipe B09.040.006 1NC43-8 CN-1 NC-43 NDE-35 PT SS 1.500 Socket NC CN-1553-1.0 160 0.281 Class A Pipe to Reducing Insert B09.040.007 1NC50-6 CN-1 NC-50 NDE-35 PT SS 2.000 Socket NC CN-1553-1.0 160 0.344 Class A Pipe to Tee B09.040.008 1NC50-29 CN-1NC-50 NDE-35 PT SS 2.000 Socket NC CN-1553-1.0 160 0.344 Class A Pipe to Elbow

EOC 15 C C, DUKE ENERG$.,APORATION CATEGORY B-J. Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Piping Inservice Inspection Database Management System Plan Report Socket Welds Catawba 1 Page 32 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS 809.040.009 1NC50-30 CN-1 NC.50 NDE-35 PT SS 2.000 Socket NC CN-1553-1.0 160 0.344 Class A Elbow to Pipe B09.040.010 1NC51-2 CN-1NC-51 NDE-35 PT SS 1.500 Socket NC CN-1553-1.0 160 0.281 Class A Pipe to Elbow B09.040.011 1NC81-21 CN-1NC-81 NDE-35 PT SS 2.000 Socket NC CN-1553-1.0 160 0.344 Class A Pipe to Tee B09.040.012 1NC82-5 CN-1NC-82 NDE-35 PT SS 1.500 Socket NC CN-1553-1.0 160 0.281 Class A Elbow to Pipe B09.040.022 1NC245-9 CN-1 NC-245 NDE-35 PT SS 2.000 (This weld was added to Outage #7 (EOC1 5) to Circumferential NC CN-1553-1.1 160 0.344 adjust the NC System Summary for Inservice Class A Reducing Insert to Inspection Category B-J. as a result of the Reducer Coupling re-classification of this weld).

B09.040.067 1N1240.4 CN-1 NI-240 NDE-35 PT SS 2.000 Socket NI CN-1562-1.2 160 0.344 Class A Branch to Pipe 809.040.068 1N1240-6 CN-1 NI-240 NDE-35 PT SS 2.000 Socket NI CN-1562-1.2 160 0.344 Class A Elbow to Pipe B09.040.069 1N1243- 1 CN.1NI.243 NDE-35 PT SS 2.000 Socket NI CN-1562-1.0 160 0.344 Class A Reducer to Valve 1NI 15 B09.040.070 1N1245-3 CN-1 NI-245 NDE-35 PT SS 1.500 Socket NI CN-1562-1.0 160 0.281 Class A Reducer to Pipe

EOC 15 DUKE ENERGC APORATION CATEGORY B-J. Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Piping Inservice Inspection Database Management System Plan Report ESocket Welds Catawba 1 Page 33 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISOIDWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS B09.040.071 1N1247-7 CN-1NI-247 NDE-35 PT SS 1.500 Socket NI CN-1562-1.0 160 0.281 Class A Reducer to Pipe B09.040.108 1NV483-3 CN-1NV-483 NDE-35 PT SS 2.000 Socket NV CN-1554-1.5 160 0.344 Class A Flange MJ-1 to Pipe B09.040.109 1NV483-7 CN-1NV-483 NDE-35 PT SS 2.000 Socket NV CN-1554-1.5 160 0.344 Class A Elbow to Pipe B09.040.110 1NV483-8 CN-1NV-483 NDE-35 PT SS 2.000 Socket NV CN-1554-1.5 160 0.344 Class A Pipe to Elbow B09.040.111 1NV483-9 CN-1NV-483 NDE-35 PT SS 2.000 Socket NV CN-1554-1.5 160 0.344 Class A Elbow to Pipe B09.040.112 1NV483-14 CN-1NV-483 NDE-35 PT SS 2.000 Socket NV CN-1554-1.5 160 0.344 Class A Pipe to Elbow Total B09.040 Items: 23 Total B09 Items: 64

EOC 15 ( DUKE ENERG( APORATION C

CATEGORY B-M-1, Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Valve Bodies Inservice Inspection Database Management System Plan Report Evalves Catawba 1 Page 34 N Inservice Inspection Plan for Interval 2 Outage 7 0810412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REC MAT/SCH DIAtTHK CAL BLOCKS COMMENTS

• • • • NPS 4 or Larger; Valve Body Welds ****

B12.040.002D 1ND-37A CN-1ND-037 NDE-630 UT SS 20.000 50354 Factory Weld- Valve Body to Bonnett.lnspect one of Circumferential ND CNM 1205.0-262 2.043 the foffowing(1ND-1B1,2A, Class A 36B,or 37A)

Total 912.040 Items: 1

EOC 15 (

DUKE ENERGV.. ,RPORATION

,C CATEGORY B-M-2. Valve Bodies INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report EValves Catawba 1 Page 35 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER Si?S ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Valve Body, Exceeding NPS 4 ****

B12.050.002B 1NC-29 CN-1NC-044 OAL-14 VT-3 SS 6.000 Inspect one of the following(1NC27,or 29)

NC CNM 1205.06-41 0.719 if disassembled Class A B12.050.007E INI-175 CN-1NI-147 OAL-14 VT-3 SS 6.000 Inspect one of the NI CNM 1205.00-63 0.719 followlng(1NI-126,134,157,160,175,176,180 or 181)

Class A if disassembled Total B12.050 Items: 2 Total B12 Items: 3

EOC 15 (

DUKE ENERG& .4PORATION CATEGORY B-N-1, Interior of Reactor Vessel INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report Reactor Vessel Catawba 1 Page 36 Inservice Inspection Plan for Interval 2 Outage 7 0810412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIANTHK CAL BLOCKS COMMENTS Vessel Interior

• B13.010.001 1RPV-INTERIOR CNM 1201.01-32

• VT-3 SS 0.000 Area Above and Below Core Made Accessible NC 0.000 During Normal Refueling Outages Class A *Use WesDyne Procedure WDI-STD-088 Total B13.010 Items: 1

EOC 15 t¢ ECATGR DUKE ENERGLRPORATION CATEGORY B-N-2. Integral Welded Core Support INSERVICE INSPECTION PLAN MANAGEMENT Structures And Interior Attach of RV Inservice Inspection Database Management System Plan Report Reactor Vessel (PWR Catawba 1 Page 37

• Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH D1A/THK CAL BLOCKS COMMENTS

• • • • Interior Attachments Beyond Beltline Region ***

B13.060.001 IRPV-CLEVIS CNM 1201.01-52/4 VT-3 SS 0.000 6 Clevis Located at 60 Degree Intervals in Lower 0.000 Shell Class A 'Use WesDyne Procedure WDI-STD-088 813.060.002 IRPV INCORE CNM 1201.01-52/2

• VT-3 SS 0.000 58 Incore Instrumentation Nozzles Located In Lower 0.000 Head Class A 'Use WesDyne Procedure WDI-STD-088 Total B13.060 Items: 2

EOC 15 (7 DUKE ENERG$ ARPORATION C, CATEGORY B-N-3, Removable Core Support INSERVICE INSPECTION PLAN MANAGEMENT Structures Inservice Inspection Database Management System Plan Report Reactor Vessel (PWR) Catawba 1 Page 38 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER IDNUMBER SYS ISO/DWG NIUMBERS PROC INSP REQ MAT/SCH DIANTHK CAL BLOCKS COMMENTS

• • • • Core Support Structure ****

B13.070.001 1RPV-CORE-SUP CNM 1201.01-32 VT-3 Ss 0.000 Examine When Stucture IsRemoved From Reactor 0.000 Vessel Class A *Use WesDyne Procedure WDI-STD-088 Total B13.070 Items: 1 Total B13 Items: 4

EOC 15 (

CATEGORY B-O, Pressure Retaining Welds In DUKE ENERG ,.RPORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Control Rod Housincs Inservice Inspection Database Management System Plan Report IReactor Vessel Catawba 1 Page 39 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISOtDWG NUI VIE3ERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS t*** Welds in CRD Housing

• 814.010.001 1RPV-CRDM64 CNM 1201.01-5217 NDE-35 PT SS-lnconel 4.000 CRD Housing Weld (Peripheral) First Interval 0.642 Item Number B14.010.010 Class A B14.010.002 1RPV-CRDM72 CNM 1201.01-52/7 NDE-35 PT SS-Inconel 4.000 CRD Housing Weld (Peripheral) First Interval 0.642 Item Number B14.010.018 Class A B14.010.003 1RPV-CRDM77 CNM 1201.01-52/7 NDE-35 PT SS-inconel 4.000 CRD Housing Weld (Peripheral) First Interval 0.642 Item Number B14.010.023 Class A Total B14.010 Items: 3 Total B14 Items: 3

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EOC 15 CATEGORY C-A, Pressure Retaining Welds In DUKE ENERG' _RPORATION INSERVICE INSPECTION PLAN MANAGEMENT C.

Pressure Vessels Inservice Inspection Database Management System Plan Report

• Head Circumferential Welds Catawba 1 Page 40 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER IDNUMBER SYS ISO(DWG NU?vIBERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS

• • • • Circumferential ****

C01.020.013 1SGD-W144 CNM-1201.01-610 NDE-640 UT CS 0.000 5139385 Steam Generator 1D Steam Drum Shell to Steam Circumferential NC CNM-1201.01.617 NDE-820 4.125 Drum Head Class B Shell to Head Total C01.020 Items: 1 Total C01 Items: 1

EOC 15 IQ DUKE ENERGC.JAPORATION ( '

CATEGORY C-B, Pressure Retaining Nozzle INSERVICE INSPECTION PLAN MANAGEMENT Welds In Vessels Inservice Inspection Database Management System Plan Report ENozzles Without Reinforcing Plate In Vessels > Catawba 1 Page 41 08104/2005 M1/2 In. Nom. Thickness Inservice Inspection Plan for Interval 2 Outage 7 ITEM NUMBER IDNUMBER SYS ISO/DWG fNUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS Nozzle-to-Shell (or Head) Weld C02.021.004 1ANSHX-3-N1 CN-1 563-1.0 NDE-630 UT SS 12.000 50380 Containment Spray Heat Exchanger 1A Inlet Nozzle Circumferential NS CNM 1201.06-90 0.500 to Channel Pc.3 to Pc.N1 Class B CNM 2201.06-2 Inlet Nozzle to The NDE for this Item Number will not be performed Channel during Outage #7(EOC15), per NSM# CN-11432101 (1A NS Heat Exchanger Replacement).

C02.021.004A IANSHX-3-N1 CN-1563-1.0 NDE-35 PT SS 12.000 Containment Spray Heat Exchanger 1A Inlet Nozzle Circumferential NS CNM 1201.06-90 0.500 to Channel Pc.3 to Pc.N1 Class B CNM 2201.06-2 Inlet Nozzle to The NDE for this Item Number will not be performed Channel during Outage #7 (EOC15), per NSM# CN-1 1432/01 (IA NS Heat Exchanger Replacement).

C02.021.005 1ANSHX-3-N2 CN-1563-1.0 NDE-630 UT Ss 12.000 50380 Containment Spray Heat Exchanger 1A Outlet Circumferential NS CNM 1201.06-90 0.500 Nozzle to Channel Pc.3 to Pc.N2 Class B CNM 2201.06-2 Outlet Nozzle to The NDE for this Item Number will not be performed Channel during Outage #7 (EOC15), per NSM# CN-I 1432101 (1A NS Heat Exchanger Replacement).

C02.021.005A 1ANSHX-3-N2 CN-1563-1.0 NDE-35 PT SS 12.000 Containment Spray Heat Exchanger 1A Outlet Circumferential NS CNM 1201.06-90 0.500 Nozzle to Channel Pc.3 to Pc.N2 Class B CNM 2201.06-2 Outlet Nozzle to The NDE for this Item Number will not be performed Channel during Outage #7 (EOC15), per NSM# CN-1 1432/01 (IA NS Heat Exchanger Replacement).

Total C02.021 Items: 4 Total C02 Items: 4

EOC 15 (

CATEGORY C-C. Integral Attachments For DUKE ENERG$IIAPORATION C.

INSERVICE INSPECTION PLAN MANAGEMENT Vessels, Piping, Pumps, And Valves Inservice Inspection Database Management System Plan Report Catawba 1 Page 42 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUME3ERS PROC INSP REQ MATISCH DIAITHK CAL BLOCKS COMMENTS

• • • • Integrally Welded Attachments ****

G03.020.010 1-R-FW-0002 CN-1492-FW0OI NDE-35 PT SS 24.000 Welded Attachment Rigid Support FW CN-1571-1.0 0.750 Class B C03.020.015 1-R-ND-0165 CN-1492-ND011 NDE-35 PT SS 14.000 Welded Attachment Rigid Support ND CN-1561-1.1 1.000 Class B C03.020.025 1-R-NI-0285 CN-1492-NI009 NDE-35 PT SS 4.000 Welded Attachment Rigid Support NI CN-1 562-1.2 0.750 Class B C03.020.026 1-R-NI-0286 CN-1492-NI006 NDE-35 PT SS 2.000 Welded Attachment Rigid Support NI CN-1562-1.2 0.750 Class B C03.020.027 1-R-NI-1195 CN-1491-NI055 NDE-35 PT SS 6.000 Welded Attachment Rigid Support NI CN-1562-1.3 0.906 Class B C03.020.052 1-R-NV-0433 CN-1492-NV054 NDE-35 PT SS 3.000 Welded Attachment Rigid Support NV CN-1554-1.2 0.750 Class B C03.020.094 1-R-SM-1008 CN-1491-SM003 NDE-25 MT CS 34.000 Welded Attachment Rigid Support SM CN-ISIN-1593-1.0 NDE-35 0.750 6 Lugs - Pc. 4 and Pc. 5 (1.50 inches thick), Pc. 8 Class B and Pc. 9 (2 inches thick), and Pc. 10 and Pc. 11 (1 Inch thick).

PT may be used in conjunction with MT.

C03.020.095 1-R-SM-1018 CN-1491-SM002 NDE-25 MT CS 34.000 Welded Attachment Rigid Support SM CN-ISIN-1593-1.0 NDE-35 0.750 6 Lugs - Pc. 4 and Pc. 5 (1.50 inches thick), Pc. 8 Class B and Pc. 9 (2 Inches thick), and Pc. 10 and Pc. 11 (1 inch thick).

PT may be used in conjunction with MT.

EOC 15

(..,

CATEGORY C-C, Integral Attachments For DUKE ENERG4IJCPORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Vessels, Piping, Pumps, And Valves Inservice Inspection Database Management System Plan Report Catawba 1 Page 43 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIAMTHK CAL BLOCKS COMMENTS C03.020.096 1-R-SM-1028 CN-1491-SMOO1 NDE-25 MT CS 34.000 Welded Attachment Rigid Support SM CN-ISIN-1593-1.0 NDE-35 0.750 6 Lugs - Pc. 4 and Pc. 5 (1.50 Inches thick), Pc. 8 Class B and Pc. 9 (2inches thick), and Pc. 10 and Pc. 11 (1 Inch thick).

PT may be used In conjunction with MT.

C03.020.097 1-R-SM-1038 CN-1491-SM004 NDE-25 MT CS 34.000 Welded Attachment Rigid Support SM CN-ISIN-1593-1.0 NDE-35 0.750 6 Lugs - Pc. 4 and Pc. 5 (1.50 inches thick), Pc. 8 Class B and Pc. 9 (2 inches thick), and Pc. 10 and Pc. 11 (1 Inch thick).

PT may be used in conjunction with MT.

Total C03.020 Items: 10

EOC 15 (

CATEGORY C-C, Integral Attachments For DUKE ENERG(- JRPORATION C INSERVICE INSPECTION PLAN MANAGEMENT Vessels, Plping, Pumps, And Valves Inservice Inspection Database Management System Plan Report E valves Catawba 1 Page 44 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS

• • • • Integrally Welded Attachments ****

C03.040.001 1-R-SV-1519 CN-1491-SV005 NDE-25 MT CS 0.000 Lug to Valve Rigid Support SV CN-ISIN-1593-1.0 1.000 Class B Lug to Valve C03.040.002 1-R-SV-1 612 CN-1491-SV005 NDE-25 MT CS 0.000 Support 1-R-SV-1612 to Forged Bracket on Valve Rigid Support SV CN-ISIN-1593-1.0 1.000 Body Class B Support to Forged Bracket C03.040.003 1-R-SV-1512 CN-1491-SVO06 NDE-25 MT CS 0.000 Lug to Valve Rigid Support SV CN-ISIN-1593-1.0 1.000 Class B Lug to Valve C03.040.004 1-R-SV-1616 CN-1491-SV006 NDE-25 MT CS 0.000 Support 1-R-SV-1616 to Forged Bracket on Valve Rigid Support SV CN-ISIN-1593-1.0 1.000 Body Class B Support to Forged Bracket C03.040.005 1-R-SV-1505 CN-1491-SVO07 NDE-25 MT CS 0.000 Lug to Valve Rigid Support SV CN.ISIN-1593-1.0 1.000 Class B Lug to Valve C03.040.006 1-R-SV-1610 CN-1491-SV007 NDE-25 MT CS 0.000 Support 1-R-SV.1610 to Forged Bracket on Valve Rigid Support SV CN-ISIN-1593-1.0 1.000 Body Class B Support to Forged Bracket C03.040.007 1-R-SV-1526 CN-1491-SV008 NDE-25 MT CS 0.000 Lug to Valve Rigid Support SV CN-ISIN-1593-1.0 1.000 Class B Lug to Valve C03.040.008 1-R-SV-1608 CN-1491-SV008 NDE-25 MT CS 0.000 Support 1 R-SV-1 608 to Forged Bracket on Valve Rigid Support SV CN-ISIN-1593-1.0 1.000 Body Class B Support to Forged Bracket Total C03.040 Items: 8 Total C03 Items: 18

EOC 15 (

DUKE ENERGYN. ,RPORATION CATEGORY C-F-i. Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Austenitic SS or High Alloy Piping Inservice Inspection Database Management System Plan Report PIDInW Welds >= 3/8 In. Nominal Wall Thickness Catawba 1 Page 45 nor Pipinq > NPS 4 Inservice Inspection Plan for Interval 2 Outagi 08104/2005 ITEM NUMBER IDNUMBER SYS ISOIDWG NUMBERS PROC INSP REQ MAT(SCH DIA/THK CAALBLOCKS COMMENTS

'* Circumferential Weld

• C05.01 1.039 1ND13-1 CN-1ND-13 NDE-600 UT SS 14.000 ^ Residual Heat Removal Pump 1B ^Reference Circumferential ND CN-1561-1.1 40 0.438 50314 General Requirements Section 8.1.10 Class B Term end ND PUMP 1Bto Depending on the examineres qualifications, Flange Procedure PDI-UT-2 may be used Inlieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.011.039A 1ND13-1 CNA1ND-13 NDE-35 PT SS 14.000 Residual Heat Removal Pump 1B Circumferential ND CN-1561-1.1 40 0.438 Class B Term end ND PUMP 1B to Flange C05.011.040 1ND13-5 CN-1ND-13 NDE-600 UT SS 14.000 *

• Reference General Requirments Section 8.1.10 Circumferential ND CN-1561-1.1, 40 0.438 50314 Depending on the examiners qualifications, Class B Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.011.040A 1ND13-5 CN-1ND-13 NDE-35 PT SS 14.000 Circumferential ND CN-1561-1.1 40 0.438 Class B Elbow to Pipe C05.01 1.041 1ND13-11 CNA1ND-13 NDE-600 UT SS 14.000 * *Reference General Requirments Section 8.1.10 Circumferential ND CN-1561-1.1 40 0.438 50314 Depending on the examiners qualifications, Class B Elbow to Procedure PDI-UT-2 may be used Inlieu of Pipe NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

C05.011.041A 1ND13-11 CN-1ND-13 NDE-35 PT SS 14.000 Circumferential ND CN-1561-1.1 40 0.438 Class B Elbow to Pipe C05.011.042 1ND14-1 CNA1ND-14 NDE.600 UT SS 14.000 * ^ Reference General Requirments Section 8.1.10 Circumferential ND CN.1561-1.1 40 0.438 50314 Depending on the examiners qualifications, Class B Pipe to Procedure PDI-UT-2 may be used Inlieu of Elbow NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used. p

EOC 15 C CATEGORY C-F-1. Pressure Retaining Welds In DUKE ENERG iQPORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Austenittc SS or High Alloy Piping Inservice Inspection Database Management System Plan Report WP vWna Welds >= 3/8 In. Nominal Wall Thickness Catawba 1 Page 46 for Piping > NPS 4 Inservice Inspection Plan for Interval 2 Outag ae7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIAJTHK CAL BLOCKS COMMENTS C05.011.042A 1ND14-1 CN-1ND-14 NDE-35 PT SS 14.000 Circumferential ND CN-1561-1.1 40 0.438 Class B Pipe to Elbow C05.011.043 1ND14-7 CN-1ND-14 NDE-600 UT SS 14.000 ^ Reference General Requirments Section 8.1.10 Circumferential ND CN-1561-1.1 40 0.438 50314 Depending on the examiners qualifications, Class B Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.011.043A 1ND14-7 CN-1ND-14 NDE-35 PT SS 14.000 Circumferential ND CN-1561-1.1 40 0.438 Class B Elbow to Pipe C05.011.044 1ND14-8 CN-1ND-14 NDE-600 UT SS 14.000 ^ Reference General Requirments Section 8.1.10 Circumferential ND CN-1561-1.1 40 0.438 50314 Depending on the examiners qualifications, Class B Pipe to Procedure PDI-UT-2 may be used In lieu of Elbow NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.011.044A 1ND14-8 CN-1ND-14 NDE-35 PT SS 14.000 Circumferential ND CN-1561-1.1 40 0.438 Class B Pipe to Elbow C05.011.049 1ND39-12 CN-1ND-39 NDE-600 UT SS 12.000 ^ Reference General Requirments Section 8.1.10 Circumferential ND CN-1561-1.0 140 1.125 50219 Depending on the examiners qualifications, Class B Valve 1ND2A to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.011.049A 1ND39-12 CN-1ND-39 NDE-35 PT SS 12.000 Circumferential ND CN-1561-1.0 140 1.125 Class B Valve 1ND2A to Pipe C05.011.067 1ND13-10 CN-1ND-13 NDE-600 UT SS 14.000 'Reference General Requirervents Section 8.1.10.

Circumferential ND CN-1561-1.1 40 0.438 Depending on the examinees 'ualifications, Class B Pipe to Procedure PDI-UT-2 may be used In lieu of Elbow NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used. (This weld was added to adjust the ND System Summary for Inservice

EOC 15 (7 DUKE ENERGY _rIPORATION CATEGORY C-,-1. Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT C

Austenitic SS or High Alloy Piping Inservice Inspection Database Management System Plan Report Welds >= 3/8 In. Nominal Wall Thickness PPivWnd Catawba 1 Page 47 nor Piping > NPS 4 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER IDNUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIATHK CAL BLOCKS COMMENTS Inspection Category C-F-1, as a result of Weld Iso revision).

C05.011.067A 1ND13-10 CN-i ND-13 NDE-35 PT SS 14.000 (This weld was added to adjust the ND System Circumferential ND CN-1561-1.1 40 0.438 Summary for Inservice Inspection Category C-F-1, Class B Pipe to as a result of Weld Iso revision).

Elbow C05.011.114 IN16-6 CN-1NI-6 NDE-600 UT SS 6.000 Reference General Requirments Section 8.1.10 Circumferential Ni CN-1562-1.3 160 0.719 50211 Depending on the examiners qualifications, Class B Pipe to Procedure PDI-UT-2 may be used In lieu of Elbow NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

C05.011.114A 1NI6-6 CN-1NI-6 NDE-35 PT SS 6.000 Circumferential NI CN-1562-1.3 160 0.719 Class B Pipe to Elbow C05.011.115 1N16-7 CN-1NI-6 NDE-600 UT SS 6.000 Reference General Requirments Section 8.1.10 Circumferential NI CN-1562-1.3 160 0.719 50211 Depending on the examinees qualifications, Class B Elbow to Procedure PDI-UT-2 may be used in lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.011.115A iN16-7 CN-1 NI-6 NDE-35 PT SS 6.000 Circumferential NI CN-1 562-1.3 160 0.719 Class B Elbow to Pipe C05.011.118 1N16-13 CN-1NI-6 NDE-600 UT SS 6.000

• Reference General Requirments Section 8.1.10 Circumferential NI CN-1562-1.3 160 0.719 50211 Depending on the examiners qualifications, Class B Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

C05.011.118A 1N16-13 CN-1 Nl-6 NDE-35 PT SS 6.000 Circumferential NI CN-1562-1.3 160 0.719 Class B Elbow to Pipe

EOC 15 DUKE ENERGY ..PORATION CATEGORY C-F-1 Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Austenitic SS or High Alloy Piping Inservice Inspection Database Management System Plan Report

• PiPlnn Welds >= 3/8 In. Nominal Wall Thickness Catawba 1 Page 48 for Pining > NPS 4 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS C05.011.119 1N16-22 CN-1NI.6 NDE-600 UT SS 6.000

• Reference General Requirments Section 8.1.10 Circumferential NI CN-1562-1.3 160 0.719 50211 Depending on the examinees qualifications, Class B Pipe to Procedure PDi-UT-2 may be used in lieu of Elbow . NDE-600. It PD1.UT-2 is used, Calibration Block PDI-UT-2-C may be used.

C05.011.119A 1N16.22 CN-1NI.6 NDE-35 PT SS 6.000 Circumferential Ni CN-1562-1.3 160 0.719 Class B Pipe to Elbow Total C05.01 1 Items: 24

EOC 15 (

CATEGORY C-F-1, Pressure Retaining Welds In EDUKE ENERG Ag

- ,IPORATION INSERVICE INSPECTION PLAN MANAGEMENT Ci Austenitic SS or High Alloy Pipjin Inservice Inspection Database Management System Plan Report EPInina Welds > 1/5 In. Nom Wall For Plping >= Catawba 1 Page 49 0810412005 NPS 2 And <= NPS 4 Inservice Inspection Plan for Interval 2 Outage 7 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBE RS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Circumferential Weld C05.021.107 1NV97-7 CN-1NV-97 NDE-600 UT SS 4.000 *

• Reference General Requirments Section 8.1.10 Circumferential NV CN-1 554-1.7 160 0.531 50275 Depending on the examineres qualifications, Class B Pipe to Procedure PDI-UT-2 may be used In lieu of Elbow NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

C05.021.107A 1NV97-7 CN-1 NV-97 NDE-35 PT SS 4.000 Circumferential NV CN-1554-1.7 160 0.531 Class B Pipe to Elbow C05.021.108 1NV97-8 CN-1NV-97 NDE-600 UT SS 4.000

• Reference General Requirments Section 8.1.10 Circumferential NV CN-1554-1.7 160 0.531 50275 Depending on the examiners qualifications, Class B Elbow to Procedure PDI-UT-2 may be used Inlieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.021.108A 1NV97-8 CN-1NV-97 NDE-35 PT SS 4.000 Circumferential NV CN-1554-1.7 160 0.531 Class B Elbow to Pipe C05.021.109 1NV97-12 CN-1NV-97 NDE-600 UT SS 4.000

• Reference General Requirements Section 8.1.10.

Circumferential NV CN-1554-1.7 160 0.531 50275 Depending on the examiners qualifications, Class B Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.021.109A 1NV97-12 CN-1 NV-97 NDE-35 PT SS 4.000 Circumferential NV CN-1 554-1.7 160 0.531 Class B Elbow to Pipe C05.021.110 1NV97-10 CN-1NV-97 NDE-600 UT SS 4.000 e Reference General Requirments Section 8.1.10 Circumferential NV CN-1554-1.7 160 0.531 50275 Depending on the examinersqualifications, Class B Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

EOC 15 C CATEGORY C-F-1, Pressure Retalning Welds In DUKE ENERGYQRPORATION INSERVICE INSPECTION PLAN MANAGEMENT C.

Austenitic SS or High Alloy Piping Inservice Inspection Database Management System LPiWinq Welds > 115 In. Nom Wall For Pipina >=

NPS 2 And <= NPS 4 Catawba 1 Inservice Inspection Plan for Interval 2 Outage Plan Report Page 50 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CA,LBLOCKS COMMENTS C05.021.110A 1NV97-10 CN-1NV-97 NDE-35 PT SS 4.000 Circumferential NV CN-1554-1.7 160 0.531 Class B Elbow to Pipe C05.021.140 1NV627-1 CN-1NV-627 NDE-600 UT SS 4.000 Reference General Requirments Section 8.1.10 Circumferential NV CN-1554-1.7 160 0.531 50275 Depending on the examiners qualifications, Class B Elbow to Procedure PDI-UT-2 may be used In lieu of Elbow NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.021.140A 1NV627-1 CN-1NV-627 NDE-35 PT SS 4.000 Circumferential NV CN-1554-1.7 160 0.531 Class B Elbow to Elbow C05.021.141 1NV627-2 CN-1NV-627 NDE-600 UT SS 4.000 Reference General Requirments Section 8.1.10 Circumferential NV CN-1554-1.7 160 0.531 50275 Depending on the examiners qualifications, Class B Elbow to Procedure PDI-UT-2 may be used In lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.021.141A 1NV627-2 CN-1 NV-627 NDE-35 PT SS 4.000 Circumferential NV CN-1554-1.7 160 0.531 Class B Elbow to Pipe C05.021.142 1NV627-5 CN-1NV-627 NDE-600 UT SS 4.000 Reference General Requirments Section 8.1.10 Circumferential NV CN-1554-1.7 160 0.531 50275 Depending on the examiners qualifications, Class B Pipe to Procedure PDI-UT-2 may be used In lieu of Elbow NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.021.142A 1NV627-5 CN-1NV-627 NDE-35 PT SS 4.000 Circumferential NV CN-1554-1.7 160 0.531 Class B Pipe to Elbow C05.021.143 1NV627-6 CN-1 NV-627 NDE-600 UT SS 4.000

• Reference General Requirments Section 8.1.10 Circumferential NV CN-1554-1.7 160 0.531 50275 Depending on the examiners qualifications, Class B Elbow to Procedure PDI-UT-2 may be used in lieu of Pipe NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

EOC 15 (

DUKE ENERGY'4. tRPORATION CATEGORY C-F-i, Pressure Retainin Welds In INSERVICE INSPECTION PLAN MANAGEMENT IPIpinq Austenitic SS or High Alloy Piping Welds > 1/5 in. Nom Wall For pinlg >=

NPS 2 And <= NPS 4 Inservice Inspection Database Management System Catawba 1 Inservice Inspection Plan for Interval 2 Outag ae7 Plan Report Page 51 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAAL BLOCKS COMMENTS C05.021.143A 1NV627-6 CN-1NV-627 NDE-35 PT SS 4.000 Circumferential NV CN-1554-1.7 160 0.531 Class B Elbow to Pipe C05.021.144 1NV627-11 CN-1NV-627 NDE-600 UT SS 4.000

• Reference General Requirments Section 8.1.10 Circumferential NV CN-1554-1.7 160 0.531 50275 Depending on the examiners qualifications, Class B Pipe to Procedure PDI-UT-2 may be used In lieu of Elbow NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2-C may be used.

C05.021.144A 1NV627-11 CN-1NV-627 NDE-35 PT SS 4.000 Circumferential NV CN-1554-1.7 160 0.531 Class B Pipe to Elbow C05.021.145 1NV627-12 CN-1NV-627 NDE-600 UT SS 4.000

• Reference General Requirments Section 8.1.10 Circumferential NV CN-1554-1.7 160 0.531 50275 Depending on the examineres qualifications, Class B Elbow to Procedure PDI-UT-2 may be used in lieu of Pipe NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2-C may be used.

C05.021.145A 1NV627-12 CN-1 NV-627 NDE-35 PT SS 4.000 Circumferential NV CN-1 554-1.7 160 0.531 Class B Elbow to Pipe Total C05.021 Items: 20

EOC 15 (

DUKE ENERGY., APORATION CATEGORY C-F-2. Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Carbon Or Low Alloy Steel Pipincg Inservice Inspection Database Management System Plan Report

• PIOna Welds >= 3/8 In. Nominal Wall Thickness Catawba 1 Page 52 For Piping > NPS 4 Inservice Inspection Plan for Interval 2 Outag e 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBEI RS PROC INSP REQ MAT/SCH DIANTHK CAL BLOCKS COMMENTS

• • • • Circumferential Weld

• C05.051.055 1CF39-1 CN-1491-CF039 NDE-600 UT CS 16.000 Steam Generator 1B Feedwater Nozzle Circumferential CF CN-1591-1.1 80 0.844 50329 Transition Ring to Elbow Class B Elbow to

• Reference General Requirements Section 8.1.10 Nozzle SG1 B Transition Ring Depending on the examineres qualifications, Procedure PD1-UT-1 may be used in lieu of NDE-600. If PDl-UT-1 Is used, Calibration Block Number PDI-UT-1-C may be used.

C05.051.055A 1CF39-1 CN-1491-CF039 NDE-25 MT CS 16.000 Steam Generator 1B Feedwater Nozzle Circumferential CF CN-1591-1.1 80 0.844 Transition Ring to Elbow Class B Elbow to Nozzle SGI B Transition Ring C05.051.058 1CF39-2 CN-1491-CF039 NDE-600 UT CS 16.000 e

• Reference General Requirements Section 8.1.10 Circumferential CF CN-1591-1.1 80 0.844 50329 Depending on the examiners qualifications, Class B Pipe to Procedure PD1-UT-1 may be used in lieu of Elbow NDE-600. If PDl-UT-1 is used, Calibration Block PDI-UT-1-C may be used.

C05.051.058A 1CF39-2 CN-1491-CF039 NDE-25 MT CS 16.000 Circumferential CF CN-1591-1.1 80 0.844 Class B Pipe to Elbow C05.051.059 1CF39-10 CN-1491-CF039 NDE-600 UT CS 16.000 * ^ Reference General Requirements Section 8.1.10 Circumferential CF CN-1591-1.1 80 0.844 50329 Depending on the examiners qualifications, Class B Elbow to Procedure PDI-UT-1 may be used In lieu of Pipe NDE-600. If PDI-UT-1 is used, Calibration Block PD1-UT-1-C may be used.

C05.051.059A 1CF39-10 CN-1491-CF039 NDE-25 MT CS 16.000 Circumferential CF CN-1591-1.1 80 0.844 Class B Elbow to Pipe C05.051.060 1CF39-11 CN-1491-CF039 NDE-600 UT CS 16.000

• Reference General Requirements Section 8.1.10 Circumferential CF CN-1591-1.1 80 0.844 50329 Depending on the examiner's qualifications, Class B Pipe to Procedure PD1-UT-1 may be used In lieu of Elbow NDE-600. If PD0-UT-1 is used, Calibration Block PD0-UT-1-C may be used.

EOC 15 DUKE ENERG(

CATEGORY C-F-2. Pressure Retaining Welds In INSERVICE INSPECTION PLAN MANAGEMENT Carbon Or Low Alloy Steel Piping

.PORATION Inservice Inspection Database Management System (C'

Plan Report 0P3OWndWelds >= 3/8 In. Nominal Wall Thickness Catawba 1 Page 53 for Piping > NPS 4 Inservice Inspection Plan for Interval 2 Outag ee7 08/04/2005 ITEM NUMBER IDNUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIAITHK CAAL BLOCKS COMMENTS C05.051.060A 1CF39-11 CN-1491-CF039 NDE-25 MT CS 16.000 Circumferential CF CN-1591-1.1 80 0.844 Class B Pipe to Elbow Total C05.051 Items: 8 Total C05 Items: 52

(

EOC 15 CATEGORY C-C. Pressure Retaining Welds In DUKE ENERG)C APORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Pumps And Valves Inservice Inspection Database Management System Plan Report ovalves Catawba 1 Page 54

. Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS

• • • • Valve Body Welds ****

C06.020.016 ISA-1 CN-1593-1.1 NDE-25 MT CS 6.000 Valve Body Weld - Valve Numbers In Valve Group Circumferential SA CNM-1205.00-0117 1.164 1SA-1,ISA-4 Class B Valve Body to Bonnet C06.020.019 1SV-16 CN-I SV-019 NDE-35 PT SS-CS 9.000 Valve Body Weld - Valve Numbers in Valve Group Circumferential SV CNM-1205.09-002 1.500 1SV-1 4, 1SV-15, 1SV-16, Class B Weld 1AD Valve Inlet Neck to 1SV-17, 1SV-18 Base C06.020.020 1SV-23 CN-1 SV-025 NDE-35 PT SS-CS 9.000 Valve Body Weld - Valve Numbers in Valve Group Circumferential SV CNM-1205.09-002 1.500 1SV-20, 1SV-21, 1SV-22, Class B Weld 1AD Valve Inlet Neck to 1SV-23, 1SV-24 Base Total C06.020 Items: 3 Total C06 Items: 3

It EOC 15 (

DUKE ENERGC .riPORATION CATEGORY D-B, Systems In Support Of ECC, INSERVICE INSPECTION PLAN MANAGEMENT CHR, Atmos. Cleanup, And RHR Inservice Inspection Database Management System Plan Report Wintearal Attachment Catawba 1 Page 55 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Component Supports and Restraints ****

D02.020.009 1-R-CA-0185 CN-1492.CA025 QAL-14 VT-3 NA 4.000 Welded Attachment Rigid Support CA CN-1592-1.1 0.750 To be done with F01.031.008 Class C D02.020.010 1-R-CA-0274 CN-1492-CA025 QAL-14 VT-3 NA 4.000 Welded Attachment Rigid Support CA CN-1592-1.1 1.000 To be done with F01.031.009 Class C D02.020.011 1-R-CA-0246 CN-1492-CA034 OAL-14 VT-3 NA 2.000 Welded Attachment Rigid Support CA CN-1592-1.0 0.375 To be done with F01.031.010 Class C D02.020.036 1-R-LD-0053 CN-1493-LD047 OAL-14 VT-3 NA 6.000 Welded Attachment Rigid Support LD CN-1 609.2.2 0.500 To be done with F01.030.125 Class C D02.020.061 1-R-RN.061 1 CN-1493-RN003 OAL-14 VT-3 NA 10.000 Welded Attachment Rigid Support RN CN-1574-2.1 0.750 To be done with F01.030.177 Class C D02.020.062 I -R-RN-0629 CN-1493-RN044 OAL-14 VT-3 NA 10.000 Welded Attachment Rigid Support RN CN-1574-2.5 0.750 To be done with F01.030.178k Class C D02.020.063 1-R-RN-0807 CN-1492-RNOO-344 OAL-14 VT-3 SS 8.000 Welded Attachment Rigid Support RN CN-ISIN-1574-2.1 0.322 To be done with F01.031.156 Class C D02.020.064 1-R-RN-0825 CN-1492.RNO-362 OAL-14 VT-3 SS 8.000 Welded Attachment Rigid Support RN CN-ISIN-1574-2.1 0.750 To be done with F01.031.157 Class C Total D02.020 Items: 8

EOC 15 ( DUKE ENERG4_*PORATION CATEGORY D-B. Systems In Support Of ECC. INSERVICE INSPECTION PLAN MANAGEMENT CHR. Atmos. Cleanup, And RHR Inservice Inspection Database Management System Plan Report IInteMral Attachment a Catawba 1 Page 56 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUIMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • Spring Type Supports ****

D02.040.027 1-R-KD.0090 CN.1493-KD052 QAL-14 VT-3 NA 8.000 Welded Attachment Spring Hgr KD CN.1609.1.0 0.625 To be done with F01.032.103 Class C D02.040.028 1-R-KD-0057 CN.1493-KD057 OAL-14 VT-3 NA 8.000 Welded Attachment Spring Hgr KD CN-1609-1.0 0.750 To be done with F01.032.104 Class C Total D02.040 Items: 2 Total D02 Items: 10

EOC 15

(.

CATEGORY F-A. Supports C

DUKE ENERGY'-.1PORATION INSERVICE INSPECTION PLAN MANAGEMENT

(

Inservice Inspection Database Management System Plan Report E1ass I Pplnq Supnorts Catawba 1 Page 57 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER IDNUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • One-Dlrectlonal ****

F01.010.091 1-R-NV-1470 CN-1491-NVO12 QAL-14 VT-3 NA 2.000 Rigid Support NV CN-1554-1.5 0.000 Class A F01.010.092 1-R-NV-1471 CN-1491.NVO12 QAL-14 VT-3 NA 2.000 Rigid Support NV CN-1554-1.5 0.000 Class A F01.010.096 1-R-NV-1503 CN-1491-NV004 OAL-14 VT-3 NA 2.000 Rigid Support NV CN-1554-1.5 0.000 Class A F01.010.097 1-R-NV-1508 CN-1491-NVO04 QAL-14 VT-3 NA 2.000 Rigid Support NV CN-1554-1.5 0.000 Class A Total F01.010 Items: 4

• • • • Multidirectlonal ****

F01.011.053 1-R-NI-1390 CN-1491-NIO59 OAL-14 VT-3 NA 6.000 Rigid Support NI CN.1562-1.3 0.000 Class A F01.011.054 1-R-NI-1465 CN-1491-NI090 OAL-14 VT-3 NA 8.000 Rigid Support NI CN-1562-1.2 0.000 Class A F01.011.091 1-R-NV-1502 CN-1491-NVO04 OAL-14 VT-3 NA 1.500 Rigid Support NV CN-1554-1.5 0.000 Class A F01.011.092 1-R-NV-1504 CN-1491-NVO04 OAL-14 VT-3 NA 2.000 Rigid Support NV CN-1554-1.5 0.000 Class A

EOC 15 (

DUKE ENERGr ,RPORATION CATEGORY F-A, Supports INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report Icass 1 Plln1q Supports Catawba 1 Page 58 Inservice Inspection Plan for Interval 2 Outage 7 08t04t2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS F01.011.095 1-R-NV-1501 CN-1491-NVO04 OAL-14 VT-3 NA 1.500 Rigid Support NV CN-1554-1.5 0.000 Class A f01.011.096 1-R-NV-1505 CN-1491-NVO04 QAL-14 VT-3 NA 2.000 Rigid Support NV CN-1554-1.5 ' 0.000 Class A Total F01.011 Items: 6

""Thermal Movement ****

F01.012.015 1-R-NC-1535 CN-1491-NC109 QAL-14 VT-3 NA 1.500 Spring Hgr NC CN-1553-1.0 0.000 Class A F01.012.016 1-R-NC-1536 CN-1491-NC109 QAL-14 VT-3 NA 1.500 Mech Snubber NC CN-1553-1.0 0.000 Class A Total F01.012 Items: 2

(

EOC 15 CATEGORY F-A, Supports DUKE ENERG. IRPORATION INSERVICE INSPECTION PLAN MANAGEMENT QI-Inservice Inspection Database Management System Plan Report lClass 2 Piping SuPPortS Catawba 1 Page 59 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MATtSCH DIA/THK CAL BLOCKS COMMENTS

• • • • One-DIrectional ****

F01.020.011 1-R-CF-1500 CN-1491-CF006 QAL-14 VT-3 NA 18.000 Rigid Support CF CN-1591-1.1 0.750 Class B F01.020.023 1-R-FW-0002 CN-1492-FW001 QAL-14 VT-3 NA 24.000 Rigid Support FW CN-1571-1.0 0.000 Class B F01.020.044 1-R-ND-0188 CN-1492-ND030 QAL-14 VT-3 NA 8.000 Rigid Support ND CN-1561-1.1 0.000 Class B F01.020.045 1-R-ND.0523 CN-1492-ND030 QAL-14 VT-3 NA 8.000 Rigid Support ND CN-1561-1.1 0.000 Class B F01.020.046 1-R8ND-0186 CN-1492-ND031 QAL-14 VT-3 NA 8.000 Rigid Support ND CN-1561-1.1 0.000 Class B F01.020.047 1-R-ND-0187 CN-1492-ND031 OAL-14 VT-3 NA 8.000 Rigid Support ND CN-1561-1.1 0.000 Class B F01.020.048 1-R-ND-0170 CN-1492-ND050 QAL-14 VT-3 NA 12.000 Rigid Support ND CN-1561-1.1 0.000 Class B F01.020.049 1-R-ND-0171 CN-1492-ND050 QAL-14 VT-3 NA 12.000 Rigid Support ND CN-1561-1.1 0.000 Class B

(

EOC 15 CATEGORY F-A, SuPports DUKE ENERGK_ .PORATION INSERVICE INSPECTION PLAN MANAGEMENT K.

Inservice Inspection Database Management System Plan Report llCass 2 PIPIng SuppOrts Catawba 1 Page 60 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS F01.020.050 1-R-ND-0172 CN-1492-ND050 OAL-14 VT-3 NA 12.000 Rigid Support ND CN-1561-1.1 0.000 Class B F01.020.067 1-R-NI-2273 CN-1491-NI087 OAL-14 VT-3 NA 8.000 Rigid Support NI CN-1562-1.2 0.000 Class B F01.020.068 1-R-NI-2274 CN-1491-NI087 OAL-14 VT-3 NA 8.000 Rigid Support NI CN-1562-1.2 0.000 Class B F01.020.069 1-R-NI-2275 CN-1491-NI087 OAL-14 VT-3 NA 8.000 Rigid Support NI CN-1562-1.2 0.000 Class B F01.020.104 1-R-NS-0058 CN-1492-NS004 QAL-14 VT-3 NA 10.000 Rigid Support NS CN-1563-1.0 0.000 Class B F01.020.105 1-R-NS-0076 CN-1492-NS004 QAL-14 VT-3 NA 10.000 Rigid Support NS CN-1563-1.0 0.000 Class B F01.020.108 1-R-NS-0001 CN-1492-NS007 OAL-14 VT-3 NA 12.000 Rigid Support NS CN-1563-1.0 0.000 Class B F01.020.109 1-R-NS-0002 CN.1492-NS007 QAL-14 VT-3 NA 12.000 Rigid Support NS CN-1563-1.0 0.000 Class B F01.020.110 1-R-NS-0003 CN-1492-NS007 OAL-14 VT-3 NA 12.000 Rigid Support NS CN-1563-1.0 0.000 Class B

EOC 15 ( DUKE ENERGY(_RPORATION C.

CATEGORY F-A. SuPports INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report WCIass 2 Ping SUPpOrtS Catawba 1 Page 61 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH D1A/THK CAL BLOCKS COMMENTS F01.020.111 1-R-NS-0037 CN-1492-NSOOB OAL-14 VT-3 NA 10.000 Rigid Support NS CN 1563.1.0 0.000 Class B F01.020.112 1-R-NS-0038 CN-1492.NSOO8 QAL-14 VT-3 NA 10.000 Rigid Support NS CN-1563-1.0 0.000 Class B F01.020.113 1-R.NS.0039 CN-1492-NS008 QAL-14 VT-3 NA 10.000 Rigid Support NS CN-1563-1.0 0.000 Class B F01.020.114 1-R-NS-0042 CN-1492-NS008 QAL-14 VT-3 NA 10.000 Rigid Support NS CN-1563-1.0 0.000 Class B F01.020.115 1.R-NS.0043 CN-1492-NS008 QAL-14 VT-3 NA 10.000 Rigid Support NS CN-1 563-1.0 0.000 Class B F01.020.116 1.R-NS-0044 CN-1492.NS008 OAL-14 VT-3 NA 10.000 Rigid Support NS CN-1563-1.0 0.000 Class B F01.020.117 1-R-NS-0047 CN-1492-NS008 OAL-14 VT-3 NA 10.000 Rigid Support NS CN-1563-1.0 0.000 Class B F01.020.118 1-R.NS-0048 CN-1492-NS008 OAL-14 VT-3 NA 8.000 Rigid Support NS CN-1563-1.0 0.000 Class B F01.020.119 1-R-NS-0049 CN-1492-NS004 OAL-14 VT-3 NA 10.000 Rigid Support NS CN-1563-1.0 0.000 Class B

EOC 15 (

CATEGORY F-A, Supports DUKE ENERG4I.PORATION INSERVICE INSPECTION PLAN MANAGEMENT

(

Inservice Inspection Database Management System Plan Report llClass 2 Piping Suports Catawba 1 Page 62 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS F01.020.155 1-R-NV.0316 CN-1492-NVOOB OAL-14 VT-3 NA 3.000 Rigid Support NV CN-1554-1.2 0.000 Class B F01.020.156 1-R-NV-0318 CN-1492-NVO08 OAL-14 VT-3 NA 3.000 Rigid Support NV CN-1554-1.2 0.000 Class B F01.020.157 1-R-NV-0131 CN-1492.NVO17 QAL-14 VT-3 NA 8.000 Rigid Support NV CN-1554-1.7 0.000 Class B F01.020.158 1-R-NV-0135 CN-1492-NVO17 OAL-14 VT-3 NA 8.000 Rigid Support NV CN-1554-1.7 0.000 Class B F01.020.159 1-R-NV-0137 CN-1492-NVO17 OAL-14 VT-3 NA 8.000 Rigid Support NV CN-1554-1.7 0.000 Class B F01.020.160 1-R-NV-0143 CN-1492-NVO17 OAL-14 VT-3 NA 6.000 Rigid Support NV CN-1554-1.7 0.000 Class B F01.020.161 1-R-NV-0293 CN-1492-NVW24 QAL-14 VT-3 NA 3.000 Rigid Support NV CN-1554-1.2 0.000 Class B F01.020.162 1-R-NV.0294 CN-1492-NV024 QAL-14 VT-3 NA 3.000 Rigid Support NV CN-1554-1.2 0.000 Class B F01.020.163 1-R-NV-0296 CN-1492-NV024 OAL.14 VT-3 NA 3.000 Rigid Support NV CN-1554-1.2 0.000 Class B

EOC 15 (

CATEGORY F-A, SuPPorts DUKE ENERGYCAPORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Inservice Inspection Database Management System Plan Report lClass 2 Piping SUPpOrtS Catawba 1 Page 63 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISOIDWG NUMBERS PROC INSP REQ MAT/SCH DIAITHK CAL BLOCKS COMMENTS F01.020.164 1-R-NV-0298 CN-1492-NV024 OAL-14 VT-3 NA 3.000 Rigid Support NV CN-1554-1.2 0.000 Class B F01.020.165 1-R-NV.0300 CN-1492-NV024 OAL-14 VT-3 NA 3.000 Rigid Support NV CN-1554-1.2 0.000 Class B F01.020.166 1-R-NV-0301 CN-1492-NV024 OAL-14 VT-3 NA 3.000 Rigid Support NV CN-1554-1.2 0.000 Class B F01.020.193 1-R-SA-0003 CN-1492-SA001 QAL-14 VT-3 NA 6.000 Rigid Support SA CN.ISIN-1593-1.1 0.000 Class B F01.020.223 1-R-SV-1522 CN-1491-SV008 QAL-14 VT-3 NA 6.000 Rigid Support SV CN-1593-1.0 0.000 Class B F01.020.224 1-R-SV-1524 CN.1491-SVOO8 QAL-14 VT-3 NA 6.000 Rigid Support SV CN-1593-1.0 0.000 Class B Total F01.020 Items: 41 t*** Multidirectional ****

F01.021.001 1-R-CA-1654 CN-1491-CA021 OAL-14 VT-3 NA 6.000 Rigid Support CA CN-1592-1.1 0.000 Class B F01.021.011 1-RCF-1518 -CN-1491-CF027 QAL-14 VT-3 NA 18.000 Rigid Support CF CN-1591-1.1 0.000 Class B

EOC 15 CATEGORY F-A. Supports DUKE ENERG)LQPORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Inservice Inspection Database Management System Plan Report Class 2 Plt~nq Supports Catawba 1 Page 64 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS F01.021.035 1-R-ND'0610 CN-1492-ND030 OAL-14 VT-3 NA 8.000 Rigid Support ND CN-1561-1.1 0.000 Class B FO1.021.036 1-R-ND.0611 CN-1492-ND030 OAL-14 VT-3 NA 8.000 Rigid Support ND CN-1561-1.1 0.000 Class B F01.021.071 1-R-NI-2271 CN-1491-NI087 QAL-14 VT-3 NA 8.000 Rigid Support NI CN-1562-1.2 0.000 Class B F01.021.072 1-R-NI-2272 CN-1491-NI087 QAL-14 VT-3 NA 8.000 Rigid Support NI CN-1 562-1.2 0.000 Class B F01.021.073 1-R-NI-2278 CN-1491-NI087 QAL-14 VT-3 NA 8.000 Rigid Support Nl CN-1562-1.2 0.000 Class B F01.021.098 1-R-NS-0033 CN-1492-NS008 OAL-14 VT-3 NA 10.000 Rigid Support NS CN-1 563-1.0 0.000 Class B F01.021.165 1-R-NV-0509 CN-1492-NVO17 OAL-14 VT-3 NA 8.000 Rigid Support NV CN-1554-1.7 0.000 Class B F01.021.166 1-R-NV-0537 CN-1492.NVO17 OAL-14 VT-3 NA 8.000 Rigid Support NV CN-1554-1.7 0.000 Class B F01.021.167 1-R-NV-0538 CN-1492-NVO17 OAL-14 VT-3 NA 8.000 Rigid Support NV CN-1554-1.7 0.000 Class B

(

EOC 15 CATEGORY F-A, Supports DUKE ENERGtQAPORATION INSERVICE INSPECTION PLAN MANAGEMENT C(

Inservice Inspection Database Management System Plan Report lClass 2 Plping Supports Catawba 1 Page 65 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS F01.021.168 1-A-NV-3202 CN-1492-NV034 OAL-14 VT-3 NA 2.000 Dwg. CN-MA-1076 Rigid Support NV CN-1554-1.6 0.000 Class B F01.021.169 1-A-NV-3205 CN-1492-NV034 OAL-14 VT-3 NA 2.000 Rigid Support NV CN.1554-1.6 0.000 Class B F01.021.170 1-R-NV-0175 CN-1492.NVO40 OAL-14 VT-3 NA 2.000 Rigid Support NV CN-1554-1.7 0.000 Class B Total F01.021 Items: 14

• • • • Thermal Movement ****

F01.022.021 1-R-FW-0056 CN-1492-FW021 QAL-14 VT-3 NA 12.000 Mech Snubber FW CN-1571-1.0 0.000 Class B F01.022.037 1-R-ND.0129 CN-1492-ND030 QAL-14 VT-3 NA 8.000 Spring Hgr ND CN-1561-1.1 0.000 Class B F01.022.038 1-R-ND-0131 CN-1492-ND030 OAL-14 VT-3 NA 8.000 Spring Hgr ND CN-1561-1.1 0.000 Class B F01.022.039 1-R-ND-0626 CN-1492-ND030 OAL-14 VT-3 NA 8.000 Spring Hgr ND CN-1561-1.1 0.000 Class B F01.022.040 1-R-ND-0168 CN-1492-ND050 OAL-14 VT-3 NA 12.000 Spring Hgr ND CN-1561-1.1 0.000 Class B

EOC 15 CATEGORY F-A, Supports DUKE ENERGYCAPORATION INSERVICE INSPECTION PLAN MANAGEMENT (7

Inservice Inspection Database Management System Plan Report llClass 2 Plplng Supports Catawba 1 Page 66 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS F01.022.063 1-R-NI-2264 CN-1491-NI060 OAL-14 VT-3 NA 6.000 Mech Snubber NI CN-1562-1.2 0.000 Class B F01.022.092 1-R-NS.0031 CN-1492-NS008 OAL-14 VT-3 NA 10.000 Mech Snubber NS CN-1563-1.0 0.000 Class B F01.022.145 1-R-NV.0315 CN-1492-NVO08 OAL-14 VT-3 NA 3.000 Spring Hgr NV CN-1554-1.2 0.000 Class B F01.022.147 1-R-NV-0319 CN.1492-NVO08 OAL-14 VT-3 NA 3.000 Spring Hgr NV CN-1554-1.2 0.000 Class B F01.022.148 1-R-NV-0015 CN-1492-NVO17 OAL-14 VT-3 NA 8.000 Mech Snubber NV CN-i 554-1.7 0.000 Class B F01.022.149 1-R-NV-0136 CN-1492-NV017 QAL-14 VT-3 NA 8.000 Spring Hgr NV CN-1554-1.7 0.000 Class B F01.022.150 1.R-NV-0508 CN-1492-NV017 QAL-14 VT-3 NA 6.000 Mech Snubber NV CN-1554-1.7 0.000 Class B F01.022.221 1-R-SV-1514 CN-1491-SV005 QAL-14 VT-3 NA 6.000 Mech Snubber SV CN-i 593-1.0 0.000 Class B Total F01.022 Items: 13

EOC 15 C CATEGORY F-A, Supports DUKE ENERGY(EA*PORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Inservice Inspection Database Management System Plan Report Class 3 PIPlng Supports Catawba I Page 67 Inservice InspectIon Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS

• • • • One-Directional ***

F01.030.090 1-R-KC-0875 CN-1492-KC349 OAL-14 VT-3 NA 6.000 Note: Added to RFO #1per IWF-2420(b)

Rigid Support KC CN-1573-1.0 0.000 Ref. PIP# 1-C93-0875 Class C F01.030.092 1-R-KC-0184 CN-1492-KC035 OAL-14 VT-3 NA 12.000 Rigid Support KC CN.ISIN-1 573-1.0 0.000 Class C F01.030.093 1-R-KC.0028 CN-1492-KC111 QAL-14 VT-3 NA 14.000 Added to Outage #7(EOC1 5).

Rigid Support KC CN-1 573-1.2 0.000 per ASME Section Xl, Paragraph IWF-2430(a) and Class C PIP # C.05-01591.

F01.030.094 1-R-KC-0031 CN-1492-KC111 OAL-14 VT-3 NA 12.000 Added to Outage #7(EOC15)

Rigid Support KC CN-1573-1.2 0.000 per ASME Section Xl, Paragraph IWF-2430(a) and Class C PIP # C-05-01591.

F01.030.124 1-R-LD-0051 CN-1493-LD047 OAL-14 VT-3 NA 6.000 Rigid Support LD CN-1609-2.2 0.000 Class C F01.030.125 1-R-LD-0053 CN-1493-LD047 QAL-14 VT-3 NA 6.000 To be done with D02.020.036 Rigid Support LD CN-1609-2.2 0.000 Class C F01.030.177 1-R-RN.0611 CN.1493-RN003 QAL-14 VT-3 NA 10.000 To be done with D02.020.061 Rigid Support RN CN-1 574-2.1 0.000 Class C F01.030.178 1-R-RN-0629 CN-1493-RN044 QAL-14 VT-3 NA 10.000 To be done with D02.020.062 Rigid Support RN CN-1574-2.5 0.000 Class C

EOC 15 CATEGORY F-A, Supports (7- DUKE ENERGY oRPORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Inservice Inspection Database Management System Plan Report ECaSS 3 Piping SuPorts Catawba 1 Page 68 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISOIDWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS F01.030.179 1-R-RN-0810 CN-1492-RN-347 QAL-14 VT-3 NA 8.000 Rigid Support RN CN-ISI-1574-2.1 0.000 Class C F01.030.180 1-R-RN.0593 CN-1492-RN.00-356 QAL-14 VT-3 NA 8.000 Rigid Support RN CN- 1574-2.5 0.000 Class C F01.030.181 1-R-RN-0594 CN-1492-RN.00-356 QAL-14 VT-3 NA 8.000 Rigid Support RN CN-1574-2.5 0.000 Class C F01.030.191 1-R-SA-0015 CN-1492-SA002 OAL-14 VT-3 NA 6.000 Rigid Support SA CN-1593-1.1 0.000 Class C CN- 1595-1.1 F01.030.201 1-R-TE-0024 CN-1492-TE001 OAL-14 VT-3 NA 12.000 Rigid Support TE CN-1593-1.2 0.000 Class C F01.030.202 1-R-TE.0032 CN-1492-TE001 OAL-14 VT-3 NA 12.000 Rigid Support TE CN-1593-1.2 0.000 Class C F01.030.225 1-R-VN-0019 CN-1493-VN009 OAL-14 VT-3 NA 30.000 Rigid Support VN CN-1 609-5.0 0.000 Class C F01.030.254 1-R-YC-0046 CN-1525-YCO07 QAL-14 VT-3 NA 6.000 Rigid Support YC CN-1578-2.0 0.000 Class C Total F01.030 Items: 16

• • • • Multidirectionam ****

EOC 15

(

CATEGORY F-A, SuppDorts DUKE ENERGYC'uRPORATION INSERVICE INSPECTION PLAN MANAGEMENT C

Inservice Inspection Database Management System Plan Report ECI8SS 3 Piping-Supports Catawba 1 Page 69 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 ITEM NUMBER ID NUMBER SYS ISOtDWG NUMBERS PROC INSP REQ MATtSCH DIAITHK CAL BLOCKS COMMENTS F01.031.008 1-R-CA.0185 CN-1492-CA025 OAL.14 VT-3 NA 4.000 To be done with D02.020.009 Rigid Support CA CN-1592-1.1 0.000 Class C F01.031.009 1-R-CA-0274 CN-1492-CA025 OAL-14 VT-3 NA 4.000 To be done with D02.020.010 Rigid Support CA CN-1592-1.1 0.000 Class C F01.031.010 1-R-CA-0246 CN-1492-CA034 OAL-14 VT-3 NA 2.000 To be done with D02.020.011 Rigid Support CA CN-1592-1.0 0.000 Class C F01.031.057 1-R-KC-0872 CN-1492-KC349 OAL-14 VT-3 NA 6.000 Rigid Support KC CN-1573-1.0 0.000 Class C F01.031.058 1-R-KC-0873 CN-1492-KC349 OAL-14 VT-3 NA 6.000 Rigid Support KC CN-1573-1.0 0.000 Class C F01.031.059 1 R-KC-0874 CN-1492-KC349 QAL-14 VT-3 NA 6.000 Rigid Support KC CN-1573-1.0 0.000 Class C F01.031.060 1-R-KC-0876 CN-1492-KC348 QAL-14 VT-3 NA 6.000 Added to Outage #7(EOC15)

Rigid Support KC CN-1573-1.0 0.000 per ASME Section Xl, Paragraph IWF-2430(a) and Class C PIP # C-05-01591.

F01.031.153 1-R-RN-0753 CN-1492.RN331 OAL-14 VT-3 NA 42.000 Rigid Support RN CN-1574-1.1 0.000 Class C F01.031.156 1-R-RN.0807 CN-1492-RNOO-344 QAL-14 VT-3 NA 8.000 To Be Done with D02.020.063 Rigid Support RN CN.ISIN-1574-2.1 0.000 Class C

EOC 15 ( DUKE ENERGCLJRPORATION C CATEGORY F-A, Suports INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report Cass 3 Piping S SuDPorts Catawba 1 Page 70 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS F01.031.157 1-R-RN-0825 CN-1492-RN0-362 QAL-14 VT-3 NA 8.000 To Be Done with D02.020.06; Rigid Support RN CN-ISIN-1574-2.1 0.000 Class C F01.031.158 1-R-RN-0826 CN-1492-RNO-353 QAL-14 VT-3 NA 8.000 Rigid Support RN CN-ISIN-1574-2.5 0.000 Class C Total F01.031 Items: 11

• • • • Thermal Movement F01.032.004 1-R-CA 0220 CN-1492-CA024 QAL-14 VT-3 NA 8.000 Spring Hgr CA CN-1 592-1.1 0.000 Class C F01.032.056 1-R-KC-0075 CN-1492-KC111 OAL-14 VT-3 NA 14.000 Spring Hgr KC CN-1573-1.2 0.000 Class C F01.032.057 1-R8KC-0076 CN-1492-KC111 QAL-14 VT-3 NA 12.000 Spring Hgr KC CN-1573-1.2 0.000 Class C F01.032.103 1-R-KD.0090 CN-1493-KD052 QAL-14 VT-3 NA 8.000 To be done with D02.040.027 Spring Hgr KD CN-1609-1.0 0.000 Class C F01.032.104 1-R-KD-0057 CN-1493-KD057 QAL-14 VT-3 NA 8.000 To be done with D02.040.028 Spring Hgr KD CN-1609-1.0 0.000 Class C F01.032.191 1-R-SA-0016 CN-1492-SA002 OAL-14 VT-3 NA 6.000 Mech Snubber SA CN-1593-1.1 0.000 Class C CN-1595-1.1

EOC 15 ( DUKE ENERGCtjRPORATION CATEGORY F-A, Supports INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report ECaass 3 Piping Supports Catawba 1 Page 71 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISOIDWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS F01.032.222 1-R-VN-0055 CN-1 493-VN006 OAL-14 VT-3 NA 26.000 Mech Snubber VN CN-1609-5.0 0.000 Class C Total F01.032 Items: 7

EOC 15 ( DUKE ENERG(..I4 PORATION C CATEGORY F-A.-Supports INSERVICE INSPECTION PLAN MANAGEMENT lnservice Inspection Database Management System it Plan Report MClass;123Spos Catawba 1 It Page72 Inservice Inspection Plan for Interval 2 Outage 7 0810412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MATISCH DINTrHK CAL BLOCKS COMMENTS

• • • Supports Other Than Piping Supports **

F01.040.004 1RICPB..COLUMNS CN-1070-9 QAL-14 VT-3 NA 0.000 Reactor Coolant Pump I 5%Spport Columns Rigid Support NC ON-i1553-1.0 0.000 3 Assemblies Class A F01.040.005 1RCPC-SUPPORT CN-1070-8 QAL-14 VT-3 NA 0.000 Reactor Coolant Pump i C Lateral Support Rigid Support NC CN-1553-1.0 0.000 Class A F01.040.006 1SGA-COLUMNS CN-1070-9 QAL-14 VT-3 NA 0.000 Steam Generator l A Support Columns Rigid Support NC CN-1 553.1 .0 0.000 4 Assemblies Class A FO1.040.011 ISGD-LATERALS CN-1070-11 QAL-14 VT-3 NA 0.000 Steam Generator i D Lower Laterals Rigid Restraint NC CN.1 553.1 .0 0.000 Reference Drawing Numbers CN-1070-12 and Class A CN-1070-12.01.

F01.040.107 1SGD-SUPPORT CN-1070-30.01 QAL-14 Vr-3 NA 0.000 Steam Generator ID Upper Lateral Support and Rigid Support NC CN-1553-1.0 0.000 Snubbers Class B Reference Drawing Numbers CN-i1070-40 and CN.1 070.41.

F01.040.205 I NSHXA-SUPPORT CNM-1201.06-52 QAL-14 VT-3 NA 0.000 Containment Spray Heat Exchanger IA Support Rigid Support NS ON-i1563.1 .0 0.000 Class C F01.040.206 1RNPA-SUPPORT CNM-1201.05-122 QAL-14 VT.3 NA 0.000 Nuclear Service Water Pump lA Support Rigid Support RN CN-1574-1.0 0.000 Class C F01.040.207 1RNSB-SUPPORT CNM-1218.02.10 QAL.14 VT-3 NA 0.000 Nuclear Service Water Strainer 18B Support Rigid Support RN CN-1574-1.2 0.000 Class C Total F01.040 Items: 8 Total F01 Items: 122

EOC 15 ( DUKE ENERGt'\.jRPORATION (

CATEGORY, Augmented INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report WiPe Rupture Protection Catawba 1 Page 73 Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MATISCH DIAiTHK CAL BLOCKS COMMENTS

• • • • Main Steam System ****

G02.001.028 1SM33-01 CN-1 SM-033 NDE-600 UT CS 34.000 *

• Reference General Requirements Section 8.1.10 Circumferential SM CN-1593-1.0 1.750 Depending on the examinees qualifications, Class B Pipe to Procedure PDI-UT-1 may be used In lieu of Pipe NDE-600. If PDI-UT-1 Is used, Calibration Block PDI-UT-1-C may be used.

G02.001.028A 1SM33-01 CN-1 SM-033 NDE-25 MT CS 34.000 Circumferential SM CN-1593-1.0 1.750 Class B Pipe to Pipe G02.001.029 1SM-4A-A CN-1 SM-033 NDE-600 UT CS 34.000 Grinnell Piece Mark CT-SM-4A Weld A Circumferential SM CN-1593-1.0 1.750

• Reference General Requirments Section 8.1.10 Class B Pipe to Depending on the examiners qualifications, Elbow Procedure PDI-UT-1 may be used Inlieu of NDE-600. If PDI-UT-1 Is used, Calibration Block PDI-UT-1-C may be used.

G02.001.029A 1SM-4A-A CN-1 SM-033 NDE-25 MT CS 34.000 Grinnell Piece Mark CT-SM-4A Weld A Circumferential SM CN-1593-1.0 1.750 Class B Pipe to Elbow G02.001.030 1SM33-02 CN-ISM-033 NDE-600 UT CS 34.000

• Reference General Requirements Section 8.1.10 Circumferential SM CN-1593-1.0 1.750 Depending on the examiners qualifications, Class B Pipe to Procedure PDI-UT-1 may be used in lieu of Elbow NDE-600. If PDI-UT-1 Is used, Calibration Block PDI-UT-1-C may be used.

G02.001.030A 1SM33-02 CN-I SM-033 NDE-25 MT CS 34.000 Circumferential SM CN-1593-1.0 1.750 Class B Pipe to Elbow G02.001.031 ISM-5A-A CN-1SM-033 NDE-600 UT CS 34.000

• Grinnell Piece Mark CT-SM-5A Weld A Circumferential SM CN-1593-1.0 1.750

• Reference General Requirments Section 8.1.10 Class B Pipe to Depending on the examiners qualifications, Elbow Procedure PDI-UT-1 may be used in lieu of NDE-600. If PDI-UT-1 is used, Calibration Block PDI-UT-1-C may be used.

r---

EOC 15 DUKE ENERG#uo.RPORATION CATEGORY, Augmented INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Pla n Report WIne Runture Protection Catawba 1 Page 74 Inservice Inspection Plan for Interval 2 Outage 7 OE 1/0412005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS G02.001.031A 1SM-5A-A CN-1SM-033 NDE-25 MT CS 34.000 Grinnell Piece Mark CT-SM-5A Weld A Circumferential SM CN-1 593-1.0 1.750 Class B Pipe to Elbow G02.001.032 1SM33-03 CN-1SM-033 NDE-600 UT CS 34.000

• Reference General Requirements Section 8.1.10 Circumferential SM CN-1 593-1.0 1.750 Depending on the examiners qualifications, Class B Pipe to Procedure PDI-UT-1 may be used In lieu of Elbow NDE-600. If PDI-UT-1 Is used, Calibration Block PDI-UT-1-C may be used.

G02.001.032A 1SM33-03 CN-1SM-033 NDE-25 MT CS 34.000 Circumferential SM CN-1 593-1.0 1.750 Class B Pipe to Elbow Total G02.001 Items: 10 Total G02 Items: 10

EOC 15 I DUKE ENERGY LURPORATION PI. C CATEGORY, INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report Catawba 1 Page 75 Inservice Inspection Plan for Interval 2 Outage 7 08/04/2005 I

ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MATISCH DIAITHK CAL BLOCKS COMMENTS HO1.001.001 1NI148-9 CN-1 NI-I48 NDE-600 UT SS 6.000

• Reference General Requirements Section 8.1.10.

Circumferential NI CN-1562-1.1 160 0.719 50211 This weld examined under Item Number Class A Pipe to 809.011.162 in Outage 1 (EOC9), and meets the Tee intent of this Elective Examination. This Elective Examination was added to the ISI Database per Engineering Examination Request # ER-CNS-99-01.

Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.002 1NI148-9L CN-1NI-148 NDE-600 UT SS 6.000 *Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 160 0.719 50211 The examination includes at least a pipe diameter Class A Pipe to length but no more than 12 inches of longitudinal Tee weld intersecting the circumferential weld In reducing T, located near circumferential weld #9.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

ER-CNS-99-01. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

HO1.001.003 1NI148-10 CN-1NI-148 NDE-600 UT SS 10.000 * *Reference General Reaulrements Section 8.1.10.

Circumferential NI CN-1562-1.1 140 1.000 50209 This weld examined under Item Number Class A Tee to B09.011.163 In Outage 1 (EOC9), and meets the Valve 1N181 Intent of this Elective Examination. This Elective Examination was added to the [SI Database per Engineering Examination Request # ER-CNS-99-01.

Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.004 1NI148-10L CN-1 NI-148 NDE-600 UT SS-Inconel 10.000 *

• Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 140 1.000 The examination Includes at least a pipe diameter Class A Tee to length but no more than 12 inches of longitudinal Valve 1NI81 weld Intersecting the circumferential weld In reducing T, located near circumferential weld #10.

This Elective Examination was added to the ISI

EOC 15

CATEGORY, C DUKE ENERGY CORPORATION INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report Catawba 1 Page 76 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 I

ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MATISCH DIA/THK CAL BLOCKS COMMENTS Database per Engineering Examination Request #

ER-CNS-99-01. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.005 1NI148-11 CN-1NI-148 NDE-600 UT SS 10.000

• Reference General Requirements Section 8.1.10.

Circumferential NI CN-1562-1.1 140 1.000 50209 This weld examined under Item Number Class A Tee to B09.011.164 In Outage 1 (EOC9), and meets the Valve 1N182 intent of this Elective Examination. This Elective Examination was added to the ISI Database per Engineering Examination Request # ER-CNS-99-01.

Depending on the examiners qualifications, Procedure PDI-UT-2 may be used In lieu of NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.006 1N1148-11L CN-1NI-148 NDE-600 UT SS 10.000

• Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 140 1.000 The examination Includes at least a pipe diameter Class A Tee to length but no more than 12 Inches of longitudinal Valve 1N182 weld Intersecting the circumferential weld in reducing T, located near circumferential weld #11.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

ER-CNS-99-01. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.007 1NI152-9 CN-1NI-152 NDE-600 UT SS 6.000 *

• Reference General Reauirements Section 8.1.10.

Circumferential NI CN-1562-1.1 160 0.719 50211 This Elective Examination was added to the IS1 Class A Pipe to Database per Engineering Examination Request #

Tee ER-CNS-99-01.

Depending on the examiners qualifications, Procedure PDI-UT-2 may be used In lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

EOC 15

( C DUKE ENERGY uORPORATION CATEGORY. INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report Catawba 1 Page 77 I

ITEM NUMBER ID NUMBER Inservice Inspection Plan for Interval 2 Outage 7 SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS 08104/2005 H01.001.008 1N1152-9L CN-INI-152 NDE-600 UT SS 6.000

• Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 160 0.719 50211 The examination includes at least a pipe diameter Class A Pipe to length but no more than 12 Inches of longitudinal Tee weld intersecting the circumferential weld in reducing T, located near circumferential weld #9.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

ER-CNS-99-01. Depending on the examiner's qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.009 1N1152-10 CN-1NI-152 NDE-600 UT SS 10.000 ^ Reference General Requirements Section 8.1.10.

Circumferential NI CN-1562-1.1 140 1.000 50209 This Elective Examination was added to the ISI Class A Tee to Database per Engineering Examination Request#

Valve 1Ni94 ER-CNS-99-01.

Depending on the examiner's qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.010 1NI152-10L CN-1NI-152 NDE-600 UT SS 10.000

• Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 140 1.000 50209 The examination Includes at least a pipe diameter Class A Tee to length but no more than 12 Inches of longitudinal Valve 1Nt94 weld Intersecting the circumferential weld in reducing T, located near circumferential weld #10.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

ER-CNS-99-01. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used In lieu of NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.011 1N1152-11 CN-1NI-152 NDE-600 UT Ss 10.000 o Reference General Requirements Section 8.1.10.

Circumferential NI CN-1562-1.1 140 1.000 50209 This Elective Examination was added to the ISI Class A Tee to Database per Engineering Examination Request #

Valve 1N193 ER-CNS-99-01.

Depending on the examiner's qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block

EOC 15

CATEGORY,

( DUKE ENERGY CORPORATION INSERVICE INSPECTION PLAN MANAGEMENT

., C Inservice Inspection Database Management System Plan Report Catawba 1 Page 78 Inservice Inspection Plan for Interval 2 Outage 7 0810412005 I

ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS PDI-UT-2 -C may be used.

H01.001.012 1N1152-11L CN-INI-152 NDE-600 UT SS 10.000 ^Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1 562-1.1 140 1.000 50209 The examination includes at least a pipe diameter Class A Tee to length but no more than 12 Inches of longitudinal Valve 1NI93 weld Intersecting the circumferential weld in reducing T, located near circumferential weld #11.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

ER-CNS-99-01. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.013 1NI162-13 CN-1NI-162 NDE-600 UT Ss 6.000 Reference General Requirements Section 8.1.10.

Circumferential NI CN-1562-1.1 160 0.719 50211 This Elective Examination was added to the ISI Class A Pipe to Database per Engineering Examination Request #

Tee ER-CNS-99-01.

Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.014 1NI162-13L CN-1NI-162 NDE-600 UT SS 6.000 *

• Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 160 0.719 50211 The examination includes at least a pipe diameter Class A Pipe to length but no more than 12 Inches of longitudinal Tee weld Intersecting the circumferential weld in reducing T, located near circumferential weld #13.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

ER-CNS-99-01. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

EOC 15 C C' DUKE ENERGY CURPORATION c

CATEGORY, INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report I

ITEM NUMBER ID NUMBER SYS ISOIDWG NUMBERS PROC Catawba 1 Inservice Inspection Plan for Interval 2 Outage 7 INSP REQ MAT/SCH DIA/THK CAL BLOCKS COMMENTS Page 79 08/04/2005 H01.001.015 1NI162-14 CN-1NI-162 NDE-600 UT SS 10.000

• Reference General Requirements Section 8.1.10.

Circumferential NI CN-1562-1.1 140 1.000 50209 This Elective Examination was added to the ISI Class A Tee to Database per Engineering Examination Request #

Pipe ER-CNS-99-01.

Depending on the examiners qualifications, Procedure PDI-UT-2 may be used In lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.016 1NI162-14L CN-1NI-162 NDE-600 UT Ss 10.000

• Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 140 1.000 50209 The examination Includes at least a pipe diameter Class A Tee to length but no more than 12 Inches of longitudinal Pipe weld Intersecting the circumferential weld in reducing T, located near circumferential weld #14.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

ER-CNS-99-01. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.017 1NI163-15 CN-1NI-163 NDE-600 UT SS 10.000 ^

• Reference General Requirements Section 8.1.10.

Circumferential Ni CN-1562-1.1 140 1.000 50209 This Elective Examination was added to the ISI Class A Valve 1N159 to Database per Engineering Examination Request #

Tee ER-CNS-99-01.

Depending on the examinees qualifications, Procedure PDI-UT-2 may be used In lieu of NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.018 1N1163-15L CN-1NI-163 NDE-600 UT SS 10.000

• Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 140 1.000 50209 The examination Includes at least a pipe diameter Class A Valve 1N159 tc length but no more than 12 inches of longitudinal Tee weld Intersecting the circumferential weld In reducing T, located near circumferential weld #15.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

ER-CNS-99-01. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block

EOC 15 DUKE ENERGY CORPORATION CATEGORY, INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report Catawba 1 Page 80 Inservice Inspection Plan for Interval 2 Outage 7 08/0412005 I

ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MATISCH DIA/THK CAL BLOCKS COMMENTS PDI-UT-2 -C may be used.

H01.001.019 1NI164-8 CN-1NI-164 NDE-600 UT SS 10.000

• Reference General Requirements Section 8.1.10.

Circumferential NI CN-1562-1.1 140 1.000 50209 This Elective Examination was added to the ISI Class A Valve 1N170 to Database per Engineering Examination Request #

Tee ER-CNS-99-01.

Depending on the examiners qualifications, Procedure PDI-UT-2 may be used In lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.020 1NI164-8L CN-1NI-164 NDE-600 UT SS 10.000

• Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 140 1.000 50209 The examination Includes at least a pipe diameter Class A Valve 1N170 to length but no more than 12 inches of longitudinal Tee weld Intersecting the circumferential weld in reducing T, located near circumferential weld #8.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

ER-CNS-99-.0. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.021 1NI165-8 CN-1NI-165 NDE-600 UT Ss 10.000

• Reference General Requirements Section 8.1.10.

Circumferential NI CN-1562-1.1 140 1.000 50209 This Elective Examination was added to the ISI Class A Valve 1N171 to Database per Engineering Examination Request #

Tee ER-CNS-99-01.

Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.022 1NI165-8L CN-1NI-165 NDE-600 UT SS 10.000

• Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 140 1.000 50209 The examination includes at least a pipe diameter Class A Valve 1N171 tiD length but no more than 12 Inches of longitudinal Tee weld intersecting the circumferential weld in reducing T, located near circumferential weld #8.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

EOC 15 (7. DUKE ENERGY CORPORATION

(

CATEGORY, INSERVICE INSPECTION PLAN MANAGEMENT Inservice Inspection Database Management System Plan Report Catawba 1 Page 81 I Inservice Inspection Plan for Interval 2 Outage 7 08104/2005 ITEM NUMBER ID NUMBER SYS ISO/DWG NUMBERS PROC INSP REQ MATISCH DIAITHK CAL BLOCKS COMMENTS ER-CNS-99-01. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used in lieu of NDE-600. If PDI-UT-2 is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.023 1NI165-9 CN-1NI-165 NDE-600 UT SS 6.000 *

• Reference General Requirements Section 8.1.10.

Circumferential NI CN-1562-1.1 160 0.719 50211 This Elective Examination was added to the ISI Class A Tee to Database per Engineering Examination Request #

Pipe ER-CNS-99-01.

Depending on the examineres qualifications, Procedure PDI-UT-2 may be used In lieu of NDE.600. If PDI-UT-2 is used, Calibration Block PDI-UT-2 -C may be used.

H01.001.024 1NI165-9L CN-1NI-165 NDE-600 UT SS 6.000

• Reference General Requirements Section 8.1.10.

Longitudinal NI CN-1562-1.1 160 0.719 50211 The examination includes at least a pipe diameter Class A Tee to length but no more than 12 inches of longitudinal Pipe weld Intersecting the circumferential weld in reducing T, located near circumferential weld #9.

This Elective Examination was added to the ISI Database per Engineering Examination Request #

ER-CNS-99-01. Depending on the examiners qualifications, Procedure PDI-UT-2 may be used In lieu of NDE-600. If PDI-UT-2 Is used, Calibration Block PDI-UT-2 -C may be used.

Total H01.001 Items: 24 Total H01 Items: 24

4.0 Results of Inspections Performed AKJ The results of each examination shown in the final Inservice Inspection Plan (Section 3.0 of this report) are included in this section. The completion date and status for each examination are shown. All examinations revealing reportable indications and any corrective action required as a result are described in further detail in Subsections 4.1 and 4.2. Corrective measures performed and limited examinations are described in further detail in Subsections 4.3 and 4.4.

The information shown below is a field description for the reporting format included in this section of the report.

ITEM NUMBER = ASME Section Xi Tables IWB-2500-1 (Class 1), IWC-2500-1 (Class 2), IWF-2500-1 (Class 1 and Class 2),

Augmented Requirements ID NUMBER = Unique Identification Number SYSTEM = Component System Identification INSP DATE = Date of Examination KJ INSP STATUS = CLR Clear REC Recordable REP Reportable INSP LIMITED = Indicates inspection was limited.

Coverage obtained is listed.

GEO REF Y Yes (Geometric N No Reflector applies only to UT)

RFR (Relief = Y Yes Request) _ No COMMENTS = General and / or Detail Description 4.1 Reportable Indications A reportable condition was detected during EOC15 on KC System Support ID Number 1-R-KC-0875 (Item Number F01.030.090). The inspection sample was increased in EOC15 in accordance with ASME Section Xl, Paragraph IWF-2430(a) and PIP #C-05-01591. No other reportable conditions were detected. A copy of the inspection data sheets is included in this section of the report.

Refueling Outage EOC 15 (Outage 7) Page 1 of 3 Catawba Unit 1 Revision 0 Section 4 August 15, 2005

42. Corrective Action Corrective action is action taken to resolve flaws and relevant conditions, including supplemental examinations, analytical evaluations, repair/ replacement activities, and corrective measures.

PIP #C-05-01591 was written during EOC15 to document a reportable condition found by a VT-3 visual examination on a KC System Rigid Support, ID. Number 1-R-KC-0875 (Item Number F01.030.090). A copy of PIP #C-05-01591 is included in this section of the report.

PIP # C-05-2956 was written during EOC15 to document an indication found by ultrasonic examination on the Reactor Vessel 338 Degree Outlet Nozzle to Safe End and Safe End to Pipe Buttering Weld, ID Number 1-RPV-W18-SE (Item Number B05.010.008 and B05.010.008A) and Weld ID Number 1NC23-01 (Item Numbers B05.130.005 and B05.130.005A). Plant Engineering performed an evaluation of the weld indication (Calculation #CNC-1201.01-00-0025). The conclusion of the evaluation determined that the integrity of the nozzle-to-pipe weld region will not be affected by the exposure of the layer of heat treated Type 309S weld material to the PWR primary water as the result of the axial indications in the Alloy 182 deposit on the ID surface. The weld indication was considered a recordable indication. A copy of Inspection Data Sheets B05.010.008, B05.010.008A, B05.130.005 and B05.130.005A are included in this section of the report. A copy of Calculation #CNC-1201.01-00-0025 is on file at Catawba Nuclear Station.

4.3 Corrective Measures Corrective measures are actions (such as maintenance) taken to resolve relevant conditions, but not including supplemental examinations, analytical evaluations, and repair / replacement activities. Any corrective measures performed for examinations associated with this report period will be shown on the examination data sheets which are on file at the Duke Energy Corporate Office in Charlotte, North Carolina.

4.4 Limited Examinations Limitations (i.e. 90% or less of the required examination coverage obtained) identified for examinations associated with this report period are shown below. A relief request will be submitted to seek NRC acceptance of the limited coverage.

Reference Subsection 1.3 for additional information.

Item Numbers Relief Request Serial Number B01.011.001 To be filed later B01.021.001 To be filed later B03.1 10.001A To be filed later Refueling Outage EOC 15 (Outage 7) Page 2 of 3 Catawba Unit 1 Revision 0 Section 4 August 15, 2005

Item Numbers Relief Request Serial Number B03.110.004A To be filed later B03.110.005 To be filed later B03.110.006A To be filed later B05.010.008 To be filed later B05.01 0.008A To be filed later B05.130.005 To be filed later B05.130.005A To be filed later B09.011.048 To be filed later B12.040.002D To be filed later C05.011.049 To be filed later

\ I Refueling Outage EOC 15 (Outage 7) Page 3 of 3 Catawba Unit 1 Revision 0 Section 4 August 15, 2005

1 DUKE ENERGY "ORATION QUALITY ASSURANCE ,NICAL SERVICES In-Service Inspection Database Management System Run D EOC 15 Page 1 Catawba 1 Inservice Inspection Listing Plant: Catawba 1 08/16/2005 Interval 2 Outage 7 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS B0l.011.001 1RPV-W03 NC 05/18/2005 CLR 72.76% N Y Request for Relief will be filed for the limitation.

B01.011.002 1RPV-W04 NC 05/18/2005 CLR 90.91% N N B01.011.003 I RPV-WO5 NC 05/18/2005 REC .-- N N B01.011.004 1RPV-W06 NC 05/21/2005 REC --- N N B01.021.001 1RPV-WO1 NC 05/19/2005 REC 87.19% N Y Request for Relief will be filed for the limitation.

B01.022.001 1RPV-W02-01 NC 05/19/2005 CLR .-. N N B01.022.002 1RPV-W02-02 NC 05/19/2005 CLR --- N N B01.022.003 1RPV-W02-03 NC 05/19/2005 REC --- N N 801.022.004 1RPV-W02.04 NC 05/19/2005 REC .-- N N B01.022.005 1RPV-W02-05 NC 05/19/2005 CLR --- N N 801.022.006 1RPV-W02-06 NC 05/19/2005 CLR --- N N 801.030.001 1RPV-W07 NC 05/21/2005 REC 99.21% N N B03.090.001 1RPV-W11 NC 05/21/2005 REC 95.19% N N B03.090.001 A 1RPV-W11 NC 05/19/2005 CLR 95.19% N N B03.090.002 1RPV-W12 NC 05/21/2005 REC 95.19% N N B03.090.002A 1RPV-W12 NC 05/19/2005 CLR 95.19% N N B03.090.003 1RPV-W13 NC 05/21/2005 REC 95.19% N N B03.090.003A 1RPV-W13 NC 05/19/2005 CLR 95.19% N N B03.090.004 1RPV-W14 NC 05/21/2005 CLR 95.19% N N B03.090.004A 1RPV-W14 NC 05/19/2005 CLR 95.19% N N B03.090.005 1RPV-W15 NC 05/21/2005 CLR 94.30% N N 803.090.005A 1RPV-W15 NC 05/19/2005 REC 94.30% N N 803.090.006 1RPV-W16 NC 05/21/2005 CLR 94.30% N N B03.090.006A 1RPV-W16 NC 05/19/2005 CLR 94.30% N N B03.090.007 1RPV-W17 NC 05/21/2005 CLR 94.30% N N B03.090.007A 1RPV-W17 NC 05/19/2005 REC 94.30% N N 803.090.008 1RPV-W18 NC 05/21/2005 CLR 94.30% N N B03.090.008A 1RPV-W18 NC 05/19/2005 CLR 94.30% N N B03.100.001 1RPV-W11 NC 05/16/2005 CLR --- N N B03.100.002 1RPV-W12 NC 05/16/2005 CLR -.- N N B03.100.003 1RPV-W13 NC 05/16/2005 CLR .-- N N B03.100.004 1RPV-W14 NC 05/16/2005 CLR -.- N N B03.1 00.005 1RPV-W15 NC 05/16/2005 CLR --- N N B03.100.006 1RPV-W16 NC 05/16/2005 CLR --- N N B03.100.007 1RPV-W17 NC 05/16/2005 CLR - N N B03.100.008 1RPV.W18 NC 05/16/2005 CLR .-. N N

DUKE ENERGYr 'ORATION QUALITY ASSURANCE iNICAL SERVICES In-Service Inspection Database Management System Run D EOC 15 Page 2 Catawba 1 Inservice Inspection Listing Plant: Catawba 1 Interval 2 Outage 7 08/16/2005 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS B03.110.001A 1PZR-W1 NC 05/17/2005 CLR 77.20% Y Request for Relief will be filed for the limitation.

B03.110.004A 1PZR-W4A NC 05/26/2005 CLR 79.20% Y Request for Relief will be filed for the limitation.

B03.1 10.005 1PZR-W4B NC 05/26/2005 CLR 79.20% Y Request for Relief will be filed for the limitation.

B03.110.006A IPZR-W4C NC 05/26/2005 CLR 79.20% Y Request for Relief will be filed for the limitation.

B03.120.001A 1PZR-W1 NC 05/17/2005 CLR ... N B03.120.004A 1PZR-W4A NC 05/26/2005 CLR N B03.120.005 1PZR-W4B NC 05/26/2005 CLR N B03.120.006A 1PZR-W4C NC 05/26/2005 CLR N B03.140.005 1SGC-INLET NC 05/13/2005 CLR N B03.140.006 1SGC-OUTLET NC 05/13/2005 CLR ... N B05.010.001 1RPV-W11-SE NC 05/18/2005 CLR 97.35% N 97.35%

B05.010.001A 1RPV-W11-SE NC 05/18/2005 CLR N B05.010.001B 1RPV-W11-SE NC 05/24/2005 CLR N B05.010.002 1RPV-W12-SE NC 05/18/2005 CLR 98.56% N B05.010.002A 1RPV-W12-SE NC 05/18/2005 CLR 98.56% N B05.010.002B 1RPV-W12-SE NC 05/24/2005 CLR ... N 805.010.003 1RPV-W13-SE NC 05/18/2005 CLR ... N B05.010.003A 1RPV-W13-SE NC 05/18/2005 CLR ... N 805.010.0036 1RPV-W13-SE NC 05/24/2005 CLR ... N 805.010.004 1RPV-W14-SE NC 05/18/2005 CLR 92.31% N B05.010.004A 1RPV-W14-SE NC 05/18/2005 CLR 92.31% N B05.010.0046 1RPV-W14-SE NC 05/24/2005 CLR ... N B05.010.005 1RPV-W15-SE NC 05/18/2005 CLR 93.20% N B05.010.005A 1RPV-W15-SE NC 05/18/2005 CLR 93.20% N B05.010.006 1RPV-W16-SE NC 05/18/2005 CLR 95.73% N 805.010.006A 1RPV-W16-SE NC 05/18/2005 CLR 95.73% N B05.010.007 1RPV-W17-SE NC 05/17/2005 CLR 90.82% N 605.010.007A 1RPV-W17-SE NC 05/17/2005 CLR 90.82% N B05.010.008 1RPV-W18-SE NC 05/18/2005 REC 82.45% Y Request for Relief will be filed for the limitation.

Reference Catawba Plant Engineering Calculation

1. CNC-1201.01-00-0025 for indication detected during EOC15.

B05.010.008A 1RPV-W18-SE NC 05/18/2005 REC 82.45% N Y Request for Relief will be filed for the limitation.

Reference Catawba Plant Engineering Calculation

1. CNC-1201.01-00-0025 for indication detected during EOC15.

Rnc; n7n nnc; 1SGC-INLET-W5SE NC 05/13/2005 CLR 92.60% N N

(

DUKE ENERGY q ORATION QUALITY ASSURANCE 1 YICAL J SERVICES In-Service Inspection Database Management System Run D EOC 15 Catawba 1 Inservice Inspection Listing Page 3 Plant: Catawba 1 08/16/2005 Interval 2 Outage 7 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS B05.070.005A 1SGC-INLET-W5SE NC 05/13/2005 CLR N N B05.070.006 1SGC-OUT-W6SE NC 05/13/2005 CLR 92.60% N N B05.070.006A 1SGC-OUT-W6SE NC 05/13/2005 CLR 5.. N N B05.130.001 1NC22-01 NC 05/18/2005 CLR 95.73% N N B05.130.001 A 1NC22-01 NC 05/18/2005 CLR 95.73% N N B05.130.004 1NC22-08 NC 05/18/2005 CLR 98.56% N N B05.130.004A 1NC22-08 NC 05/18/2005 CLR 98.56% N N B05.130.004B 1NC22-08 NC 05/24/2005 CLR ... N N B05.130.005 1NC23-01 NC 05/18/2005 REC 82.45% N Y Request for Relief will be filed for the limitation.

Reference Catawba Plant Engineering Calculation

1. CNC-1201.01-00-0025 for Indication detected during EOC15.

B05.130.005A 1NC23-01 NC 05/18/2005 REC 82.45% N Y Request for Relief will be filed for the limitation.

Reference Catawba Plant Engineering Calculation

1. CNC-1201.01-00-0025 for indication detected during EOCI5.

B05.130.008 1NC23-08 NC 05/18/2005 CLR 92.31% N N B05.130.008A 1NC23-08 NC 05/18/2005 CLR 92.31% N N B05.130.008B 1NC23-08 NC 05/24/2005 CLR ... N N 805.130.009 1NC24-01 NC 05/18/2005 CLR 93.20% N N B05.130.009A 1NC24-01 NC 05/1812005 CLR 93.20% N N B05.130.012 1NC24-08 NC 05/18/2005 CLR 97.35% N N B05.130.012A 1NC24-08 NC 05/18/2005 CLR 97.35% N N B05.130.012B I NC24-08 NC 05/24/2005 CLR ... N N B05.130.013 1NC25-01 NC 05/17/2005 CLR 90.82% N N B05.130.013A I NC25-01 NC 05/17/2005 CLR 90.82% N N B05.130.016 1NC25-08 NC 05/18/2005 CLR ... N N B05.130.016A 1NC25-08 NC 05/18/2005 CLR ... N N B05.130.016B 1NC25-08 NC 05/24/2005 CLR ... N N B06.110.007 1SGD-MW-Y1 -X2 NC 05/17/2005 CLR ... N N 606.110.008 1SGD-MW-X2-Y2 NC 05/17/2005 CLR N N B07.050.056 1NV614-MJ1 NV 05/10/2005 CLR N N B07.050.057 1NV615-MJ1 NV 05/10/2005 CLR N N 807.070.023 1NI-125 NI 05/16/2005 CLR N N B07.070.024 1NI-126 NI 05/24/2005 CLR N N B09.011.020 1NC30-2 NC 05/21/2005 CLR N N MOA nAltV)nA I Kirlin.9 NC 05/21/2005 CLR N N

EOC 15 DUKE ENERGY QUALITY ASSURANCE

- 'ORATION

,NICAL SERVICES In-Service Inspection Database Management System C Run D Page 4 Catawba 1 Inservice Inspection Listing Plant: Catawba 1 08/16/2005 Interval 2 Outage 7 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS .

B09.011.021 1NC30-3 NC 05/21/2005 CLR 96.40% N B09.011.021A 1NC30-3 NC 05/21/2005 CLR ... N B09.011.024 1NC32-2 NC 05/18/2005 CLR ... N B09.011.024A 1NC32-2 NC 05/17/2005 CLR N B09.011.025 1NC32-3 NC 05/18/2005 CLR N B09.011.025A 1NC32-3 NC 05/17/2005 CLR N B09.011.026 1NC32-4 NC 05/18/2005 CLR N B09.011.026A 1NC32-4 NC 05/17/2005 CLR N B09.011.027 1NC32-6 NC 05/18/2005 CLR N B09.011.027A 1NC32-6 NC 05/17/2005 CLR N B09.011.048 1NC286-1 NC 05/19/2005 CLR 37.50% Y Request for Relief will be filed for the limitation.

B09.011.048A 1NC286-1 NC 05/19/2005 CLR N B09.011.156 1Nl32-3 NI 05/18/2005 CLR N B09.011.156A 1N132-3 NI 05/18/2005 CLR N B09.011.157 1N132-4 NI 05/18/2005 CLR N B09.011.157A 1Nl32-4 NI 05/18/2005 CLR N 609.011.158 I Nl32-5 NI 05/18/2005 CLR 93.60% N 609.011.158A 1Nl32-5 NI 05/18/2005 CLR N B09.011.192 1Nl240-8 NI 05/18(2005 CLR N B09.011.192A 1N1240-8 NI 05/18/2005 CLR N B09.011.193 1Nl240-10 NI 05/18/2005 CLR N B09.011.193A 1Nl240-10 NI 05/18/2005 CLR N B09.011.194 1NI240-11 NI 05/18/2005 CLR N B09.011.194A 1Nl240-11 NI 05/18/2005 CLR N B09.021.001 1NC22-12 NC 05/22/2005 CLR N B09.021.002 1NC22-16 NC 05/22/2005 CLR N B09.021.009 1NC41-15 NC 05/14/2005 CLR N B09.021.010 1NC42-1 NC 05/17/2005 CLR N B09.021.011 I NC43-11 NC 05/14/2005 CLR N 609.021.012 1NC50-25 NC 05/15/2005 CLR N B09.021.013 1NC50-26 NC 05/15/2005 CLR N B09.021.014 1NC51-1 NC 05/15/2005 CLR N B09.021.015 1NC56-1 NC 05/15/2005 CLR N B09.021.103 1NV31 0-1 NV 05/17/2005 CLR N B09.021.104 1NV310-2 NV 05/17/2005 CLR N B09.031.002 1NC22-WN8 NC 05/27/2005 CLR N

DUKE ENERGY r EOC 15

'ORATION QUALITY ASSURANCE_ .NICAL SERVICES In-Service Inspection Database Management System Catawba 1 Inservice Inspection Llsting

( Run D Page 5 Plant: Catawba 1 08/16/2005 Interval 2 Outage 7 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS B09.031.002A 1NC22-WN8 NC 05/22/2005 CLR B09.032.051 1NI10-2 NI 05/11/2005 CLR B09.032.052 1N1147-3 NI 05/11/2005 CLR 96.90%

B09.040.001 1NC24-12 NC 05/22/2005 CLR B09.040.002 1NC41-36 NC 05/14/2005 CLR B09.040.003 1NC41-37 NC 05/14/2005 CLR B09.040.004 1NC41-35 NC 05/14/2005 CLR 809.040.005 1NC42-5 NC 05/14/2005 CLR .-

B09.040.006 1NC43-8 NC 05/14/2005 CLR ...

B09.040.007 1NC50-6 NC 05/15/2005 CLR B09.040.008 1NC50-29 NC 05/15/2005 CLR ...

B09.040.009 1NC50-30 NC 05/15/2005 CLR ...

B09.040.010 1NC51-2 NC 05/15/2005 CLR ...

B09.040.011 1NC81-21 NC 05/10/2005 CLR ..

B09.040.012 1NC82-5 NC 05/10/2005 CLR B09.040.022 1NC245-9 NC 05/27/2005 CLR B09.040.067 1N1240-4 NI 05/18/2005 CLR B09.040.068 1N1240-6 NI 05/18/2005 CLR B09.040.069 1N1243-1 NI 05/15/2005 CLR 6.30%

B09.040.070 1N1245-3 NI 05/20/2005 CLR B09.040.071 1N1247-7 NI 05/10/2005 CLR 909.040.108 1NV483-3 NV 05/12/2005 CLR 809.040.109 1NV483-7 NV 05/12/2005 CLR B09.040.110 1NV483-8 NV 05/12/2005 CLR B09.040.111 1NV483-9 NV 05/12/2005 CLR B09.040.112 1NV483-14 NV 05/12/2005 CLR N B12.040.002D 1ND-37A ND 05/25/2005 CLR Y Request for Relief will be filed for the limitation.

B12.050.002B 1NC-29 NC 05/14/2005 CLR N B12.050.007E INI-175 NI 05/14/2005 CLR N B13.010.001 1RPV-INTERIOR NC 05/16/2005 CLR N B13.060.001 1RPV-CLEVIS 05/16/2005 CLR N B13.060.002 1RPV-INCORE 05/16/2005 CLR N B13.070.001 1RPV-CORE-SUP 05/20/2005 CLR N B14.010.001 1RPV-CRDM64 05/19/2005 CLR N B14.010.002 1RPV-CRDM72 05/19/2005 CLR N B314.010.003 1RPV-CRDM77 05/19/2005 CLR N

DUKE ENERGYC 'ORATION EOC 15 QUALITY ASSURANCE INICAL SERVICES In-Service Inspection Database Management System

( Run D Catawba 1 Inservice Inspection Listing Page 6 Plant: Catawba 1 08116/2005 Interval 2 Outage 7 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS C01.020.013 1SGD-Wi44 NC 05/23/2005 CLR ... N N C02.021.004 1ANSHX-3-N1 NS /1l ... N N The NDE for this Item Number was not performed during Outage

1. 7 (EOC1 5), per NSM# CN-1 1432101 (1A NS Heat Exchanger Replacement).

C02.021.004A 1ANSHX-3-N1 NS I' N N The NDE for this Item Number was not performed during Outage

1. 7 (EOC15), per NSM# CN-1 1432/01 (IA NS Heat Exchanger Replacement).

C02.021.005 1ANSHX-3-N2 NS Il N N The NDE for this Item Number was not performed during Outage

1. 7 (EOC15), per NSM# CN-11432/01 (IA NS Heat Exchanger Replacement).

C02.021.005A 1ANSHX-3-N2 NS /1 N N The NDE for this Item Number was not performed during Outage

1. 7 (EOC15), per NSM# CN-1 1432/01 (IA NS Heat Exchanger Replacement).

C03.020.01 0 1-R-FW-0002 FW 05/03/2005 CLR N N C03.020.015 1-R-ND-0165 ND 04/27/2005 CLR N N C03.020.025 1-R-NI-0285 NI 04/27/2005 CLR N N C03.020.026 1-R-NI-0286 NI 05/06/2005 CLR N N C03.020.027 1-R-NI-1195 Ni 05/21/2005 CLR N N C03.020.052 1*R-NV-0433 NV 05/03/2005 CLR ... N N C03.020.094 1-R-SM-1008 SM 05/29/2005 CLR 98.00% N N C03.020.095 1-R-SM-1018 SM 05/29/2005 CLR ... N N C03.020.096 1-R-SM-1028 SM 05/29/2005 CLR ... N N C03.020.097 1-R-SM-1038 SM 05/29/2005 CLR ... N N C03.040.001 1-R-SV-1519 SV 05/26/2005 CLR ... N N C03.040.002 1-R-SV-1612 SV 05/26/2005 CLR N N C03.040.003 1-R-SV-1512 SV 05/26/2005 CLR ... N N C03.040.004 1-R-SV-1616 SV 05/26/2005 CLR ... N N C03.040.005 1-R-SV-1505 SV 05/26/2005 CLR N N C03.040.006 1-R-SV-1610 SV 05/26/2005 CLR N N C03.040.007 1-R-SV-1 526 SV 05/26/2005 CLR N N C03.040.008 1-R-SV-1608 SV 05/26/2005 CLR N N C05.011.039 1ND13-1 ND 05/01/2005 CLR N N C05.011.039A 1ND1 3-1 ND 04/30/2005 CLR N N C05.011.040 1ND13-5 ND 05/01/2005 CLR N N C05.011.040A 1ND13-5 ND 04/30/2005 CLR N N C05.011.041 1ND13-11 ND 05/01/2005 CLR N N C05.011.041A 1ND13-11 ND 04/30/2005 CLR N N

DUKE ENERGY - '-PORATION EOC 15 QUALITY ASSURANCE INICAL SERVICES In-Service Inspection Database Management System Catawba I Inservice Inspection Listing

( Run D Page 7 Plant: Catawba 1 08/16/2005 Interval2 Outage 7 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS C05.011.042 1ND14-1 ND 05/01/2005 CLR --- N N C05.011.042A 1ND14-1 ND 04/30/2005 CLR --- N N C05.011.043 1ND14-7 ND 05/01/2005 CLR .-- N N C05.011.043A 1ND14-7 ND 04/30/2005 CLR --- N N C05.011.044 1ND14-8 ND 05/01/2005 CLR .-- N N C05.011.044A 1ND14-8 ND 04/30/2005 CLR --- N N C05.011.049 1ND39-12 ND 05/20/2005 CLR 76.10% N Y Request for Relief will be filed for the limitation.

C05.011.049A 1ND39-12 ND 05/20/2005 CLR --- N N C05.011.067 1ND13-10 ND 05/01/2005 CLR --. N N C05.011.067A 1ND13-10 ND 04/30/2005 CLR --- N N C05.011.114 1N16-6 NI 05/12/2005 CLR --- N N C05.011.114A 1N16-6 NI 05/12/2005 CLR --- N N C05.011.115 1N16-7 NI 05/12/2005 CLR --- N N C05.011.115A 1N16-7 NI 05112/2005 CLR --- N N C05.011.118 1N16-13 NI 05/12/2005 CLR --. N N C05.011.118A 1NI6-13 NI 05/12/2005 CLR --- N N C05.011.119 1N16-22 NI 05/12/2005 CLR --- N N C05.011.1 19A 1N16-22 NI 05/12/2005 CLR --- N N C05.021.107 1NV97-7 NV 05/04/2005 CLR --- N N C05.021.107A 1NV97-7 NV 05/04/2005 CLR --- N N C05.021.108 1NV97-8 NV 05/04/2005 CLR --- N N C05.021.108A 1NV97-8 NV 05/04/2005 CLR .-- N N C05.021.109 1NV97-12 NV 05/04/2005 CLR -.- N N C05.021.109A 1NV97-12 NV 05/04/2005 CLR --- N N C05.021.110 1NV97-10 NV 05/04/2005 CLR --- N N C05.021.11OA 1NV97-10 NV 05/04/2005 CLR --- N N C05.021.140 1NV627-1 NV 05/05/2005 CLR .-- N N C05.021.140A 1NV627-1 NV 05/04/2005 CLR --- N N C05.021.141 1NV627-2 NV 05/05/2005 CLR --. N N C05.021.141A 1NV627-2 NV 05/04/2005 CLR --- N N C05.021.142 1NV627-5 NV 05/05/2005 CLR .-- N N C05.021.142A 1NV627-5 NV 05/04/2005 CLR --- N N C05.021.143 1NV627-6 NV 05/05/2005 CLR --- N N C05.021.143A 1NV627-6 NV 05/04/2005 CLR --- N N C05.021.144 1NV627-1 1 NV 05/0512005 CLR --- N N C05.021.144A 1NV627-11 NV 05/04/2005 CLR --- N N

DUKE ENERGY r "ORATION EOC 15 QUALITY ASSURANCE NICAL SERVICES In-Service Inspection Database Management System (7 Run D Page 8 Catawba 1 Inservice Inspection Listing Plant: Catawba 1 08/16/2005 Interval 2 Outage 7 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS C05.021.145 1NV627-12 NV 05/05/2005 CLR -- N N C05.021.145A 1NV627-12 NV 05/04/2005 CLR -- N N C05.051.055 1CF39-1 CF 05/22/2005 REC .. Y N C05.051.055A 1CF39-1 CF 05/21/2005 CLR -- N N C05.051.058 1CF39-2 CF 05/22/2005 CLR -- N N C05.051.058A 10CF39-2 CF 05/21/2005 CLR .. N N C05.051.059 1CF39-10 CF 05/22/2005 CLR -- N N C05.051.059A 10CF39-10 CF 05/21/2005 CLR -- N N C05.051.060 1CF39-11 CF 05/22/2005 CLR -- N N C05.051.060A 1CF39-11 CF 05/21/2005 CLR -- N N C06.020.016 1SA-1 SA 05/23/2005 CLR -- N N C06.020.019 ISV-16 SV 05/23/2005 CLR -- N N C06.020.020 1SV-23 SV 05/23/2005 CLR -- N N D02.020.009 1-R-CA-0185 CA 04/05/2005 CLR .. N N D02.020.010 1-R-CA.0274 CA 04/05/2005 CLR .. N N D02.020.011 1-R-CA-0246 CA 04/05/2005 CLR -- N N D02.020.036 1-R-LD-0053 LD 04/21/2005 CLR -- N N D02.020.061 1-R-RN-0611 RN 05/15/2005 CLR -- N N D02.020.062 1-R-RN-0629 RN 05/15/2005 CLR -- N N D02.020.063 1-R-RN-0807 RN 05/15/2005 CLR -- N N D02.020.064 1-R-RN-0825 RN 05/15/1905 CLR -- N N D02.040.027 1-R-KD-0090 KD 06/02/2005 CLR -- N N D02.040.028 1-R-KD-0057 KD 05/15/2005 CLR -- N N F01.010.091 1-R-NV-1470 NV 05/10/2005 CLR -- N N F01.010.092 1-R-NV-1471 NV 05/10/2005 CLR .N N F01.010.096 1-R-NV-1503 NV 05/10/2005 CLR -- N N F01.010.097 1-R-NV-1508 NV 05/10/2005 CLR -- N N F01.011.053 1-R-NI-1390 NI 05/10/2005 CLR -- N N F01.011.054 1-R-NI-1465 NV 05/10/2005 CLR -- N N F01.011.091 1-R-NV-1502 NV 05/10/2005 CLR -- N N F01.011.092 1-R-NV-1504 NV 05/10/2005 CLR -- N N F01.011.095 1-R-NV-1501 NV 05/10/2005 CLR -- N N F01.011.096 1-R-NV-1505 NV 05/10/2005 CLR -- N N F01.012.015 1-R-NC-1535 NC 05/10/2005 REC . -- N N F01.012.016 1-R-NC-1536 NC 05/10/2005 REC -- N N F01.020.011 1-R-CF-1500 CF 05/08/2005 CLR -- N N

DUKE ENERGY ( 'ORATION QUALITY ASSURANCE t .NICAL SERVICES In-Service Inspection Database Management System C Run D EOC 15 Page 9 Catawba 1 Inservice Inspection Listing Plant: Catawba 1 Interval 2 Outage 7 08/16/2005 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS F01.020.023 1-R-FW-0002 FW 05/03/2005 REC -.- N N F01.020.044 1-R-ND-0188 ND 04/20/2005 CLR .-- N N F01.020.045 1-R-ND-0523 ND 04/19/2005 CLR --- N N F01.020.046 1-R-ND.0186 ND 04/20/2005 CLR --- N N F01.020.047 1-R-ND-0187 ND 04/20/2005 CLR --- N N F01.020.048 I -RND-0170 ND 04/19/2005 CLR --- N N F01.020.049 1-R-ND-0171 ND 05/15/2005 CLR --- N N F01.020.050 1-R-ND-0172 ND 04/19/2005 CLR -.- N N F01.020.067 1-R-NI -2273 NI 05/10/2005 CLR --- N N F01.020.068 1-R-NI-2274 NI 05/10/2005 CLR --- N N F01.020.069 1-R-NI-2275 NI 05/10/2005 CLR -.- N N F01.020.104 1-R-NS-0058 NS 04/04/2005 CLR -.. N N F01.020.105 1-R-NS-0076 NS 04/04/2005 CLR --. N N F01.020.108 1-R-NS-0001 NS 04/19/2005 CLR --- N N F01.020.109 1-R-NS-0002 NS 04/19/2005 CLR --- N N F01.020.110 1-R-NS-0003 NS 04/19/2005 CLR --- N N FO1.020.111 1-R-NS-0037 NS 04/18/2005 CLR --- N N F01.020.112 1-R-NS-0038 NS 04/18/2005 CLR --- N N F01.020.113 1-R-NS-0039 NS 04/18/2005 REC --. N N F01.020.114 1-R-NS-0042 NS 04/18/2005 CLR -.- N N F01.020.115 1-R-NS-0043 NS 04/18/2005 CLR .-- N N F01.020.116 1-R-NS-0044 NS 04/18/2005 CLR --- N N F01.020.117 1-R-NS.0047 NS 04/18/2005 CLR --- N N F01.020.118 I -R-NS-0048 NS 04/18/2005 REC --- N N F01.020.119 1-R-NS-0049 NS 04/05/2005 CLR --. N N F01.020.155 1-R-NV-0316 NV 04/05/2005 CLR --- N N F01.020.156 1-R-NV-0318 NV 04/05/2005 CLR --- N N F01.020.157 1-R-NV-0131 NV 04/04/2005 CLR --- N N F01.020.158 1-R-NV-0135 NV 04/04/2005 CLR --- N N F01.020.159 1-R-NV-0137 NV 04/04/2005 REC .-. N N F01.020.160 1-R-NV-0143 NV 04/04/2005 CLR --- N N F01.020.161 1-R-NV-0293 NV 04/19/2005 CLR --- N N F01.020.162 1-R-NV-0294 NV 04/19/2005 CLR --- N N F01.020.163 1-R-NV-0296 NV 04/05/2005 CLR --- N N F01.020.164 1-R-NV-0298 NV 04/04/2005 CLR --- N N F01.020.165 1-R-NV-0300 NV 04/04/2005 CLR --- N N

DUKE ENERGY 'ORATION EOC 15 QUALITY ASSURANCE 1K .NICAL SERVICES In-Service Inspection Database Management Syste C( Run D Catawba 1 Inservice Inspection Listing Page 10 Plant: Catawba 1 08/16/2005 Interval 2 Outage 7 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR R COMMENTS F01.020.166 1-RNV-0301 NV 04104/2C105 CLR --- N N F01.020.193 1-R-SA-0003 SA 04/20/2CD05 CLR --- N N F01.020.223 1-RSV-1522 SV 05/08/2CD05 CLR --- N N F01.020.224 1-R-SV-1524 SV 05/08/2Cl05 CLR --- N N F01.021.001 1 R-CA-1654 CA 04/25/2CD05 CLR -- N N F01.021.011 1-RCF-1518 CF 05/15/2C)05 CLR --- N N F01.021.035 1-R-ND-0610 ND 04/19/2C)05 CLR --- N N F01.021.036 1-R-ND-0611 ND 04/20/2C105 CLR --- N N F01.021.071 1 R-NI-2271 NI 05/10/2CD05 CLR .-- N N F01.021.072 1-R-NI 2272 NI 05110/2C D05 CLR .-- N N F01.021.073 1-R-NI-2278 NI 05/10/2C105 CLR --- N N F01.021.098 1-R-NS-0033 NS 04/19/2CD05 CLR .-. N N F01.021.165 1-R-NV.0509 NV 04/04/2CD05 CLR --- N N F01.021.166 1-R-NV-0537 NV 04/04/2CD05 CLR --. N N F01.021.167 1-RNV-0538 NV 04/04/2CD05 CLR .-- N N F01.021.168 1-A-NV-3202 NV 04112/2C105 CLR --- N N F01.021.169 1 A-NV-3205 NV 04/12/2CD05 CLR --- N N F01.021.170 1-R-NV.0175 NV 04112/2C105 CLR --- N N F01.022.021 1 R-FW 0056 FW 04/19/2CD05 CLR --- N N F01.022.037 1-RND-0129 ND 04/19/2CD05 CLR --- N N F01.022.038 1-R-ND-0131 ND 04120/2C105 CLR --- N N F01.022.039 1-RND-0626 ND 04/20/2CD05 CLR --- N N F01.022.040 1 R-ND-0168 ND 04/19/2C)05 CLR --- N N F01.022.063 1-R-NI-2264 NI 05/10/2C )05 CLR .-- N N F01.022.092 1-RNS-0031 NS 04/20/2C)05 CLR --- N N F01.022.145 1-RNV.0315 NV 04/05/2C)05 CLR --. N N F01.022.147 1-R-NV-0319 NV 04/05/2C 105 CLR --- N N F01.022.148 1-R-NV.0015 NV 04/05/2C)05 CLR .-- N N F01.022.149 1 R8NV-0136 NV 04/05/2C105 CLR --- N N F01.022.150 1-R-NV.0508 NV 04/05/2C)05 CLR --- N N F01.022.221 1-R-SV-1514 SV 04/25/2C 05 CLR --- N N F01.030.090 1-R-KC-0875 KC 04/06/2C105 REP --- N N Reference PIFP#C 05-1591 in Section 1.0.

F01.030.092 1 R-KC-0184 KC 04/06/2C105 CLR --. N N F01.030.093 1 R-KC-0028 KC 04/25/2C105 CLR --- N N Added to OuWina #7 IFOC1 51 nar ARMF fqctinn XIL Parnnrnnh IWF-2430(a) and PIP #C.05-01591.

F01.030.094 1-RKC.0031 KC 04/25/2005 CLR N N Added to Outage #7 (EOC1 5) per ASME Section Xi, Paragraph IWF.MP-fl(s nnd PIP #0-05-01591.

EOC 15 (7- DUKE ENERGY QUALITY ASSURANCE .

'ORATION NICAL SERVICES In-Service Inspection Database Management System C Run D Catawba 1 Inservice Inspection Listing Page 11 Plant: Catawba 1 Interval 2 Outage 7 08/16/2005 ITEM NUMBER ID NUMBER SYSTEM INSP DA TE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS F01.030.124 1 R-LD-0051 LD 04/2112( 005 CLR --- N N F01.030.125 1-RLD-0053 LD 04/21/2( 005 CLR .-- N N F01.030.177 1-R.RN.0611 RN 05115/2( 305 CLR --- N N F01.030.178 1-R.RN.0629 RN 05/15/2( 005 CLR --- N N F01.030.179 1-R-RN.0810 RN 05/15/2( 005 CLR -.- N N F01.030.180 1-R-RN-0593 RN 06/02/2( )05 CLR --- N N F01.030.181 1-R-RN-0594 RN 06102/2(005 CLR -.. N N F01.030.191 1-R-SA-0015 SA 04/05/2(005 CLR --- N N F01.030.201 1-RTE-0024 TE 04/05/2(005 CLR .-. N N F01.030.202 1-RTE-0032 TE 04/05/2(305 CLR .-- N N F01.030.225 1-R-VN-0019 VN 06/02/2( 305 CLR .-. N N F01.030.254 1-RYC-0046 YC 05/15/2( 305 CLR --- N N F01.031.008 1-R-CA-0185 CA 04/0512( 305 CLR --- N N F01.031.009 1-R-CA-0274 CA 04/05/2( 305 CLR --- N N F01.031.010 1-RCA-0246 CA 04/05/2( 305 CLR --- N N F01.031.057 1-R-KC-0872 KC 04106/2(305 CLR .-- N N F01.031.058 1-R-KC-0873 KC 04/06/2(305 REC --- N N F01.031.059 I -R-KC-0874 KC 04/06/2(305 REC --- N N F01.031.060 1-R-KC-0876 KC 04/13/2(305 REC -.- N N Added to Outage #7 (EOC1 5) per ASME Section XI, Paragraph IWF-2430(a) and PIP #C-05-1591.

F01.031.153 1-R8RN-0753 RN 04/20/2005 CLR N N F01.031.156 1-R-RN.0807 RN 05/15/2005 CLR N N F01.031.157 1-R-RN-0825 RN 05/15/2005 CLR N N F01.031.158 1-RRN-0826 RN 04/20/2005 CLR N N F01.032.004 1 R-CA.0220 CA 04/05/2005 CLR N N F01.032.056 1-R-KC-0075 KC 04/20/2005 CLR N N F01.032.057 1-R-KC.0076 KC 04/20/2005 CLR N N F01.032.103 1-R-KD.0090 KD 05/23/2005 CLR N N F01.032.104 1-R-KD.0057 KD 05/15/2005 CLR N N F01.032.191 1-R-SA.0016 SA 04/05/2005 CLR N N F01.032.222 1-R-VN-0055 VN 04/06/2005 CLR N N F01.040.004 I RCPB.COLUMNS NC 05/29/2005 CLR N N F01.040.005 1RCPC-SUPPORT NC 05/09/2005 CLR N N F01.040.006 1SGA-COLUMNS NC 05/09/2005 CLR N N F01.040.011 1SGD-LATERALS NC 05/10/2005 CLR N N F01.040.107 1SGD-SUPPORT NC 05/27/2005 CLR N N 9^ a A 141^ ,F-fl e% > KI PI

DUKE ENERGY 'ORATION EOC 15 QUALITY O ASSURANCE NICAL SERVICES In-Service Inspection Database Management System C' Run D Page 12 Catawba 1 Inservice Inspection Listing Plant: Catawba 1 08/16/2005 Interval 2 Outage 7 ITEM NUMBER ID NUMBER SYSTEM INSP DATE INSP STATUS INSP LIMITED GEO REF RFR COMMENTS F01 .040.206 1RNPA-SUPPORT RN 04/12/2005 REC --- N N F01 .040.207 1RNSB-SUPPORT RN 05/04/2005 CLR -.- N N G02.001 .028 1SM33-01 SM 05/29/2005 CLR --- N N G02.001 .028A 1SM33-01 SM 05/28/2005 CLR ... N N G02.001 .029 1SM-4A-A SM 05/29/2005 CLR -.- N N G02.001 .029A 1SM-4A-A SM 05/28/2005 CLR -.- N N G02.001 .030 1SM33-02 SM 05/29/2005 CLR --- N N G02.001 .030A 1SM33-02 SM 05/28/2005 CLR .-. N N G02.001 .031 1SM-5A-A SM 05/29/2005 CLR --- N N G02.001 .031A 1SM-5A-A SM 05/28/2005 CLR .-- N N G02.001.032 1SM33-03 SM 05/29/2005 CLR .-. N N G02.001 .032A 1SM33-03 SM 05/28/2005 CLR --- N N H01 .001.001 1N1148-9 NI 05/20/2005 CLR --- N N H01.001.002 1NI148-9L NI 05/20/2005 CLR --- N N H01.001.003 1N1148-10 NI 05/20/2005 CLR .-- N N H01 .001.004 1NI148-10L NI 05/20/2005 CLR .-- N N H01 .001.005 1NI148-11 Ni 05/20/2005 CLR .-- N N H01 .001.006 1N1148-11L Ni 05/20/2005 CLR .-. N N H01 .001.007 1NI152-9 NI 05/20/2005 CLR -.- N N H01 .001.008 1NI152-9L NI 05/20/2005 CLR --- N N H01 .001.009 1N1152-10 NI 05/20/2005 CLR - N N H01 .001.010 1NI152-10L NI 05/20/2005 CLR --- N N H01.001.01 1 1NI152-11 NI 05/20/2005 CLR -.- N N H01 .001.012 1N1152-11L NI 05/20/2005 CLR .-- N N H01.001.013 1NI162-13 Ni 05/20/2005 CLR --. N N H01 .001.014 1NI162-13L NI 05/20/2005 CLR .-- N N H01.001.015 1NI162-14 NI 05/20/2005 CLR --- N N H01 .001.016 1NI162-14L NI 05/20/2005 CLR --- N N H01 .001.017 1N1163-15 NI 05/20/2005 CLR -- N N H01 .001.018 1NI163-15L NI 05/20/2005 CLR .-- N N H01 .001.019 1NI164-8 NI 05/20/2005 CLR .-- N N H01 .001.020 1NI164-8L NI 05/20/2005 CLR --- N N H01.001.021 1N1165-8 NI 05/20/2005 CLR --- N N H01 .001.022 1N1165-8L NI 05/20/2005 CLR .-. N N H01 .001.023 1NI165-9 NI 05/20/2005 CLR .-. N N H01.001.024 1N1165-9L NI 05/20/2005 CLR --. N N

Catawba 1 EOC15 ISI Visual Examination Data Sheets ITEM NUMBER F01.030.090

QAL-14 Form QAL-14A Revision 15 PAGE 1 OF 1 DUKE POWER COMPANY PROJECT Catawba fJ PSI [F] IS1 ISI VISUAL EXAMINATION VT-3 HANGERS UNIT 1 W.O. *~INSM L It -0 6-~7 PROCEDUREOAL-14 REV.

INSPECTOR LEVEL DATE VISUAL METHOD: E-6IRECT E REMOTE R ', - S-6 ° VISUAL AIDS M&TE SERIAL NUMBER SYSTEM STATUS: 5 HOT ffrOLD 5 OTHER (EXPLAIN IN COMMENTS)

S/R NUMBER REV. I.D. NUMBER Rigid Support ACTUAL SYSTEM TEMPERATURE ff-R - k -k 0 1-R-KC-0875 ' Amt.-c.,,+

RESULTS: 5 ACCEPTABLE &iNACCEPTABLE (REQUIRES NDE, EVALUATION OR REPAIR) (See sketch / Dwg Attached)

C C ) SEE ENGINEERING JUSTIFICATION ATTACHED (OPTIONAL)

IND. INDICATION NO. TYPE LENGTH WIDTH REMARKS J4 ' t k3 2L-OS 6os. pl,...1

£4uc's P& pu(e.J 4-9 f Ce.(s', .e-

_ PJP PIP______9_ ). q 0 2- O"o-F-2 - '030 4- -os MECHANICAL SHOCK SUPPRESSOR A B LIMIT STOP A B HOT SETTING N/A N/A ACTUAL TRAVEL (COMP/TENSION) lNIA COLD SETTING NIA NIA HYDRAULIC SHOCK SUPPRESSOR A B ACTUAL PISTON SETTING N/A N/A FLUID LEVEL NIA l N/A VARIABLE SPRING SUPPORTS A B HOT SETTING N/A N/A HOT LOAD N/A N/A COLD SETTING N/A N/A COLD LOAD N/A N/A ACTUAL PISTON SETTING N/A N/A LOAD IND. READING N/A N/A COMMENTS/DISPOSITION CONSTANT SUPPORT A B Note: Added to RFO #1 per IWF-2420(b)

Ref. PIP# 1-C93-0875 HOTLOAD N/A N/A 1S i5of o e#/ A A,-iwui e '1.

COLDLOAD N/A N/A yfsie C^S~$J~

e J

O~O'CC/e'-&q4Ci'J e- )I. lc PC, f P/,-'

POSITION IND. READING N/A N/A 4/f4 Z q-it-e-TOTAL NO. OF DIV. SCALE N/A N/A PIP: ElYES 5 NO lSERIAL NO. C-OS 1I S9/

FINAL REVIEW DATE ANII RW DATE I -- I L. MA4& 1( C

. r In$ M4 S-8o5 ITEM NUMBER F01.030.090 dig#I/Ar&

ITEM NO. SIZE LOT DESCRIPT ION ASTM BY NO. REO'D NUMBER T B FIG. 211N' SWAY STRUT ASSEMBLY. OPilo4 M1, I m-41728 W 0O-11Y2" F S.O. C. S. PIPe CLAMP 8 ,I/.2(IN _t___ 09R t 1 4 x 4 x .250 X 0oY4L6 s40 G B _R 4 1 1971 AS .

5 4.l 3/4- ultP5sO. cA51s. 34 4 0 __

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pc?('l;4Dl TJJE LS t vt U REFERNEDAIG DUK POWER OMPAN __ ~JCT AKW, LOCRTION PLSN DIRECTION _VMT. T LD. COLD LD. KHYDRO _F_ _TEDALLOW LD VERTICAL  ;~~__ _ _ _ _ -t_ _

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N..KY ANAYSI PRBLM ATRPT.19 CAMC NO. -DP. CO. CLRSS Cfl*D nwveIf-Nd 9-t- WIVED Q-A. to-90-M61 amrcwmnvo 4 A7^aNMq vn) _efmo r2-*7- 61Z,5/83 REfERENCE DRRWItfGS DUKE POWER COMPANY ,PIPE M 01-142-KCN94 REV.

K- _ _LN CATAW9A NUCLEAR 08ST^ 0TIO s M-12Zl-2/-

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_ . . .. .. SHEET I Of I I .

Catawba 1 EOC15 PIP #C-05-01591 J'roblem Invesligaliott P'rocess C(atawba Nulclear Staitoi l PIP Serial No: Action Category: LER No:: . Other Report:

K) lC-05-01591 __ 3 Problem Identification Discovered Time/Date: 10:43 03/2312005 Occurred Time/Date:

Unit(s) Affected:

Unit Mode %Power Unit Status Remarks I I 100 At power Svstem(s) Affected:

KC Component Cooling Affected Equipment (No Equipment Affected)

Location of Problem:

Bldg: AUX Column Line: 57-1111 Elev: 560 Location Remarks:

Method Used to Discover Problem:

"' inspections er Problem

Description:

ISI inspector (John Faris) noted damage to several pipe supports on the 6" 1A KC Miniflow line. Additional examination by engineering indicates that the damage is likely due to a system transient, the date of which is unknown.

Detail Problem

Description:

OSM Concurrence on operability assessment:

Based on my visual observations or the hangers, supports and piping associated with this PIP and my discussions with ENG (Fred Willis & Dave Ward) about the status of the inspections and work completed (still have one anchor bolt that will need to be addressed at a later time), I concur with the Operability Assessment as it is decsribed below.

Jimmy Burgess On Duty OSM Last Updated By: JEB5426: BURGESS, JAMES E Team: CLO5903 Group: OPS Date: 03/2312005 ISI inspector (John Faris) noted damage to several pipe supports on the 6" IA KC Miniflow line. Additional examination by engineering (Mark Shutt and Fred Willis) indicates that the damage is likely due to a system transient, the date of which is unknown. The support damage is detailed as follows:

Support I -R-KC-0S73:

The concrete anchors on the north side are pulled out about 3/8". The northwest anchor is loose and can be spun by hand.

Support I-R-KC-0874:

The lateral strut is misaligned by about 2' (down) at the clamp attachment point. The vertical support rods attach to the base plate for l-R-KC-0S75 "ich is damaged as noted.

Kdpport I-R-KC-0S75:

All four concrete anchors are pulled out to some extent. The west anchors are out about I 1/2". the cast anchors about 3/8" Support l-R-KC-0876:

0411212005 14:50 Page I PIP No: C-05-01591

IProblent Invie.stigation P'roces.%

Calan lba ,itclear Matagtiom is no disccrnablc damage to this support. but therc is paint chipped at the anchor washcrs that indicate the support was subjected to a shock Hact some point.

The OSM was notified of the situation and work requcsl 98340909 has been written to initiate repairs. Engineering is reviewing the pipe stress analysis to determine affect on system operability.

Originated By: MDS8363: SIIUTT. MARK D Team: DLW2990 Group: MCE Date: 03123/2005 Additional Information/OE Supports l-R-KC-0873, 1-R-KC-0874. l-R-KC-0875 and l-R-KC-0876 were found damaged in 1984 due to a water hammer. The damage included concrete anchors partially pulled out. This condition was documented in NCI CN-147.

During a visual ISI examination support l-R-KC-0875 was found damaged. The inspector noted that the base plate had separated from the ceiling about YW. Thbis condition was documented in PIP l-C93-0875.

Operability Assessment Component Affected The component affected is the IA KC pump mini-flow line between valves IKCC36 and I KCC38. Loss of this line would affect the 'A' train of KC. This line is Duke Class C, ASME Class 3 and is required to be operable per Catawba Technical Specification 3.7.7 Component Cooling Water (CCW) System.

Degraded Condition

,-- description above for degraded components.

Evluation The I A KC pump mini-flow line between valves I KCC36 and I KCC38 is covered by Unit I piping analysis problem KCY, calculation file CNC-1206.02-80-2025. The piping covered by this analysis problem was analyzed using the computer program Superpipe. This analysis model was modified to remove the vertical and lateral support functions of support I -R-KC-0873. the vertical support function of l-R-KC-0874 and the lateral support function of support I-R-KC-0875. Based on inspection and engineering judgment the lateral strut part of I-R-KC-0874 would still carry its design load. Also the minor damage noted on I -R-KC-0876 would not have prevented this support from carrying its design load. With the above support functions removed the problem was reanalyzed. The following design requirements were reviewed.

ASME Code Stresses - All pipe stresses were less than the Code allowables.

Valve Accelerations - All valve accelerations were less than the values considered in the valve design.

Pipe Sleeve Clearances - All pipe sleeve clearances were greater than the revised movements.

Functionality Pipe Stresses - All pipe stresses were less than the allowables required to show functionality.

Support Loads - All supports loads were less than the original design loads (Ref. Calculation CNC-1206.12-16-1113).

Conclusion Based on the above evaluation the piping covered by Unit I analysis problem KCY can be considered operable with the degraded hangers as noted above.

The changes to the analysis model and results were generated by Bill Callaway and reviewed by Fred Willis. The support load evaluation was performed by Bill Callaway and reviewed by Mark Shut.

-'-tus of Immediate Corrective Actions

"'-.drrcntly all of the supports have been repaired with the exception of support l-R-KC-0875. This support still has one anchor bolt that will not torque. This work was performed tinder W/O 98720840.

Page 2 PIP No: C-05-01591 0J/12)2005 14:50 041)212005 14.50 Page 2 PIPNo: C-0.5-01591

I'roIblent ha estigativInu I'rocs%

Catt ntit/Nuclear Station kWtiUpdated By: JIFW8363: WILLIS. JAMES F Team: GWI17828 Group: RES Datc: 03/23/2005 Extent of Condition Review:

A walk down was performed of all four mini-flow lines (IA. I B. 2A. 2B) in their entirely. from header to header on elevations 560 ad 577. In addition other portions of the KC system pipe and supports in the area were visually examined, including the essential header in the vicinity or thc mini-flow connections. No other discrepancies or unusual indications were noted. This condition is considered to be isolated to the IA mini-flow loop.

Last Updated By: MDSS363: SIIUT. MARK D Team: DLW2990 Group: MCE Date: 03/23/2005 Other Units/Comronents1SvstemqAreas Affected(Y.N.U): N Industry Plants Affected(Y'.N,U): N Immediate Corrective Actiorns:

OSM notified. Work request 98340909 written to initiate repairs.

Originated By: MDS8363: SHUTT, MARK D Team: DLW2990 Group: MCE Date: 03/23/2005 Immediate Corrective Action Documents / Work Orders:

Indiv Team Group Date Problem Identified By: MDS8363 DLW2990 MCE 03/23/2005 Problem Entered By: MDS8363 DLW2990 MCE 0312312005 Screening Action Category: 3 Root Cause performed? No OEP No:

Other Report Nos:

Event Codes:

FIO Equipment Damage Screening Remarks:

Screened by the Centralized Screening Team on March 28, 2005.

Originated By: DSMOSI I: MILLER (DSMOSII). DAVID S Team: PAM7334 Group: SRG Date: 0312812005 Assignments:

Responsible Groups(s) for Problem Evaluation: MCE Mechanical/Civil Eng Responsible Group for Present Operability: N/A Responsible Group for Report Support Info: N/A Responsible Group for Reportability: NIA

-ponsible Group for Overall PIP Approval: MCE Mechanical/Civil Eng SrSignatuied BD-yDM3 -_ RGr 0.3ate28/20'0 ..

I Screened By: DSM08 I PAM7334 SRG 03128/2005 PIP No: c-OS-V 1591 Page 3 04/12/2005 14:50 0J11212005 Page .} PIP No: C-05-01591

Pioblent Investigatiott I'ro'es, Present Operability Responsible Group: Status:

Sys/Comp Operable? (Y.N.C.E.T):

Required Mode:

Comments:

No Current Signatures For This Section Reportability Responsible Group: Status:

Problem Reportable(Y.N.E):

Reportable Per:

Comments:

No Current Signatures For This Section

'estigationReport:

Responsible Group: Act Date:

Investigator: Group:

Due Date:

Date Due to VP or Sta. Mgr:

Date Regulatory or Agency Rpt Due:

Date Investigation Report Approved:

NRC Cause Codes:

Report Support Info:

Responsible Group: Status:

No Current Signatures For This Section Problemii Evaluation je t': .  :-Cau Des u 'n-",l  ; iirnay .. Caustngi6 ips Problem Evaluation From:Resp. Group: MCE Status: Open OEDB Checked: No

, 41APLATE FOR CAT 3 PROBLEM EVALUATIONS To meet the minimum expectations for a Category 3 PIP Problem Evaluation this section must include the following. Reference NSD 208 (Section 208.10) and NSD 212 (Section 212.6.2).

P11' No: C.05-0 1591 Pare 4 14:50 04/12/2005 14.50 04112no00s Page 4 rlrlvo: C-05-01591

Prolelmw Inrextiga7tiot Proce.s

,Nuclear Station Caraii-ba

\q.brting Information- (ltis section is not mandatory but may he used to provide additional information to hetter define the problem.)

jh. -

Apparent Cause- (Clearly statc why the problem occurred and causing group.)

Corrective Actions- (Stale the actions taken or needed to address the problem. Ensure actions align with the cause.)

Notes:

-Verify event codes are correct. If additional event codes need to be added or existing event codes need to be changed. contact SRG at extension 3972 or 3973.

-NMak-e sure cause code matches the apparent cause. Select down to at least the second level of cause code. (Ex. Choose "F13 or 1F3e" instead of F")

-Make sure the correct culpable group is selected based on the group this is designated as causing the event as stated in the apparent cause.

-Additional guidance and detail for addressing these items is contained in the help (blue text) section above.

Originated By: SITECOOR: SITE COORDINATOR Team: Group: SRG Date: 03/29/2005 OEDB Comments:

\k1cmarks Comments:

Due Date: 04122/2005 Accepted By: TIM8390 GTH7317 MCE 03/29(2005 Assigned To: JFM9986 SMS838 I MCE 03/29/2005 Corrective Actions CA Seq. No: 1

[StRisK~~s' Oi roii upkvelv.7~'itu dA.& . . _Gis Cd I MCE Closed MCE FIO Q YYY Proposed Corrective Action:

Perform and document an extent of condition review for the failure identified in this pip. Work orders initiated as a result of the extent of condition review should initially be coded as "E" and follow the work control process for urgent work with a date specified for the work order to be completed.

Originated By: TIM8390: MC KINNEY, TIMOTHY Team: GTH7317 Group: MCE Date: 03/2912005

,Si nature ......- z-' i; - o.. .2 'i. t -roup

• Date '

T7-:' -'-"-

Ready For Approval: TIM8390 GT117317 MCE 03129/2005 Approval Assigned To: GT117317 GT117317 NMCE 03/29/2005 Unproved By: TIM8390 GTH7317 MCE 03/29/2005 K-I Genernl:Outage: Mode:

Other Tracking Processes 0411212005 14:50 Page 5 PIPNo: C-05-01591

Problem InIestigalioi: Procevs Cotaaivba Nuclear.Sialonh, KJ Number Text Actual Corrective Action:

Priority: 12 Actual CAC: Q Status: Closcd Duc Date: 06/W9/2005 Extent of Condition Review (originally documented in Problem Description 3/23/2005):

A walk down was performed of all four mini-flow lincs (I A. I B. 2A. 2B) in thcir entircty. from hcader to header on elevations S60 and 577. In addition other portions of the KC system pipe and supports in the area were visually examined, including the essential header in the vicinity of the mini-flow connections. No other discrepancies or unusual indications were noted. nis condition is considered to be isolated to the IA mini-flow loop.

Originated By: MDS8363: SIHUTT. MARIK D Team: DLW2990 Group: NICE Date: 03/30/2005 Accepted By: TIM8390 GTH7317 MCE 03/29/2005 Assigned To: MDS8363 DLW2990 MCE 03/29/2005 Due Date: 06129/2005 Ready For Approval: MDS8363 DLW2990 MCE 03/30/2005 Approval Assigned To: DLW2990 DLWV2990 MCE 03/30/2005 Approved By: DLN%'2990 DLW2990 MCE 04/05/2005 Fi ial and Overall PIPApproval ponsibleGroup: MCE Status: Screened l.Signha tiiea~pA t*/ < Gr _~ ~;i:.; Date AssignedTo: MCE 03/28/2005 Any Supplemental Concurrence Signatures Above Do Not Affect PIP Closure.

Closure Document Tvpe Closure Document No Attachments GenericApplicability Responsible Group: Status:

GO PIP No:

Assessment Remarks:

No Current Signatures For This Section FailurePreventionInvestigation No FPI Records for this PIP.

Remarks No Remarks for this PIP.

Maintenance Ride Responsible Group: MCE Status: Open 04112/200.5 14.-50 Page 6 PIPNo: C-05-01591

Prolbezi, Iestigatinl lie Process Ciatte a Nuclear Start fbi Maintenance Rule .SC Risk Primary SSC Description Rin S stim

. n ' Significante SstemN KC ComponenitCooling .. ._

__ _ _..-- No---- _

Equipment Group:

Applicable Unit:

Functional Failurc: Yes MPFF: No Repetitive M PFF: No Functional Failure Comments:

MPFF Comments:

Repetitive MlPFFCormrnents:

Reactor Trip: No Safety System Actuation: No Loss of Heat Decay Removal: 'No Force Outage Rate or Plant Transient: No Loss Of Spent Fuel: No iments:

Asine To: . J1ndMv - - Cite S 3.'.4-I . N->E .:1 -0312912005 I.-: '-?

I Assigned To: JFM9986 SMS8381 MCE 03/29/2005 1 End of the Document for PIP No: C-5-1591 The status of this PIP is: Screened The duration of this PIP was: 5 days Page 7 PIP No: C-05-01591 0411212005 14:50 04/12/2005 14:50 Pmage 7 PIPNo: C-05-01591

<v Catawba 1 EOC15 PIP #C-05-02956 K>

Problem Investigation Process Catawba NuclearStation KU RM IC-05-02956 4 Problem Identification Discovered Time/Date: 19:20 05/20/2005 Occurred Time/Date:

Unit(s) Affected:

Unit Mode %Power Unit Status Remarks I NOMODE IEOC15 System(s) Affected:

NC Reactor Coolant Affected Equipment ICNINCRXOOOI I NC RX 0001 47611 l Location of Problem:

Bldg: RX Column Line: Elev:

Location Remarks:

• iodUsed to Discover Problem:

Brief Problem

Description:

Ultrasonic examinations performed by Westdyne during the IEOC 15, 10 yr RV ISI have identified five recordable indications in the Unit I reactor vessel, hot leg ID nozzle to safe end weld region.

Detail Problem Descrintion:

Ultrasonic examinations performed by Westdyne during the IEOCI5, 10 yr RV ISI have identified five recordable indications in the Unit I reactor vessel, hot leg ID nozzle to safe end weld region. These indications arc surface connected on the interior of the piping in the region of the weld between the carbon steel nozzle forging and the stainless steel buttered safe end. Looking out from the RV centerline, (with 0 deg at the top of the piping) all five indications are between 86 and 100 deg. All flaws are axially oriented. Eddy current has confirmed these indications.

The connection between the RV nozzle and the reactor coolant piping was made by buttering the carbon steel (SA508 Class 2) nozzle with a 309S material. A 308L (low carbon) stainless steel safe end was applied via weld buildup over the buttering. Circumferential Inconel bands were then placed on the inside and outside surfaces. These bands served to reduce the susceptibility of the 309S material to stress corrosion cracking related to the sensitization of the 309S, SS material after RV post weld heat treatment. The safe end was then welded to the cast austenitic stainless steel reactor coolant loop piping. All of these flaws are located within the Inconel band on the inside surface of the piping / nozzle.

Based on Westdyne sizing techniques, four of these five flaws have been evaluated and accepted under ASME XI, IWVB-3500 acceptance standards.

The remaining flaw has been characterized with a length of 0.89" long and a depth of 0.25". A penalty of 0.064" must be applied to the flaw depth based on the current limitations of sizing ability, thus yielding a 0.31" deep flaw. The initial review of this flaw indicates that the flaw exceeds the IWB-3500 acceptance standards. Further review of this indication is necessary to evaluate the flaw characteristics in conjunction with the applied internal SS and Inconel vessel and nozzle cladding and determine if this flaw is reportable (ie exceeds the ASME Xl acceptance limits).

This PIP should be screened as Category 4. A corrective action is needed to review the Westdyne characterization of the remaining flaw and determine if ASME Xl, IWB-3500 acceptance limits are satisfied. Corrective action should be completed prior to MODE 4.

Kginated By: WOC8363: CALLAWAY, WILLIAM 0 Team: DLW2990 Group: MCE Date: 05/2012005 Other Units/Components1Svstems/Areas Affected(YN.U': N Page I PIP No: C-05-02956 081/Ol7O05 17.02 08/0)r2005 17.^02 PageI PIPNo:C-0S-02956

Problem Investigation Process Catawba Nuclear Station y< stry Plants Affected(YNA): U Immediate Corrective Actions:

Imnmediate Corrective Action Documents / Work Orders:

mndiv Team Group Date Problem Identified By: W0C8363 DLW2990 MCE 05t20/2005 Problem Entered By: W0C8363 DLW2990 MCE 05/20/2005 Screening Action Category: 4 Root Cause performed? No OEP No:

Other Report Nos:

Event Codes:

FS Testing 02a ASME Section Xl Screening Remarks:

Screened by the centralized screening team on 5/23/05 K)Updated By: SRGADMIN: SRG Admin Team: Group: SRG Date: 05123/2005 Originated By: RSP5945: PURSLEY, R STEVE Team: PAM7334 Group: SRG Date: 05120/2005 Assignments:

Responsible Groups(s) for Problem Evaluation: Responsible Group for Present Operability: N/A Responsible Group for Report Support Info: N/A Responsible Group for Reportability: N/A Responsible Group for Overall PIP Approval: MCE Mechanical/Civil Eng l Screened By: RSP5945 PAM7334 SRG 0512012005 PresentOperability Responsible Group: Status:

Sys/Comp Operable? (Y,N,C,ET):

Required Mode:

\.Aimcnts:

No Current Signatures For This Section 081/Of2O05 17.02 Page2 PIP No: C-05-029S6

Problem Investigation Process CatawbaNuclearStation

-i8Portabilitv Responsible Group: Status:

Problem Reportable(Y,NE):

Reportable Per.

Comments:

No Current Signatures For This Section Investigation Report:

Responsible Group: Act Date:

Investigator: Group:

Due Date:

Date Due to VP or Sta. Mgr:

Date Regulatory or Agency Rpt Due:

Date Investigation Report Approved:

NRC Cause Codes:

t gort Support Info:

Responsible Group: Status:

No Current Signatures For This Section Problem Evaluation Problem Evaluation From: N/A CorrectiveActions CA Seq. No: 1 IMCE Closed SRG FS 133 R Proposed Corrective Action:

Rreview the Westdyne characterization of the remaining flaw and determine if ASME Xl, IWB-3500 acceptance limits are satisfied.

Corrective action should be completed prior to MODE 4.

,\"'ginated By: WOC8363: CALLAWAY, WTILLIAM 0 Team: DLW2990 Group: MCE Date: 05/20/2005 Entered By: RSP5945: PURSLEY, R STEVE Team: PAM7334 Group: SRG Date: 05/20/2005 08/0112005 17.02 Page 3 PIP No: C-05-02956

Problem Investigation Process Catawba NuclearStation

.GrI N-4roval Assigned To: PAM7334 PAM7334 SRG 052012005 Ready For Aproval: RSP5945 PAM7334 SRG 051202005 Approved By: RSP5945 PAM7334 SRG 05120/2005 `

General:Outage: lEOC15 Mode: 4 Other Tracking Processes TMne Number Text Actual Corrective Action:

Priority: 02 Actual CAC: N Status: Closed Due Date: 06/03/2005 A review of the Westdyne RV ISI call sheets was performed in Calculation CNC-1201.01-00-0025. Indication # 2 was evaluated and found acceptable in accordance with ASME Xl, IWB-3430. The acceptance standards of IWB-3514 were satisfied as documented in the calculation. No ASME Code required repairs, replacements, additional examrinations, successive examinations nor analytical evaluations are required.

An additional corrective action will be assigned to the MM&P group (NGO) to evaluate the potential exposure effects of the primary water environment to the sensitized stainless steel (309S) buttering resulting from the possibility that the indication extends entirely through the Inconel /

stainless cladding. Westinghouse has been contracted to support this effort.

Originated By: WOC8363: CALLAWAY, WILLIAM 0 Team: DLW2990 Group: MCE Date: 06/0112005 The subsequent corrective action is not a Mode 4 issue. The new CA will be a further action to pursue any work associated with longer term dispositioning that Duke may elect to take associated with the indications found this Outage. As stated above, all indications were of sufficient ted size to be determined as within the acceptance limits of the ASME Code with no followup actions required.

Last Updated By: DLW2990: WARD, DAVID L Team: DLW2990 Group: MCE Date: 06/01/2005 I n e u Due Date: 06/03/2005 Accepted By: TIM8390 GTH7317 MCE 05/2412005 Assigned To: WOC8363 DLW2990 MCE 05/24/2005 Approval Assigned To: DLW2990 DLW2990 MCE 06/0112005 Ready For Approval: DLW2990 DLW2990 MCE 06/0112005 Approved By: DLW2990 DLW2990 MCE 06/01/2005 CA Seq. No: 2 00 o Mcen I MMP Closed MCE 02a B3 R Proposed Corrective Action:

MM&P group (NGO) - David Whitaker - to evaluate the potential exposure effects of the primary water environment to the sensitized stainless steel (309S) buttering resulting from the possibility that the indication extends entirely through the Inconel / stainless cladding.

ariginated By: WOC8363: CALLAWAY, WILLIAM 0 Team: DLW2990 Group: MCE Date: 06/01/2005 This Corrective Action is not a restart issue for Catawba Unit 1. Reference response detailed in CA #1.

PIP No: C-05-02956 Page 4 0810112005 17:02 08/0)12005 17:02 Page4 PIPNo:C-05-029S6

Problem Investigation Process Catawba Nuclear Station Kj)

Last Updated By: DLW2990: WARD, DAVID L Team: DLW2990 Group: MCE Date: 06/0112005 Approval Assigned To: DLW2990 DLW2990 MCE 06/01/2005 Ready For Approval: DLW2990 DLWV2990 MCE 06/01/2005 Approved By: DLW2990 DLW2990 MCE 06101/2005 General:Outage: Mode:

Other Tracking Processes TIype Number Text Actual Corrective Action:

Priority: 12d Actual CAC: Status: Open DueDate: 11/16/2005 Accepted By: JMS8460 CTA7235 MMP 06/06/2005 Assigned To: DEW4981 CTA7235 MMP 06/06/2005 Due Date: 11/16/2005 Finaland Overall PIPApproval Responsible Group: MCE Status: Screened l AssignedTo: MCE 05/20/2005 Any Supplemental Concurrence Signatures Above Do Not Affect PIP Closure.

Closure Document Type Closure Document No Attachments GenericApplicability Responsible Group: Status:

GO PIP No:

Assessment Remarks:

No Current Signatures For This Section 17'qilure Prevention Investikation No FPI Records for this PIP.

Remarks No Remnarks for this PIP.

08101/2800S 17.02 PageS PIP No: C-05-02956

Problem Investigation Process Catawba Nuclear Station

'xydintenanceRule No Maintenance Rule Records for this PIP.

End of the Document for PIP No: C-5-2956 The status of this PIP is: Screened The duration of this PIP was: 0 days PIPNo: c-05-02956 Page 6 17:02 08/O)f2005 17.02 08/0l/2005 Page 6 PIP.No: C-05-02956

Catawba 1 EOC15 ISI Examination Data Sheettr ITEM NUMBERS B05.010.008, B05.010.008A, B05.130.005, B05.130.005A K>

WesDyne International K) Reactor Vessel Weld Results Summary CATAWBA UNIT 1 WELD NO. 1RP V-Wi8-SE DESCRIPTION OUTLET NOZZLE AND INC23-01 DM WELD @ 3380 (BO5.010.008 &

B05.010.008A)

AND (B05.130.005 &

B05.130.005A)

LIMITATIONS NODa YES X COVERAGE= 82.45%

Kmy RESULTS RI NO. OF INDICATIONS 5 STATUS 4 CODE ALLOWABLE AND 1 NON-ALLOWABLE EXAM DOCUMENTATION INDICATION DOCUMENTATION

[X] ANALYSIS LOG Ia ASSESSMENT SHEET X ACQUISITION LOG [XI PARAGON HARD COPY n3 SCAN PRINTOUT x OTHIER (specify)

INDICATION LOCATION SKETCH K) [X] COVERAGE BREAKDOWN WESDYNE ANALYST K742l4-

F wasDynE I"T 1* "AT IO-A Q CI Page I of I DATA ACQUISITION LOG # WN338-1 Utility: DUKE POWER Plant: I CATAWBA Unit: 1 Outage: IEOC15 Procedure No: I PDI-ISI-254-SE Procedure Rev. No.: 2 Applicable Sensitivity Calibration Data Sheet No: SE-01 UT Examiner Signature: l ( ___l_Level: III Date: 5/18/05 Data File Name Weld No. Index Scan Total # 'AVE' Gain . Date Time Comments Start Start of Signal AdJ. * .o Sweeps Amplitude (dB) °' (mmlddlyy) 0~

WN338-SE.PRP-DET.ON.CH.1 1RPV-W18-SE 0. 109.98- 374 43 0 DS 5/18105 08:47

& 1NC23-01 WN338.SE-PRP-DET-ON-CH.2 1RPV-W18-SE 0' 109.98- 374 10 o Os 5/18/05 08:47

& 1NC23-01 .

WN338-SE-PAR-DET-OWNCH.1 1RPV-W18-SE 122- 0' 70 12 - Ds 5/18/05 09:59

& 1NC23-01 WN338-SE-PAR.DET.ON-CH.2 1RPV-W18-SE 122 0' 70 13 0 DS 5/18/05 09:59

& 1NC23-01 Il Form 12.4 PDI.ISI.254-SE, Rev. I

WesDyne International Reactor Vessel Inservice Examination Scan Parameter Execution CUSTOMER .. ............. DUKE POWE1*

SITE ............... CATAWBA UNIT-1 i OUTAGE ...............lEOC15 VESSEL TYPE ............... Westinghouse 4-Loop WELD IDENTIFICATION - IRPV-W18-SE Weld and Scan Type = NOZZLE SAFE END PERPENDICULAR SCAN Scan Data File Name = WN338-SE-PRP-DET-ON SCAN AREA PER THE ORIGINAL TECHNIQUES UDRPS SCAN AREA DEFINITION AZIMUTH DEPTH (DEGREES) (IN)

START CW 179.90 109.98 END CCW -179.90 109.98 START CW 179.90 125.50 END CCW -179.90 125.50 Index Size (in) = 0.24 Number of Indexes Specified = 373 Number of Indexes Completed = 373 Time Date Scan Started 08:04:14.851 05/18/05 Scan Completed 08:45:34.936 05/18/05 Robot Operator Signature c ~ °DATE °S /9-Os PARAGON Operator Signature / Ad -1DATE A-Zg Comments

WesDyne International Reactor Vessel Inservice Examination Scan Parameter Execution CUSTOMER .. ............. DUKE POA SITE ............... CATAWBA UNIT-1 I OUTAGE ...............lEOC15 VESSEL TYPE ............... Westinghouse 4-Loop WELD IDENTIFICATION - IRPV-W18-SE Weld and Scan Type = NOZZLE SAFE END PARALLEL SCAN Scan Data File Name = WN338-SE-PAR-DET-ON SCAN AREA PER THE ORIGINAL TECHNIQUES UDRPS SCAN AREA DEFINITION DEPTH AZIMUTH (IN) (DEGREES)

START CW 122.00 179.90 END CCW 122.00 -179.90 START CW 127.50 179.90 END CCW 127.50 -179.90 K) Index Size (in) = 0.08 Number of Indexes Specified = 70 Number of Indexes Completed = 70 Time Date Scan Started 09:56:54.957 05/18/05 Scan Completed 11:14:21.408 05/18/05 Robot Operator Signature 6> o k DAT ERS 6 2 2

• PARAGON Operator Signature DATE _z__o_-_

Comments -'S -c-, 3

[F£IwcE T a a " AT IDa

( C Page I of I ANALYSIS LOG # WN338-1 Utility: I DUKE POWER Plant: I CATAWBA Unit: 1 Outage: I1EOC15 Procedure No: I PDI-ISI-254-SE I Procedure Rev. No.: l 2 Weld No: 1RPV-Wl8-SE AND 1NC23-01 Weld Type: OUTLET NOZZLE Exam. Surface: ID 10DM WELD @ 338° Applicable Sensitivity Calibration Data Sheet No: l SE-01 l AcquIsitIon Log No: I WN338-1 PARAGON Anal. Release: 6.1.3 UT Examiner Signature: lLevel: lI Date: 5/1P805 Data File Name UT Beam AngleI NI RI RI Examiner ID I Date Channel Beam Direction Resolution / Comments / Limitations No. Inor ou%CworCMCeoltoWICmetsILmiain WN338-SE-PRP-DET-ON 1 70°L / IN X SAS / 5/18/05 WN338-SE-PRP-DET-ON 2 70 0L / OUT X SAS I 5/18/05 WN338-SE-PAR-DET-ON I 70°L I CCW X SAS I 5118/05 WN338-SE-PAR-DET-ON 2 70 0L I CW X 5 INDICATIONS, SIZING SCANS REQUIRED SAS / 5/18/05 Form 12.5 PDI-ISI-254-SE, Rev. 1

WIWcDynE MT I R. AT I * ^

C.

Page 1 of 1 INDICATION DATA SHEET # WN338-1 Utility: I DUKE POWER Plant: I CATAWBA I Unit: I I I Outage: I EOC15 Procedure No: I PDI-ISI-254-SE Procedure Rev. No.: l 2 l PARAGON Anal. Release: 6.1.3 Applicable Analysis Log WN338-1 Applicable Acquisition Log WN338-1 Applicable Sensitivity Calibration SE-01 Sheet No: Sheet No: Data Sheet No:

Weld No: 1RPV-WI8-SE & Axial Scan Increment (deg): 0.970 Axial Scan Increment (in.): 0.25" Circ. Scan Increment (In.): 0.8" I NC23-01 UT Examiner Signature: Level: ill Date: 5/18/05 Center of Indication o - ~~ ~ co .0 -

File Name .* eaE £ J) o i. i d ea WN338-SE-PAR-DET-ON 1 2 70 CW P 21 27 6 121.1 121.58 121.4 74.28 0.19 0.48 0.19 0 WN338-SE-PAR-DET-ON 2 2 70 CW P 16 26 11 120.7 121.5 121.18 78.93 0.25 0.88 0.25 0 WN338-SE-PAR-DET-ON 3 2 70 CW P 18 28 9 120.86 121.5 121.26 83.68 0.21 0.72 0.21 0 WN338-SE-PAR-DET-ON 4 2 70 CW P 21 27 7 121.1 121.58 121.26 85.76 0.22 0.56 0.22 0 WN338-SE-PAR.DET-ON 5 2 70 CW P 20 25 6 121.02 121.42 121.26 87.64 0.21 0.48 0.21 0 Form 12.7 PDI-ISI-254-SE, Rev. 1

C C c

w=spym i" N T a.v . . I

( C Form 12.5: ET Analysis Log Utility: DUKE POWER Plant: CATAWBA Unit: i Outage: 1EOCI5 Procedure No: WDI-STD.148 Procedure Rev. No.: 4 WeldNo. 1RPVW18SEand1NC23-01 WeldType: OUTLET NOZZLE DM WELD @ 338 Applicable Sensitivity Calibration Data Sheet No: ET-01 Acquisition Log No: WN338-1 ET Examiner Signature: Level II Date:5118105 Data ET ET Probe Scan Ni RI RI Examiner ID / Date File Name Probe Direction Resolution I Comments I Limitations No. Cj avCrclm WN338-SE.PRP-DET.ON 3 AX BAD DATA WEH 15/18105 WN338-SE-PRP-DET-ON 4 AX BAD DATA WEH I 5118105 WN338-SE.PAR-DET.ON 3 CIRC X WEH 15118106 WN338.SE-PAR-DET.ON 4 CIRC X SEE ET INDICATION ASSESSMENT SHEET WEH I 5118/05 WN338-1

1!1Wc~DyflE inwks^tvnr= C Page 1 of 1 ET INDICATION ASSESSMENT SHEET # WN338-1 Utility: DUKE POWER Plant: CATAWBA Unit: I Outage: 2EOC15 Procedure No: I WDI-STD-146 Procedure Rev. No.: 4 Weld No: IRPV-W18-SE AND Scan Increment (inch): 0.08: Scan Increment (deg): 0.08'. Total Number of Sweeps: 70 I NC23-01 ET Examiner Signature: Level IlIl ate: 5/18/05 indication Parameters Center of Indication o 0. 250 kHz Frequency 0t File Name Disk .E =. E3 (inch) (deg)

No 0t WN338-SE-PAR-DET-ON N/A 1 4 CIRC 28 30 3 30 593 63.0 244' 121.74" 72.3* 0.24" WN338-SE-PAR-DET-ON N/A 2 4 CIRC 21 31 11 27 670 133.0 254' 121.58' 78.40 0.88' WN338-SE-PAR-DET-ON N/A 3 4 CIRC 24 30 7 25 716 99 263' 121.58" 82.0° 0.56" WN338-SE-PAR-DET-ON N/A 4 4 CIRC 25 30 6 29 743 86.4 267' 121.66" 84.2' 0.48" WN338-SE-PAR-DET-ON N/A 5 4 CIRC 23 28 6 25 782 125.0 261' 121.50" 873 , 0.48" WN338-SE.PAR-DET-ON N/A 6 4 CIRC 29 34 6 33 903 90.5 258' 121.98" 96.9' 0.48" Form 12.6

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M WE!DynE I .T I 0 AT I &^

C (7 Page 1 of I DATA ACQUISITION LOG # WN338-2 Utility: I DUKE POWER Plant: I CATAWBA Unit: Outage: I lEOC15 Procedure No: I PDI-ISI-254-SE l Procedure Rev. No.: 2 Applicable Sensitivity Calibration Data Sheot No: SE-CIRC-01 -

UT Examiner Signature: I Pole . AaVlsa _ _ ILevel: I11 Date: 5/20/05 Data File Name Weld No. Index Scan Total # 'AVE' Gain Date Time Comments Start Start of Signal Adj. o .

Sweeps Amplitude (dB) _ (mmlddlyy) 0~

WN338-SE-SIZ-PAR.ON 1RPV-W18-SE 117- 0. 130 11 0 DN 5/20/05 01:00

&INC23-01 . .

WN338.SE-SIZ-PAR-ONA 1RPV.W18-SE 117' 06 100 11 +10 DN 5/20/05 03:10

&1NC23-01 _

Form 12.4 PDI-ISI-254-SE, Rev. 1

WesDyne International Reactor Vessel Inservice Examination Scan Parameter Execution CUSTOMER ................4..:DUKE POWER SITE . CATAWBA UNIT-1 OUTAGE .. EOC15 VESSEL TYPE . Westinghouse 4-Loop WELD IDENTIFICATION - 1RPV-W18-SE Weld and Scan Type = NOZZLE SAFE END PARALLEL SCAN Scan Data File Name = WN338-SE-SIZ-PAR-ON SCAN AREA PER THE ORIGINAL TECHNIQUES UDRPS SCAN AREA DEFINITION DEPTH AZIMUTH (IN) (DEGREES)

START CW 117.00 179.90 END CCW 117.00 -179.90 START CW 127.25 179.90 END CCW 127.25 -179.90 Index Size (in) = 0.08 Number of Indexes Specified = 130 Number of Indexes Completed = 130 Time Date Scan Started 22:22:34.350 05/19/05 Scan Completed 00:47:20.550 05/20/05 Robot Operator Signature -DATE 5 -/ - ° -

PARAGON Operator Signature .DATE '5 Comments

WesDyne International Reactor Vessel Inservice Examination Scan Parameter Execution CUSTOMER .......... ..... -DUKE POWER SITE . CATAWBA UNIT-i OUTAGE . lEOC15 VESSEL TYPE . Westinghouse 4-Loop WELD IDENTIFICATION - IRPV-W18-SE Weld and Scan Type = NOZZLE SAFE END PARALLEL SCAN Scan Data File Name = WN338-SE-SIZ-PAR-ON SCAN AREA PER THE ORIGINAL TECHNIQUES UDRPS SCAN AREA DEFINITION DEPTH AZIMUTH (IN) (DEGREES)

START CW 117.00 179.90 END CCW 117.00 -179.90 START CW 127.25 179.90 END CCW 127.25 -179.90 Index Size (in) = 0.08 Number of Indexes Specified = 130 Number of Indexes Completed = 101 Time Date Scan Started 01:18:11.858 05/20/05 Scan Completed 03:11:23.882 05/20/05 Robot Operator Signature DATE5-Z 0@ I PARAGON Operator Signature Comments \\cZ-Comments - -- cA

rnwEsDvflE

( ~ C C Page I of I ANALYSIS LOG # WN338-2 Utillty: DUKE POWER Plant: CATAWBA Unit: 1 Outage: lEOC15 Procedure No: I PDI-ISI-254-SE I Procedure Rev. No.: l 2 Weld No: I RPV-W18-SE AND 1NC23-01 Weld Type: OUTLET NOZZLE Exam. Surface: ID DM WELD @ 3380 Applicable Sensitivity Calibration Data Sheet No: SE-CIRC-01 Acquisition Log No: WN338-2 PARAGON Anal. Release: 6.1.3 UT Examiner Signature: l /. ,Jd( 6 o Level: lIl IIl Date: 5/20/05 Data File Name UT Beam Angle / NI RI RI Examiner ID I Date Channel Beam Direction Resolution I Comments I Limitations NO. 4° CW /o DCCW WN338-SE-SIZ-PAR-ONA 2 45°L / CCW X DN I 5/20/05 WN338-SE-SIZ-PAR-ONA 3 60°L / CW X DN / 5/20/05 WN338-SE-SIZ-PAR-ONA 4 600L / CCW X DN / 5/20/05 WN338-SE-SIZ-PAR-ONA 370 L / CW X = DN / 5/20/05 WN338-SE-SIZ-PAR-ONA 6 37°L / CCW X DN / 5/20/05 Form 12.5 PDI-ISI-254-SE, Rev. 1

wEsDyniE

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( C Page 1 of 1 INDICATION DATA SHEET # WN338-2 Utility: I DUKE POWER Plant: I CATAWBA I Unit: I 1 1Outage: I EOC15 Procedure No: I PDI-ISI-254-SE Procedure Rev. No.: I 2 l PARAGON Anal. Release: 6.1.3 Applicable Analysis Log WN338-2 Applicable Acquisition Log WN338-2 Applicable Sensitivity Calibration SE-CIRC-01 Sheet No: Sheet No: Data Sheet No:

Weld No: IRPV-WI8-SE & Axial Scan Increment (deg): N/A Axial Scan Increment (in.): N/A Circ. Scan Increment 0.080" INC23-01 (in.):

UT Examiner Signature: _ _ 4. Level: IlIl Date: 5(2005 Center of Indication

_ 0 CIE

. a[ I0 I _ 0 I 0 ) -

FileName _ = = == == == m I WN338-SE-SIZ-PAR-ON 2 2 45 COW P 82 89 8 120.98 121.54 121,27 79.6 0.25 0.64 0.25 0

.. . ===

WN338-SE.SiZPAR-ON 3 2 45 CCW P 89 90 2 121.46 121.54 121.54 82.45 0.21 0.16 0.21 0 WN338-SE-SiZPAR-ON 5 2 45 CCW P 80 81 2 120.82 120.9 120.85 87.3 0.21 0.16 0.21 0

. __ __ == 5 I Form 12.7 PDI-ISI-254-SE, Rev. 1

1E"TWESDyflE W~lwyT flE f

C Page 1 of 1 INDICATION ASSESSMENT SHEET # WN338-1 Utility: I DUKE POWER Plant: lCATAWBA Unit: 1 Outage: lEOC15 Procedure PDI-ISI-254-SE Procedure Rev. No.: 2 No: I UT Examiner _ Level: lli Date: 5/20/05 Signature:

0 0 0 to: :5 6d File Name . E ES 3 o.= l E . 3 WN338-SE-PAR-DET-ON 1RPVMW18 SE WN338-1 #1 70 CW P 2.58 0 048 SURF 0 0 0.25' 0.50 9.7 11.1 Y AND 1NC23-01 0.25' 0.13 WN338-SE-SIZ-PAR-ONA IRPV-W18-SE WN338-2 #2 45 CCW P 2.58 0 (1) 0.88 SURF 0 0 0.31' 0.35 12.0 10.8 N AND 1NC23-01 II 0.31' 0.16 WN338-SE-SIZ.PAR-ONA IRPV-W18.SE WN338-2 #3 45 CCW P 2.58 0 (1) 0.58 SURF 0 0 0.28' 0.50 10.9 11.1 Y AND 1NC23-01 0.28' 0.14 WN338-SE-PAR-DET-ON IRPV-W18-SE WN338.1 #4 70 CW P 2.58 0 0.58 SURF 0 0 0.28- 0.50 10.9 11.1 Y AND 1NC23-01 0.28' 0.14 WN338-SE SIZ.PAR-ONA 1RPV.W18-SE WN338-2 #5 45 CCW P 2.58 0 (1)0.48 SURF 0 0 0.28' 0.50 10.9 11.1 Y AND 1NC23-01 0.28' 0.14 Notes: Y=CODE ALLOWABLE PER ASME 1989; IWB-3514-2.

N=NON-ALLOWABLE PER ASME 1989; IWB-3514-2.

• =INCLUDES +0.064w ADDED AS COMPENSATION FOR PDI QUALIFICATION RMS ERROR.

(1) LENGTH FROM EDDY CURRENT.

Re/t ew A b v-Form 12.3 PDI.ISI-254-SE, Rev. 1

(

W.1 Westinghouse 1 _

C etary Class 2C C I

-Toward Vessel Theta Location 74.28'

.53

-1.57 Inconet Band (ET estimate) L .t. t I-1.17 1.20 -

X

.47 48 120.94 121.56 l -- d Iiii 1 (i (ET Only)

.48( 88 j() .56l-j 34 48

.95 Inconet Band (design) 122.51 I .

Weld i 123.17

-- **- 00 360° NW CATAWBA 1 DCP WesDyne Interna tional SI=T 0,2525 inches per degree MTMl 338' OUTLET SAFE END INDICATIONS Weld # IRPV-W18-SE & INC23-01 ALL DIMENSIONS IN INCHES I UNLESS OTHERWISE NOTED

. I-Westinghouse *etaryClass 2C (I I

-Toward Vessel Theta Location 74.2G8 57 Inconet Band (ET estimate) 120.94 121.56 Weld i 123.17

~ 0° CATAWBA 1 DCP WesDyne lntL-rno tional HEE 338 OUTLET SAFE END INDICATIONS 0.2525 inches per degree Weld # IRPV-W18-SE . INC23-01 ALL DIMENSIONS IN INCHES I UNLESS OTHERWISE NOTED

VesDyne 2005 Y-Mg tesDyne 2005

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K-)l VesDyne 2005

VesDyne 2005 V:

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VesDyne 2005

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UT / ET CORRELATION k

.1r Catawba Unit #1,MNS #2 Hot Leg Nozzle/Safe End Details Catawba Unit #2, MNS #1 Hot Leg Nozzle/Safe End Details INCONEL VELD

< ~ElicrFe.) t(18l)

Ml* 33(82

,TiErre RES HOShLEG C X 133'te

- NOtZL Et KIN wn biS ufE Ad ased XSi 3oLo1-Oo d5tac8 CStM- h

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UT / ET CORRELATION Indication # Method 0 Position Start Y End Y Length Comments (center) position position

. UT 74.280 121.10" 121.58" 0.48" ET 72.300 121.66" 121.82" 0.24" _

2 UT 78.930 120.70" 121.50" 0.88" ET 78.40° 121.10" 121.90" 0.88" 3 UT 83.680 120.86" 121.50" 0.72" ET 82.000 121.34" 121.82" 0.56" 4 UT 85.760 121.10" 121.58" 0.56" ET 84.200 121.42" 121.82" 0.48" 5 UT 87.640 121.02" 121.42" 0.48" ET 87.300 121.26" 121.66" 0.48" 6 UT NOT SEEN ET 96.900 121.74" 122.14" 0.48"

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'3 CATAWBA 1 WesDy eInternationat I Oe SAFE END DETECTION SLED EXAMINATION PROGRAM PLAN

5.0 Owner's Report for Repair / Replacement Activities As required by the applicable code, records of Class 1 and Class 2 Repair and Replacement work is included on NIS-2 forms in this section.

The NIS-2 forms included in this section were completed for work performed during this report period.

The individual work request documents and manufacturers' data reports are on file at Catawba Nuclear Station.

PIP #C-04-02215 was written on May 6, 2004 to document that a NIS-2 Form for the NV System Valve 1NV338 Disc that was replaced during the EOC14 Refueling Outage. The NIS-2 Form had not been submitted in time to support the 90 day time frame submittal requirement of the Catawba 1 EOC14 ISI Summary Report. A revised EOC14 Section Xl Repair/Replacement Activities Log and the NV System Valve 1NV338 Replacement Disc NIS-2 Form is included in this section of this report. Reference Section 1.3 for additional information. A copy of PIP #C-04-02215 is included in this section of the report.

Refueling Outage EOC 15 (Outage 7) Page 1 of 1 Catawba Unit 1 Revision 0 Section 5 August 15, 2005

C c (

Flaw Indication Code Repair, Maint/ ISI Owner Work Order Class Sys MOD No. Description Replacement (*Yes No) Final ANII Final 98440711-21 A NC NA Replace Spare Valve Replacement No 12/6/2004 1/13/2005 98636132-05 A NC NA Disc for Valve 1NC-29 Replacement No 6/13/2005 6/20/2005 98649526-01 A NV NA Load Pin for S/R 1-R-NV-1 188 Replacement No 7/7/2005 7/12/2005 98683543-04 A NC NA Bolting for S/R 1-R-NC-2320 Replacement No 7/7/2005 7/12/2005 98683598-05 A NC NA Valve 1NC-003 Replacement No 6/13/2005 6/20/2005 98728678-01 A NI NA Seal Weld Valve 1NI19 Replacement No 6/13/2005 6/20/2005 98440714-05 B NI CE61612 NI Piping Replacement No 12/9/2004 1/13/2005 98453424-04 B ND NA Offsite Repair of ND Stuffing Box Repair No 5/3/2004 5/6/2004 98588027-01 B NV NA Disc for Valve 1NV338 Replacement No 5/6/2004 5/6/2004 98640136-01 B CA NA 1CA190 valve cover Replacement No 8/15/2005 8/17/2005 98644720-37 B NS 11432/01 Containment Spray HX "1A" Replacement No 7/28/2005 8/1/2005 98644720-43 B NS 11432/01 NS HX "1A" Piping Replacement No 7/27/2005 8/2/2005 98647944-01 B NV NA Valve 1NV-235 Replacement No 3/29/2004 5/6/2004 98647944-06 B NV NA Disc for Valve 1NV-235 Replacement No 7/6/2004 7/22/2004 98668640-01 B NV NA Valve 1NV-294 Plug Assembly Replacement No 6/13/2005 6/20/2005 98668644-01 B NV NA Valve 1NV-232 Replacement No 717/2005 7/12/2005 98668650-01 B SM NA Valve 1SM-19 Replacement No 7/26/2005 7/26/2005 98668763-01 B NV NA Replace Valve 1NV-235 Replacement No 7/6/2004 7/22/2004 98668763-05 B NV NA Valve Disc for 1NV-235 Replacement No 2/14/2005 2/14/2005 98669062-01 B NV CE-1 001 84 Valve 1 NV-233 Disc Replacement No 6/3/2005 6/28/2005 98670596-01 B NV NA Valve 1NV-849 Plug Assembly Replacement No 6/13/2005 6/20/2005 98684801-01 B NV NA Valve 1NV-290 Disc Replacement No 6/3/2005 6/27/2005 98688771-10 B NS CD100115 NS Test Loop A Train Piping Replacement No 8/2/2005 8/9/2005 98688781-11 B NS CD100115 NS Test Loop B Train Piping Replacement No 8/3/2005 8/9/2005 98690544-08 B SV NA Valve 1SV-19 Plug Assembly Replacement No 3/8/2005 3/8/2005 98698971-01 B SM NA Bolting for Valve 1 SM-3 Replacement No 6/13/2005 6/21/2005 98698972-01 B SM NA Bolting for Valve 1SM-5 Replacement No 6/14/2005 6/21/2005 98712333-14 B CA CD100262 Valve 1CA-57 Replacement No 7/29/2005 8/1/2005 98712362-14 B CA NA Valve 1CA-61 Replacement No 7/25/2005 7/25/2005 98714044-01 B ND NA RHR HX 1A Bolting Replacement No 2/23/2005 3/1/2005 98714044-04 B ND NA RHR HX 1A Bolting Replacement No 3/31/2005 4/4/2005

c C Section E Exhibit A ASME Section XI Manual FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 12/06/04 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. PIanz CATAWBA NUCLEAR STATION 2a Unit 3I 2 ai 3 aII Shared (specify Units: )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 984407 '11-21 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System NC REACTOR COOLANT SYSTEM Class A

5. (a) Applicable Construction Code imi 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE 6 Id entifr-ntinn of Cnmnnnents Renaired or Renincement Comnonentq Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 _ _ _ _ _ _ _ _6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Replacement Stamped Number ____________________________________________(yes or no)

A Valve Disc Dresser AAC-19 NA For Spare Valve with S/N BS-02872 NA Replaced No B Valve Disc Dresser AAC-78 NA For Spare Valve with S/N BS-02872 NA Replacement No D

E=_=

F _==

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A V NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Offsite Spare Valve Repair_

8. Test Conducted: Hydrostatic Pressure psig n1 Pneumatic Cl Nominal Operating Pressure Test Temp. deg.F.

n Other FI Exempt 3

9. Remarks _ Code Cases __NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of uthorization No. N/A Sine utorz

-*c-*- S * - z {_ a- l TECH SPEC Date /7/? 20.0 <

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by HSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period 9 0\ to I -13 'O5 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_ _ _ _ _ Cm Commissions NC 978 Inspector's Signature Date * - ,20_Z. 5 _

Revision 6

C C Section E Exhibit A ASME Section XI Manual FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 12/09/04 Sheet 1 of 1 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 1 E2 Dj 3 L] Shared (specify UnitsRl )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order# 984407 14-05 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp NLA Authorization No. N/A 3b NSM or MN # CE616 12 Expiration Date N/A 4 Identification of System NI SAFETY INJECTION SYSTEM Class B

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Addenda NONE

6. Identification of Comnonentq Renaired or Renlncement Comnonents Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 __6 8 Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Name of Component Manufacturer Serial Number Built Replaced. or Code Number Replacement Stamped yes or no)

Number(

A Pipe/Fittings Duke Power C-INI 128 1 1/4" Pipe- SA106, Pipe Cap- SA105, NA Replacement No Co. Cplg.- SA105, 90 ell- SA105 B Tee- SA105 C Pipe Welds Duke Power C-1NI 128 Welds #1201.05-0075-1B3 1B4 1B5 2004 Replacement No Co. 1B6 1B7 1B8 1B9 DtI1 I - t

_E .

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Install Lube Oil Piping_.

8. Test Conducted: Hydrostatic Dl Pneumatic R Nominal Operating Pressure Other F1 Exempt 3 Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases _N-416-2 USING SECT. 111 1992 NDE Pressure Test not required due to line is under atmosperic pressure.

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp NIA Expiration Date N/A Certificate of A horiztion No. N/A Signed /i TECH SPEC Date J20L,20 4

/

> Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by HSB I AND I Comnanv of Connecticut have inspected the components described in this Owners Report during the period 6 l04 to I - °5 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_ __ _ _ _Commissions NC 978 Inspecto Signature Date L- l ._ ,20p 5 Revision 6

C ASME Section XI Manual C Section E Exhibit A C

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS

_ As Required By The Provisions Of The ASME Code Section XI 1.Owner DUKE POWER COMPANY la Date 5/04/04 Sheet / of /

Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 1 E2 D 3 D Shared (specify UnitsD )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order# 984534 424-04 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp NIA Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B ND RESIDUAL HEAT REMOVAL SYSTEM

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. dentification of Comnonents Reniired or Repnlrcement Comronentq Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column

_ 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Replacement Stamped or no)

N umber __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _(yes A Stuffing Box Ingersoll- 78890 NA Weld Alignment Pads to Stuffing Box NA Repaired No Extension Rand F

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A t A' NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Offsite Repair to Spare RNR Pump_

8. Test Conducted: Hydrostatic L Pneumatic M Nominal Operating Pressure I Other Li Exempt 3 Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases ___NONE_Pump was repaired offsite by Flowserve.

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed ZZA TECH SPEC Date &5 ,20 OS/

/ Owner or Owner's Designee. Titl CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORT11 CAROLINA and employed by HSB I AND I Companv of Connecticut have inspected the components described in this Owners Report during the period ID- B- 03 to 5 -&-09 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspectio

_ __o Commissions NC 978 Inspec or's Signature Date 5-Q'.,20-4 _

Revision 6

C ( (7 ASME Section Xl hlanual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section Xi I. o.-rcr DUKE POWER COMPANY la Date 5!10/04 Shect I of I Addess 526 S. CHURCH STREET. CHARLOYT2 N.C. 28201-1006

2. nit1 CATAWBA NUCLEAR STATION 2aUnit I n 2 E 2 0 Shared (specify Units12 )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98588( )27-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construcuion Code III 1974 Edition, S'75 Addenda, Code Cases (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Comnonents Repaired or Renlacement Comnonmnntq Column 2 Column 3 Column Column 5 Column Column 7 Column Column I 8 4 6 Manufacturer N B Othcr Identification (Size) Year Repaired. ASME Name of Name of Serial Number Built Replaced. or Co&e Component Nianufacturcr Number Replacement Stamped NA NA For Valve lNV338 with SN# E1581 NA Replaced No A Valve Disc Anchor Darling I and NB# 694 Anchor See altnached NA Valve 1NV338 NA Replacement No B Valve Disc Darling Data Report D_

E _ _

F Revision 6

/le*

ASME Scction Xl Manual Form NIS-2 ( 13nck) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches. or drawings may be used. provided (I) size is 8 Ifhn. x I I in. (2) information in items I through 6 on this reports included on each sheet. and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Replace Disc for INV338-

8. Test Conducted: Hydrostatic Cl Pneumatic a Nominal Operating Pressure Other [] Exempt 0 Pressure psig Test Temp. deg.F.

9. Remarks - Code Cascs _NONE.

• Rcference PIP C-04-2215 (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code. Section Xi.

Type Code Symbol Stamp N/A Expiration Date NMA Certificate of pthorization No. N/A Signed 4 Oa , O,g TECH SPEC Date .20 Owner or Owner's Dr-signec:. Titt:

CERTIFICATE OF INSERVICE INSPECTION

1. the undersigned. holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROL.INA and employed by IISB I AND I Company of Connecticut have inspected the components described in this Owners Rcpori during the period Itl - ° 03 to S -- O1 and state that to the bcst of my knowledge and belief. the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code. Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied. concerning the examinations and corrective measure described in this Owners Report. Furthermore. ncithc the Inspector nor his employer shall be liable in any manner for any personal injury or prnpeny damage or a loss of any kind arising from or connected with this inspection.

( ___ CCommissions NC 978 Ins tor's Signature Date 5 .I20_0 4 -

Revision C)

ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

l. Owner DUKE POWER COMPANY la Date 6/13/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit E 1 112 aI 3 LI Shared (specify UnitsD )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98636132-05 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System NC REACTOR COOLANT SYSTEM Class A

5. (a) Applicable Construction Code HI 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column

__4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number N um ber______ __ _ _ _ _ __________

Replacement Stamped (yes or no)

A Vee Ball Fisher NA NA Valve tag lNC-29 NA Replaced No Assembly _ _

B Vee Ball Fisher AD941 1-1 NA Valve Tag INC-29 NA Replacement No Assembly D

EtIIiII1 Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A yJNOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items 1 through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work I/R Valve INC-29_

8. Test Conducted: Hydrostatic a Pneumatic El Nominal Operating PressureR Other FZ Exempt Z Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases __NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp NLA Expiration Date N/A Certificate of Authorization No. N/A Signed TECH SPEC Date 7/3 ,20A Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by HSB I AND I Companiv of Connecticut have inspected the components described in this Owners Report during the period 5 -215-05 to C& n i'Sand state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_______ ______ Commissions NC 978 Inspector s Signature Date _. Zt_ ,20_0 5 Revision 6

C C Section E Exhibit A C

ASME Section Xl Manual FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 8/16/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOITE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 31 12 E3 2 Shared (specify UnitsM )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order# 986401 36-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System CA AUXILIARY FEEDWATER SYSTEM Class B

5. (a) Applicable Construction Code HI 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or code Replacement Stamrped Number (yes or no)

A Valve Cover Flowserve TX5-3 NA For valve ICA 190 NA Replaced No B Valve Cover Flowserve HAP-4-9 NA For valve ICA 190 NA Replacement No D

_E FtgIs4I1 Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2in. x 11 in. (2)

K.. information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work I/R Leak around ICA 190 valve cover._

8. Test Conducted: Hydrostatic l Pneumatic Nominal Operating Pressure 3 OtherE]Exempt a Pressure 1156 psig Test Temp. 442 deg.F.

9. Remarks _ Code Cases _N-416-2 USING SECT. 1I 1992 NDE_ Pressure Test was performed on work order 98742786-01. Ref PIP C-05-4782.

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code, Section Xl.

Type Code Symbol Stamp N!A Expiration Date N/A Certificate of Authorization No. N/A Signed 6 S2-w Owner or Owner's Designee. Title TECH SPEC Date 8/7G ,20-US CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by IISB I AND I Companv of Connecticut have inspected the components described in this Owners Report during the periods-)"/&l'5 to 4F) -1k2-0 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Qitu _________Commissions NC 978 Inspector's Signature Date .. VL ,20_0 S5 Revision 6

C ASME Section XI Manual C C Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 7/28/05 Sheet I of Z Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2aUnit E 1 E2 E] 3 E Shared (specify UnitsL )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98644720-37 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp NLA Authorization No. N/A 3b NSM or MN # 11432/01 Expiration Date N/A 4 Identification of System NS CONTAINMENT SPRAY SYSTEM Class B

5. (a) Applicable Construction Code 11 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification

a. of Components

_ __. Repaired

_. or Replacemcnt r~- Components

..... Z.......L r.

Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number N um ber Replacement Stamped (yes or no)

A Heat Exchanger YUBA 74-N-008-2A 3324 Containment Spray Heat Exchanger 1978 Replaced Yes

_~ "A" B Heat Exchanger Joseph Oat 2636C 3456 Containment Spray Heat Exchanger 2005 Replacement Yes

__ __ _ _ _ _ C orp. __ __ __ __" A 1 C__

D F

Revision 6

C ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 7/28/05 Sheet 2 of Z-Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2aUnit E 1 j2 C 3 0 Shared (specify UnitsD )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order# 98644720-37 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # 11432/01 Expiration Date N/A 4 Identification of System NS CONTAINMENT SPRAY SYSTEM Class NF

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number N u m ber__ __ _ _ _ _ _ __ _ _ _ _ _ __ _ _ _ _ _ __ _ _ _ _ _ __ _ _ _ _ _(yes Replacement Stamped or no)

A Sway Strut Anvil 2004-1015 NA 1-E-NS-0103 2004 New Yes International B Sway Strut Anvil 2004-1016 NA 1-E-NS-0103 2004 New Yes International C Sway Strut Anvil 2004-1017 NA 1-E-NS-0103 2004 New Yes Internationa D Sway Strut Anvil 2004-1018 NA I-E-NS-0 103 2004 New Yes International E Brackets Anvil NA NA I-E-NS-0103 NA New No International F Welds Duke Power C-INS 118 Weld #I-E-NS-103-1 thru 8 2005 New No Co.

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A k;NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Replace Containment Spray HX I A_

8. Test Conducted: Hydrostatic M Pneumatic M Nominal Operating Pressure Other M Exempt 2 Pressure 252 psig Test Temp. 60 deg.F.

9. Remarks _ Code Cases __N-416-2 USING SECT. III 1992 NDE (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed TECH SPEC Date 78 20 CC

/ Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by IISB I AND I Companv of Connecticut have inspected the components described in this Owners Report during the period3 - '7-05 to - II3-O' and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

2 9 4 Inspector's Signature d Commissions NC 978 Date L3j(-,20 3 -

Revision 6

C C C.

Section E Exhibit A ASME Section XI Manual FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 7/26/05 Sheet I of 4 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2aUnit 31 Z2 Li 3 M Shared (specify UnitsE )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98644720-43 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # 11432/01 Expiration Date N/A 4 Identification of System NS CONTAINMENT SPRAY SYSTEM Class B

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number Replacement Stamped Valve Kerotest FAL4-25 35944 Valve tag INS-89 1983 Replaced Yes B Valve BNL A981103 NA Valve tag LNS-89 2004 Replacement Yes Industries 77 C Valve Kerotest HAD9-6 29173 Valve tag INS-90 1980 Replaced Yes D Valve BNL A981103 NA Valve tag INS-90 2004 Replacement Yes Industries 78 E

F Revision 6

c ASME Section Xi Manual c Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section Xl I. Owner DUKE POWER COMPANY la Date 7/26/05 Sheet 2 of #

Address 526 S. CHURCH STREET. CHARLOTTE N.C. 2820 1-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit E I E2 aI 3 LI Shared (specify UnitsF] )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98644720-43 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # 11432/01 Expiration Date N/A 4 Identification of System NS CONTAINMENT SPRAY SYSTEM Class B

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Renlacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Replacement Stamped um ber _______(Ves or no)

_____________N A Bolting Duke Power C-INS 118 Hex Nuts- SA194, Threaded Rod-SA193 NA Replacement No Co.

B Pipe/Fittings Duke Power C-INS 118 2" Pipe Cap-SA182, 2" 90 ell- SA182, NA New No Co. 2" Flange-SA 182, 2x1 Red. Ins.-SA182 CU __ 2"Tee-SA 182, 2"Couplg.-SB462, 2x1I Red Ins.-SB462, 2" Pipe Cap-SA105 _

D 10" 90/45 ell-SA403, 10" Pipe-SA403/

SA312, 2" Pipe-SA376/SB675 E 10x8 Red-SA403, 2" 90 ell-SB462, 18"

__ __ _ Pipe-SB366, 18" 90/45 ell-SB366 _

F 10" Tee-SA403 18"Flg.- SB462/SA105 _ .

Revision 6

C (

ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI 1.owner DUKE POWER COMPANY la Date 7/26/05 Sheet 3 of ,T4 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit EI 1112 01 3 F Shared (specify UnitsD1 )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98644720-43 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # 11432/01 Expiration Date N/A 4 Identification of System NS CONTAINMENT SPRAY SYSTEM Class B

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Addenda NONE

6. Identification of Comronentr Rennired or Renlacement Comnonentq Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number Replacement stamped A Pipe Welds Duke Power C-INS 118 INS40-7, INS22-27 thru 33, INS36-25 Replacement No Co. thru 40, INS20-18, 23 thru 30 B New No C

D F

Revision 6

CC C ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Ot The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 7/26/05 Sheet 4 of 4L Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit I 11j2 ZJ3 El Shared (specify UnitsE )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986447 720-43 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # 11432/ 01 Expiration Date N/A 4 Identification of System NS CONTAINMENT SPRAY SYSTEM Class NF

5. (a) Applicable Construction Code 11 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Nameof Nameof Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Replacement stamped

_ _ _ _ N um ber __ _ _ _ _ _ _ _ _ _ _ _ ys or no)

A Mech Shock Anvil 1997-96 NA 1-R-NS-030 NA Replacement No Extension International B Plate NA NA NA For S/R I -R-NS-030 NA New No C Welds Duke Power C-INS 118 Welds #I-R-NS-0030-2 & 4 For S/R 1- 2005 New No Co. R-NS-030 D

F .

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x II in. (2)

K.i information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Replace NS HX IA and Associated Piping_

8. Test Conducted: Hydrostatic Pressure 252 psig ni Pneumatic D Nominal Operating Pressure E Test Temp. 60 deg.F.

Other i] Exempt LI

9. Remarks _ Code Cases __N-416-2 USING SECT. III 1992 NDE (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Sqiane-d C"9 . 911W_ A rx o AWAY_ TECH SPEC Date S/Z7 ,200

/ Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLTNA and employed by HISB I AND I Companv of Connecticut have inspected the components described in this Owners Report during the period 3-ckHL- to b-tO5 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

D._____________ _ Commissions NC 978 I'~spector's Signature Date 7Q-_20_0.5 __

K' Revision 6

C C CE ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY 1a Date 3/29/04 Sheet / of /

Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 3 1 12 Zj3 LI Shared (specify UnitsE )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98647944-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code 11 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column

__4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Replacement Scamped Number yes or no)

A Valve Dresser TG-80174 1927 Valve tag LNV-235 1986 Replaced Yes B Valve Dresser TE-03781 576 Valve tag 1NV-235 1978 Replacement Yes C Bolting Duke Power NA NA Studs-SA193, Hex Nuts-SA194 NA Replacement No ECo.

E Revision 6

ASME Section XI Manual Form NIS-2 (Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Replace Valve INV-235_

8. Test Conducted: Hydrostatic E] Pneumatic 2 Nominal Operating Pressure E Other III Exempt 1 Pressure 27.3 psig Test Temp. 96.6 deg.F.

9. Remarks - Code Cases __NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed / TECH SPEC Date 4/29 ,20_A

/ Owner or Owner's Designee. Title

.1 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by HSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period 2-2rL to S- G-O4` and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspe n.

Commissions NC 978 ns ctor's Signature 4

Date 5 _ ,20 ) -

Revision 6

C. C C.

Section E Exhibit A ASME Section XI Manual FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY Ia Date 7/6/04 Sheet 1 of 1 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plnnt CATAWBA NUCLEAR STATION 2a Unit E 1 E12 E3 M Shared (specify UnitsDl )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986479 44-06 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code imi 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 6 8

_4 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced, or Code

___ ___ Nu berReplacem ent Stamped Number A Ve Dc D(yes or no)

A Valve Disc Dresser NA NA Valve tag 1NV-235 NA Replaced No B Valve Disc Dresser ACY44 NA Valve tag 1NV-235 Na Replacement No C

E__

F.._

Revision 6

ASME Section XI Manual Form NIS -2 ( Back) Section E Exibit A

.<_) NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Refurbished Valve INV-235_

8. Test Conducted: Hydrostatic D Pneumatic 2 Nominal Operating Pressure D OtherF]Exempt Z Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases __NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed d/ ." TECH SPEC Date 7X6 20JO Owner or Owner's Designee. Title jfl CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed b HSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period b to -) 22-o0 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_ _ _ _ _ _Commissions NC 978 L Date -7 ' a ,200A Revision 6

(C ASME Section XI Manual Section E Exhibit A C

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 7/7/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 53I 2 F3 O Shared (specify UnitsE )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986495 26-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN It NA Expiration Date N/A 4 Identification of System Class A NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code II 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Manufacturer Serial Number Built Replaced. or Code Component Replacement Stamped Number __ _ _ _ _ _ (yes or no)

A Load Pin Anvil NA NA For S/R 1-R-NV-1188 NA Replacement No International B

CF '

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (l) size is 81/2in. x I1 in. (2)

"-' information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Replace Load Pin for S/R l-R-NV-I 188_

8. Test Conducted: Hydrostatic LI Pneumatic LI Nominal Operating PressureE OtherD Exempt 3 Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases _NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Sipned c S s Ad TECH SPEC Date 2 7 .20 "S5

/ Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by IISB I AND I Companv of Connecticut have inspected the components described in this Owners Report during the period X -j I 9> 1?05 and state that to the best of my 5 to - '1Z knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied. concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

P Commissions NC 978 Inspec6r's Signature Date _ I L ,2_ -5 Revision 6

C ASME Section XI Manual c Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 6/13/05 Sheet I of 1 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 1 L12 LI 3 ] Shared (specify UnitsE )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98668640-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code Iml 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 _ 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number Replacement Stamped or no)

Number_____________________________________(yes A Valve Plug Fisher AH 0110-1 NA Valve tag INV-294 NA Replaced No B Valve Plug Fisher PE 0262-1 NA Valve tag INV-294 NA Replacement No C

D ._

F_=

Revision 6

ASME Section XI Manual Form NIS -2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work h/R Valve INV-294_

8. Test Conducted: Hydrostatic F Pneumatic F Nominal Operating Pressure Other Li Exempt E Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed O w g TECH SPEC Date 6 ,20e5

/Owner or Owner's Designee, TitleI

-I CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed b HSB I AND I Companv of Connecticut have inspected the components described in this Owners Report during the period To--CI to 260 05 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

3Z NV Ark Commissions NC 978 Inspector's Signature Date -t->-2 ,20.2P 5 Revision 6

C C Section E Exhibit A ASME Section Xl Manual FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI 1.Owner DUKE POWER COMPANY la Date 7/7/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit I 1F12 D3 1 Shared (specify UnitsD )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986686644-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced.

Replacement or Code Stamped

_ (yes or no)

Number ______ ________

A Valve Dresser TE03775 78 Valve tag INV-232 1978 Replaced Yes B Valve Dresser TE03781 576 Valve tag INV-232 1978 Replacement Yes FSI]1!T3 E

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2)

K.> information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Replace Valve INV-232_

8. Test Conducted: Hydrostatic R Pneumatic F] Nominal Operating Pressure Z Other 1 Exempt f Pressure 26 psig Test Temp. Ambient deg.F.

9. Remarks _ Code Cases ___NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed TECH SPEC Date d7 ,20 01

/ Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by IISB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period 4 -1POS to 7 -120.S and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

W1 C Commissions NC 978 Inspector's Signature Dater -Z_&,20 DS Revision 6

C. C (C ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI 1.Owner DUKE POWER COMPANY la Date 7/26/05 Sheet I of l Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit E1 F2 0 3 D Shared (specify UnitsFl )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986686 650-01 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System SM MAIN STEAM SYSTEM Class B

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Addenda NONE

6. Identification of Componentq Rennired or Renlacement Comnonents Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or CodeL Cmnreril Replacement Stamped Num ber ______ ________ (yes or no)

A Valve Borg Warner 53015 1808 Valve tag ISM-19 1979 Replaced Yes B Valve Borg Warner 26910 737 Valve tag ISM-19 1978 Replacement Yes C Pipe Duke Power C-1SM 122 2" Pipe- SA376 NA Replacement No Co.

D Pipe Welds Duke Power C-1SM 122 ISM55-22 2005 Replacement No Co. .

E Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A

, NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81I2in. x II in. (2)

V information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Replace Valve ISM- 19_

8. Test Conducted: Hydrostatic M Pneumatic M Nominal Operating Pressure 3 Other F] Exempt [

Pressure 973 psig Test Temp. 544 deg.F.

9. Remarks _ Code Cases _N-416-2 USING SECT. III 1992 NDE (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Sigyned 1~2-& ,:A s _~

TECH SPEC Date Z4 20 =

/ Owner or Owner's Dcsignee. Titic CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by IISB I AND I Companv of Connecticut have inspected the componentsdescribedinthisOwnersReport duringtheperiod to'/

o'-\ *-'°) andstatethattothebestofmy knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

__ _ _ _ _ _ _ _ Commissions NC 978 Inspector's Signature Date b ,2 O 5 __

Revision 6

c ASME Section XI Manual C Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY ia Date 7/6/04 Sheet 1 of 1 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Pjant CATAWBA NUCLEAR STATION 2a Unit E 1 E2 D3 fl Shared (specify UnitsD )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986687 '63-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp NLA Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code 11 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Comnonents Renaired or Renlacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number Replacement Stamped A Valve Dresser TE03781 576 Valve tag INV-235 1978 Replaced Yes B Valve Dresser TG80174 1927 Valve tag INV-235 1986 Replacement Yes C

F Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Replace Valve I NV-235_

8. Test Conducted: Hydrostatic M Pneumatic Nominal Operating Pressure 3 OtherO Exempt 0 Pressure 30.9 psig Test Temp. 97 deg.F.

9. Remarks _ Code Cases __NONE (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed

/ Owner or Owner's Designee, Title TECH SPEC Date Ve 20

-I I

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed byHSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period f' to.to G l t and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspect'.

__ v____ Commissions NC 978 In ctor's Signature Date_) - Z ,20_ C 4 _

Revision 6

(

ASME Section XI Manual C Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 2/14/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit E 1 [12 [13 [ Shared (specify Units[] )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986687 63-05 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp H/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code 11 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components

_ _ __ __- A-r--I -~

Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number Replacement Stamped A Disc Dresser NA NA Valve tag lNV-235 NA Replaced No B Disc Dresser ACY46 NA Valve tag INV-235 NA Replacement No E

Revision 6

ASME Section Xl Manual Form NIS-2 ( Back) Section E Exibit A

<.NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items 1 through 6 on this reports included on each sheet, and (3)each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Refurbished Valve INV-235-

8. Test Conducted: Hydrostatic rI Pneumatic LI Nominal Operating Pressure E Other R Exempt 3 Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases ___NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A

.n d -a, 6 4 _

TECH SPEC Date .ZLL&,20 -

Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by HSB I AND I Compan' of Connecticut have inspected the components described in this Owners Report during the period tKSI to ?-- N1 -o5 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

______ __ _m m Commissions NC 978 ispector's Signature Date 2 1+4 ,201 5 Revision 6

ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 6/03/05 Sheet 1 of 1 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit N 1 L12 0 ]3 IL Shared (specify Units[l )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98669062-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp NLA Authorization No. N/A 3b NSM orMN # CE-100184 Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code 11 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column

_ 4 6 8 Name of Name of Manufactur N B Other Identification (Size) Year Repaired. ASME Component Manufacturer er Serial Number Built Replaced. or Code Replacement Stamped Number (yes or no)

A Valve Disc Kerotest Original NA Valve tag INV-233 NA Replaced No Valve Part B Valve Disc Kerotest 14 NA Valve tag INV-233 NA Replacement No C

F Revision 6

ASME Section XI Manual Form NIS-2 (Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Install soft seat in valve INV-233_

8. Test Conducted: Hydrostatic E Pneumatic Nominal Operating Pressure LI Other El Exempt 3 Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases __NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A eofuthorization No. N/A Signed /9? z TECH SPEC Date /.? -,20P Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTIh CAROLINA and employed by HSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period I b OS to i6

16. C)and c) state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_______k_

_ _ _ _ _ _ Commissions NC 978 Ins ector's Signature Date_6 -2& ,20_1S -

Revision 6

(

ASME Section XI Manual C Section E Exhibit A C.

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions orThe ASME Code Section XI 1.owner DUKE POWER COMPANY Ia Date 6/16105 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit [1 12 Fo3 D Shared (specify UnitsE )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986705 96-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number

_N _ u_ m __b er__

Replacement Stamped (yes or no)

A Plug Assembly CCI NA NA For valve tag INV49 NA Replaced No B Plug Assembly CCI 635278 NA For Valve tag INV849 NA Replacement No D

E Revision 6

ASME Section XI Manual Form NIS -2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (I) size is 81/2in. x II in. (2)

K.J information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work I/R Valve INV849_

8. Test Conducted: HydrostaticD Pneumatic [ Nominal Operating Pressure g Other M Exempt Z Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases __NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp NIA Expiration Date N/A Certificate of uthoization No. N/A Signed a/' 6 f TECH SPEC Date GBlS20,20

/ Owner or Owner's Desinee. Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORT11 CAROLINA and employed by IISB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period S-2.*0 5 to - 2O-5 Z, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

__ _ _ __ _ _ _ Commissions NC 978 Inspecto Si-nature Date IC7O ,20_ $ -

Revision 6 K.>

C ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 6/13105 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 31 D2 D 3 E Shared (specify UnitsE )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98683598-05 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System NC REACTOR COOLANT SYSTEM Class A

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Nameof Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number N um ber__

Replacement Stamped (yes or no)

A Valve Dresser BS-02867 NA Valve tag I NC-003 1979 Replaced Yes B Valve Dresser BS-02869 NA Valve tag 1NC-003 1980 Replacement Yes D

E=

F Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2)

\ information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work I/R Valve INC-29_

8. Test Conducted: Hydrostatic IZ Pneumatic go Nominal Operating Pressure V3 OtherO Exempt E Pressure 2230 psig Test Temp. 662 deg.F.

9. Remarks - Code Cases ___NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed /*11 o tc Owner or Owner's Designee, Title TECH SPEC Date 44? ,20P, CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLTNA and employed by HSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period S-z2-CO 5 to 6-205 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_ __ _ _ _ _ _ _Commissions NC 978 Inspector Signature Date -G -4 ,20-05 Revision 6

{

ASME Section XI Manual C Section E Exhibit A C

FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI 1.Owner DUKE POWER COMPANY la Date 7/7/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2aUnit E1 F2 EJ 3 0 Shared (specify UnitsE )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986835 43-04 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System NC REACTOR COOLANT SYSTEM Class A

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code

____Number Replacement Stamped

_ _ _ __ _ _ _ _ __ _ _ _ __ _ _ _ _(yes or no)

_ _ __ _ __ N u m ber__ _ __ _ _ _ __

A Bolting Duke Power NA NA Threaded Rod - SA 193 for S/R 1-R-NC- NA Replacement No Co. 2320 B Cotter Pin Duke Power NA NA For S/R 1-R-NC-2320 NA Replacement No Co.

C D

E==

F Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8112in. x 11 in. (2) information in items 1 through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Restore Support 1-R-NC-2320_

8. Test Conducted: Hydrostatic 2 Pneumatic LI Nominal Operating Pressure L1 Other C] Exempt 3 Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases _NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed A TECH SPEC Date 7/7 ,20A*.

/ Owner or Owner's Desienee. Titic CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by IISB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period - CS to7 -J'OSand state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Atd Inspector's Signature Commissions NC 978 Date 7 \Z . .20-* G _

Revision 6

C CS Section E Exhibit A ASME Section XI Manual FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY Ia Date 6/03/05 Sheet 1 of 1 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit E 1 El2 El 3 E-1 Shared (specify UnitsFl )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98684801-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp NLA Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code 11 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufactur N B Other Identification (Size) Year Repaired. ASME Component Manufacturer er Serial Number Built Replaced. or Code Number Replacement Stamped A Valve Disc Westinghouse 1627 NA Valve tag INV-290 NA Replaced No B Valve Disc Westinghouse 1836 NA Valve tag 1NV-290 NA Replacement No C

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Inspect Valve INV-290C

8. Test Conducted: Hydrostatic Pressure psig L Pneumatic Nominal Operating Pressurej Test Temp. deg.F.

Other a Exempt S

9. Remarks _ Code Cases ___NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp NIA Expiration Date N/A Certificate of, uthorization No. N/A Signed. Zti TECH SPEC Date _2,0

,2 Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by HS11 I AND I Company of Connecticut have inspected the components described in this Owners Report during the period 5 to &2-2 05 nd state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

__ __ __ __ om Commissions NC 978 Inspector's Signature Date . 2L ,20j0 5_

Revision 6

ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section Xl

1. owner DUKE POWER COMPANY Ia Date 8/2/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 2820 1-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit E 1 2 El 3 0 Shared (specify UnitsEl )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order# 986887771-10 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # CD 100D115 Expiration Date N/A 4 Identification of System NS CONTAINMENT SPRAY SYSTEM Class B

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code NubrReplacement Stamped Numbe_ (yes or no)

A Pipe/Fittings Duke Power C-INS 118 12"Pipe-SA403, 2" Pipe-SA376, 2" NA Replacement No Co. HI/Cplg.-SA 182, 10" Tee-SA403 B IIi II 12"Flange-SA182 11 C Bolting Duke Power NA NA Hex Nuts-SA194, Threaded Rod-SA193 NA Replacement No C o. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

D Pipe Welds Duke Power C-INS 118 INS3-19 thru 21, INS1-3, 7, 11, 8, 19, 2005 Replacement No Co. 20, 25 Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x II in. (2)

'>information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Install Test NS Test Loop_

8. Test Conducted: Hydrostatic D Pneumatic n Nominal Operating Pressure 3 Otheri- Exempt L Pressure 252 psig Test Temp. 83 deg.F.

9. Remarks _ Code Cases _N-416-2 USING SECT. 11 1992 NDE (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed A& fs TECH SPEC Date 8'Z - 20 ,20

/ Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORT1I CAROLINA and employed by IISB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period 3 18-C05 to a -e -0 5-and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_ ___ _ _ _ _ _ _ Commissions NC 978 Inspector's Signature Date ?3 9_2Osj$

Revision 6

(

ASME Section XI Manual (c Section E Exhibit A (SE FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI 1.Owner DUKE POWER COMPANY la Date 8/3/05 Sheet I of l Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Piant CATAWBA NUCLEAR STATION 2a Unit E 1 F2 II 3 LI Shared (specify UnitsE )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a WorkOrder# 98688781-11 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # CD100115 Expiration Date NIA 4 Identification of System NSCONTAINMENTSPRAYSYSTEM Class B

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code NumerReplacement Stamped (ye%Or ZoO)

Number A Pipe/Fittings Duke Power C-INS 118 12" Pipe-SA403, 2" Pipe-SA376, 2" 90 NA Replacement No Co. Ell-SA403, 12"/10" Flange-SA 182, B _ 2" II/Cplg.-SA182 10"Tee-SA403, C Bolting Duke Power NA NA Threaded Rod-SA193, Hex Nuts-SA194 NA Replacement No Co.

D Pipe Welds Duke Power C-INS 118 INS6-3,7,8,11,49,50,55 INS8-9,10,11 2005 Replacement E

CoF_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings maybe used, provided (1) size is 8112in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Install NS Test Loop B Train_

8. Test Conducted: Hydrostatic ] Pneumatic Nominal Operating Pressure Z Other i- Exempt g Pressure 50 psig Test Temp. 90 deg.F.

9. Remarks _ Code Cases _N-416-2 USING SECT. III 1992 NDE (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate ofAuthorization No. N/A Signed TECH SPEC Date . RL3 ,20 DO Owner or Owncr's Designee. Titic

/

CERTIFICATE OF INSERVICE INSPECTION

1. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by IISB I AND I Cornpanv of Connecticut have inspected the components described in this Owners Report during the period ; to fXHOC) and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in an manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. /

(I AQ° Commissions NC 978 Inspectoi's Sioniture Date 2? (Q1,20 . -

Revision 6

CC ASME Section XI Manual C.

Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI 1.Owner DUKE POWER COMPANY la Date 3/08/05 Sheet I of 1 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 3 1 D2 0-I3 D Shared (specify UnitsEI )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98690544-08 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B SV MAIN STEAM VENT TO ATMOSPHERE

5. (a) Applicable Construction Code 11 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number Replacement Stamped or no)

N u m ber__________________________(yes A Plug Assembly CCI 4 NA For Valve ISV-19 NA Replaced No B Plug Assembly CCI 2 NA For Valve ISV-19 NA Replacement Yes C.

E_.

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2)

KJ information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work IR Valve 1SV-19_

8. Test Conducted: Hydrostatic El Pneumatic LI Nominal Operating Pressure L Other n Exempt Z Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases __NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed /4ZCS TECH SPEC Date 4/i; -20 45-

/ Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTIh CAROLINA and employed by IHSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period 7 B- 6 to S -8&c5 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions NC 978 Inspe rs Signature Date 3 'Z ,20_ jo5 Revision 6

ASME Section XI Manual c Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 6/13/05 Sheet [ of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 1 112 LI 3 0] Shared (specify Units[-] )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986989 '7 1-01 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System SM MAIN STEAM SYSTEM Class B

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number N u m b er__ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Replacement Stamped (yes or no)

A Studs/Nuts Duke Power NA NA Studs- SA193 Gr B7, Nuts- SA194 Gr NA Replacement No Co. l_____2H for valve 1SM-3 l l___

B D

F __

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2)

K.1 information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work I/R Valve ISM-3_

8. Test Conducted: Hydrostatic Fo Pneumatic E Nominal Operating Pressure D OtherD Exempt Z Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases _NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed S C t TECH SPEC Date I" ,20 lb S

/ Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTHI CAROLINA and employed b HSB I AND I Companv of Connecticut have inspected the components described in this Owners Report during the period)- 2-lI (b to 6 -&I -CIS and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

L6\

Ait2,\ Commissions NC 978 Inspector's Signature DateA,.C2. ,20-OC. _

Revision 6

(7 ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 6/14/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit E I [L2 F] 3 0I Shared (specify UnitsDj )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 986989172-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System SM MAIN STEAM SYSTEM Class B

5. (a) Applicable Construction Code HI 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Replacement Stamped

__ _ __ _ _ Number _ _ _ __(yes or no)

A Bolting Duke Power NA NA Nut- SA194 Gr 2H for valve ISM-5 NA Replacement No

_ __ _ _ _ _ _ _ _ C o. _ _ _ _ _ _ _

B C

E F _

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A

NOTE

Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8112in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work I/R Valve ISM-5_

8. Test Conducted: HydrostaticE Pneumatic RI Nominal Operating Pressure L Other E Exempt E Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases __NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. N/A Signed TECH SPEC Date 4 /W 2 204EL

/ Owner or Owner's Designee, Title o

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by HSB I AND I Comprianv of Connecticut have inspected the components described in this Owners Report during the period 5-2t.- OS to 6- Id -0°5 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

p(etx-) 1VNld Commissions NC 978 Ispector's Signature Date L-g 2c ,20_0 5 Revision 6

(

ASME Section XI Manual C Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI 1.Owner DUKE POWER COMPANY la Date 7/28/05 Sheet / of /

Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 1 F12 0I 3 2 Shared (specify Units:] )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order# 98712333-14 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # CD100262 Expiration Date N/A 4 Identification of System CAAUXILIARYFEEDWATERSYSTEM Class B

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number Replacement Stamped or no)

Number____(yes A Valve Anchor ET697-1-5 1784 Valve tag ICA-57 1994 Replaced Yes Darling _

B Valve International E206A- 1-3 2032 Valve tag ICA-57 1998 Replacement Yes C Pipe/Fittings Duke Power C-ICA 121 4" Pipe-SA106, 4" 90 ell-SA2134, 4" NA Replacement No Co. Flange-SA 105 D Bolting Duke Power NA NA Hex Nuts-SA 194 Threaded Rod- NA Replacement No Co. SA193 E Pipe Welds Duke Power C-ICA 121 1491-CA.00-024-1 thru 6, 9, 10 1CA98- 2005 New No

_ Co. 11, 1CA43-16 F_

Revision 6

ASME Section Xl Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2in. x II in. (2)

'J information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Relocate Valve ICA 8. Test Conducted: Hydrostatic DI Pneumatic LI Nominal Operating Pressure M Other i- Exempt a Pressure 959 psig Test Temp. 85.8 deg.F.

9. Remarks _ Code Cases __N-416-2 USING SECT. III 1992 NDE (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date NIA Certificate of Authorization No. N/A Signed ce s? a TECH SPEC i & i i - Date

-k, 7 "Z - 2'?

- -- 20 b-

-- I Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROINA and employed by IISB I AND I Companv of Connecticut have inspected the components described in this Owners Report during the period 4-13 -O5 to A - 05 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

4d)YtAIQ. Commissions NC 978 Inspeib r's Signature Date _ I _ .20015 Revision 6

(E ASME Section XI Manual C (.

Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 7/24/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTT'E N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit E 1 E2 D3 D Shared (specify UnitsD )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 987123 62-14 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # CD100 0262 Expiration Date N/A 4 Identification of System CA AUXILIARY FEEDWATER SYSTEM Class B

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code N Replacement Stamped Number (yes or no)

A Valve Anchor ET697-1-6 1785 Valve tag ICA-61 1994 Replaced Yes Darling B Valve BWIP E206A-1-2 2031 Valve tag 1CA-61 1998 Replacement Yes International C Pipe/Fittings Duke Power C-ICA 121 4" Pipe- SA106, 4" 90 Ell-SA234, 4" NA Replacement No Co. Flange- SA105 D Bolting Duke Power NA NA Threaded Rod- SA193, Hex Nuts- NA Replacement No Co. SA194 E Pipe Welds Duke Power C-ICA 121 ICA125-11, 1491-CA.00-023-1 thru 9 NA Replacement No Co. 13 Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2)

" 'j information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Relocate Valve ICA-61_

8. Test Conducted: Hydrostatic 2 Pneumatic LI Nominal Operating Pressure M OtherF Exempt Fl Pressure 1780 psig Test Temp. 120 deg.F.

9. Remarks _ Code Cases __N-416-2 USING SECT. III 1992 NDE (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of uthorization No. N/A Signed /g>L TECH SPEC Date Z ,20 Cr

/ Owner or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTIh CAROLINA and employed by HSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period 4.l3 <* to Z -c5-05and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied. concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_ _ _ _ _ _ _ _ Commissions NC 978 I spector's Signature Date7 ,20_0S 2Q Revision 6

C ASME Section XI Manual

( Section E Exhibit A 1i FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 2/23/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 3 1 E2 D3 D Shared (specify UnitsD )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 987140i44-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp NLA Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B ND RESIDUAL HEAT REMOVAL SYSTEM

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Comnponents Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column

_ 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Number Replacement Stamped or no)

Number_________________________(yes A Bolting Duke Power NA NA Threaded Rod-SA193, Hex Bolt-SA194 NA Replacement No Co. for RHR HX IA B

C==

FI Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2)

\>- information in items 1 through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work RIR RHR HX IA Bolting_..

8. Test Conducted: Hydrostatic El Pneumatic E Nominal Operating Pressure E OtherO Exempt Z Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases _NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of uthorization No. N/A Signed ,

/i&A&Adse 4 ~X TECH SPEC Date zip ,20 -f 7 Owner or Owner's Designee, Titl CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by HSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period 2--.2.. OS to S --ih 5 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

_______________ >NCommissions NC 978 Inspecr's Signature Date . \ _-,2032) -

Revision 6

(C ( ib'.'

Section E Exhibit A\

ASME Section XI Manual FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 3/31/05 Sheet 1 of 1 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit E 1 D2 L 3 El Shared (specify UnitsE )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98714044-04 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B ND RESIDUAL HEAT REMOVAL SYSTEM

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column 1 Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code NumberReplacement Stamped (yes or no)

Number A Bolting Duke Power NA NA Rod- SA193, Hex Nuts- SA194 for RHR NA Replacement No Co. FIX "IA" 1I CoTX Revision 6

ASME Section XI Manual Form N1S-2 ( Back) Section E Exibit A

,1 J NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2)

<. information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work RIR RHR HX IA Bolting_

8. Test Conducted: Hydrostatic [2 Pressure psig Pneumatic a Nominal Operating Pressure Test Temp. deg.F.

El Other :1 Exempt 3

9. Remarks _ Code Cases _NONE_

(Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of Authorization No. NIA Sis0ned b

w , A,

)/ -

D2~

I u [, _ TECH SPEC Date :V/ 20 Owner or Owner's Designee. Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of. NORTH CAROLINA and employed by HSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period 3--ISSŽ to 4A 1t-0S and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspeLt on.

_ _ A _t_tur

_ _ _ _ Commissions NC 978 D2spector's Signature Date _ -k,20LU-Revision 6 s_,

ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI

1. Owner DUKE POWER COMPANY la Date 6/16/05 Sheet I of I Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2aUnit E F 12 L13 E Shared (specify UnitsD )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 987286 78-01 Address 526 S. Church St. Charlotte, N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System NI SAFETY INJECTION SYSTEM Class A

5. (a) Applicable Construction Code III 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1992 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired. ASME Component Manufacturer Serial Number Built Replaced. or Code Replacement Stamped Number (yes or no)

A Weld Duke Power C-1NI 128 Seal weld Bonnet to Body for valve with NA Replacement No Co. tag# 1N19.

E F===

Revision 6

-ZA~.SME Section XI Manual Form NIS-2 ( Back) Section E Exibit A NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (I) size is 81/2in. x 11 in. (2) information in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Seal Weld Bonnet to Valve Body 1N119_

8. Test Conducted: Hydrostatic E] PneumaticD Nominal Operating PressureD Other  :] Exempt Z Pressure psig Test Temp. deg.F.

9. Remarks _ Code Cases _N-416-2 USING SECT. III 1992 NDE (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A

.rtiticate ofituothorization No. N/A TECH SPEC Date AOZ ,207 l ~Owner or Owvncr's Designee. Title ----

CERTIFICATE OF INSERVICE INSPECTION I. the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by HSB I AND I Companv of Connecticut have inspected the components described in this Owners Report during the period S-a2.0 5 to &,2-0-O5 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Commissions NC 978 Insp c r's Signature L j, _- 2.D,20_C7 -

Revision 6

Problem Investigation Process Catawba NuclearStation C _

}C-04-02215 3l

_jLs7-Problem Identification Discovered Time/Date: 07:39 05/0612004 Occurred Time/Date:

Unit(s) Affected:

Unit Mode %Power Unit Status Remarks 1 1]00 System(s) Affected:

NV Chemical & Volumc Control Affected Equipment (No Equipment Affected)

Location of Problem:

Bldg: Column Line: Elev:

Location Remarks:

Method Used to Discover Problem:

r Problem

Description:

'lIS-2 form on work order 98588027-01 was not completed and submitted for inclusion in the 1EOC14 refueling cycle Inservice Inspection report.

Detail Problem

Description:

Last Updated By: CLS4586: SMITH, CARLTON L Team: RSB2070 Group: WCG Date: 05/06/2004 ASME Section Xl Repair/Replacement code requires the owner to file a Inservice inspection report within 90 days of the completion of the refueling cycle. Work order 98588027-01 was not received by the work control coordinator until after all NIS-2 (Owner Report for Repair or Replacement) forms were submitted for inclusion in the IEOC14 recycle period Inservice inspection report. PIP C-04-1639 was written to address why this work order was not signed and completed within 30 days of Labor Complete according to MNT Directive 2.20.

Last Updated By: CLS4586: SMITH, CARLTON L Team: RSB2070 Group: WCG Date: 05/06/2004

'Originated By: CLS4586: SMITH, CARLTON L Team: RSB2070 Group: WCG Date: 05/06/2004 Other Units/Component.s.Svstems/Areas Affected(YANMU): N Industry Plants Affected(YNU): U Immediate Corrective Actions:

rimMediate Corrective Action Documents / Work Orders:

Indiv Team Group Date 08111/2005 14.20 PageI PIP No: C-04-02215

Problem Investigation Process CatawbaNuclear Station

• em Identified By: CLS4586RSB2070 WCG 05/0612004

\ lem Entered By: CLS4586RSB2070 WCG 05/06/2004 Screening Action Category: 3 Root Cause performed? No OEP No:

Other Report Nos:

Event Codes:

Ala Adherence\Failure to follow procedure\Administrative xi General Work Execution Screening Remarks:

This PIP was screened by the PIP Centralized Screening Team on 5/10/04.

Originated By: MLS9465: STANDRIDGE, MICKEY L Team: PAM7334 Group: SRG Date: 05/10/2004 Assienments:

Responsible Groups(s) for Problem Evaluation: MNT Maintenance Responsible Group for Present Operability: N/A P-,ponsible Group for Report Support Info: N/A onsible Group for Reportability: N/A

\.uonsible Group for Overall PIP Approval: WCG Work Control 1 _ _ __ _ U l Screened By: MLS9465 PAM7334 SRG 05/1012004 Present Operability Responsible Group: Status:

Sys/Comp Operable? (Y,N,C,ET):

Required Mode:

Comments:

No Current Signatures For This Section Reportabilitv Responsible Group: Status:

Problem Reportable(Y,N,E):

"oortable Per:

K n4mcnts:

No Current Signatures For This Section 081111205 14.20 Page2 PIP No: C-04-02215

Problem Investigation Process Catawba Nuclear Station "Iv. -'estig~ation Report:

Responsible Group: Act Date:

Investigator: Group:

Due Date:

Date Due to VP or Sta. Mgr:

Date Regulatory or Agency Rpt Due:

Date Investigation Report Approved:

NRC Cause Codes:

Report Support Info:

Responsible Group: Status:

No Current Signatures For This Section Problem Evaluation l RI Cause Determination Not Required Yes NIAI

,,rlem Evaluation From: Resp. Group: MNT Status: Closed OEDB Checked: No Problem ASME Section XI Repair/Replacement code requires the owner to file a In-service inspection report within 90 days of the completion of the refueling cycle. Work order 98588027-01 was not received by the work control coordinator until after all NIS-2 (Owner Report for Repair or Replacement) forms were submitted for inclusion in the IEOCI4 recycle period In-service inspection report. PIP C-04-1639 was written to address why this work order was not signed and completed within 30 days of Labor Complete according to MNT Directive 2.20.

Apparent Cause (NIA)

Apparent Cause for this issue is covered in PIP C-04-01639. Duplicate P/E is not required.

OEDBI Comments:

Remarks Comments:

Due Date: 06105/2004 Accepted BY: RNT9231 DBO8337 MNT 05/12/2004

^ ssigned To: EXJ9391 DBO8337 MNT 05/12/2004 A..vn Aeen

-. rlT-- JWC4686 JWC4686 MNT 06107/2004

% n,va. fl3fl3i6,IA n. J.

\-~..T~dv For Anoroval: FAK4452 CWT7322 MNT 09/30/2004 I Approved By: FAK4452 CWT7322 MNT 09/30/2004 Page 3 PIP No: C-04-02215 08/11/2005 14:20 0811112005 14:20 Page 3 PIPNo: C-04-02215

Problem Investigation Process Catawba NuclearStation

\o 4rrective Actions No Corrective Actions for this PIP Finaland Overall PIPApproval Responsible Group: WCG Status: Closed Assiged To: WCG 0511012004 A roval Assigned To: RSB2070 WCG 06/08/2004 Aproved By: FAK4452 RSB2070 WCG 09/300oo4 Any Supplemental Concurrence Signatures Above Do Not Affect PIP Closure.

Closure Document Type Closure Document No Attachments Gen eric Applicability Responsible Group: Status:

r) PIP No:

-> .ssent Remarks:

No Current Signatures For This Section FailurePreventionInvestigation No FPI Records for this PIP.

Remarks No Remarks for this PIP.

Maintenance Rule No Maintenance Rule Records for this PIP.

End of the Document for PIP No: C-4-2215 The status of this PIP is: Closed The duration of this PIP was: 147 days Page 4 PIP No: C-04-02215 08/1112005 14:20 0811112005 14:20 Page 4 PIto:s C-04-02215

( Section Xi Repair/Repla( .nt Activities For 1EOC14 Flaw

(

Indication Code Repair, Maint! ISI Owner ANII Work Order Class Sys MOD No. Type of Inspection Description of Work Replacement (*Yes No) Final Final 98555521-07 A NI NA VT Replace Spare Valve Disc Replacement No 4/28/03 4/30/03 98579251-04 A NC NA VT Repl.Piv. Pin 1-R-NC-1644 Replacement No 12/8/03 12/22/03 98579343-05 A NC NA VT Stud for 1NC-03 Replacement No 12/15/03 1/5/04 98607917-01 A NI CE72592 VT Disc for l NI60 Replacement No 2/17/04 2/18/04 98466044-01 B ND CE-70741 Pressure Test Replace 1ND-27 Replacement No 1/5/04 1/12/04 98466045-01 B ND CNCE7O741 Pressure Test Valve 1ND26 Replacement No 2/5/04 2/9/04 98481880-01 B NV NA Pressure Test Disc for 1NV-235 Replacement No 2/12/04 2/17/04 98497026-01 B CA NA VT Disc for valve DMV-934 Replacement No 9/30/03 10/1/03 98507281-01 B SV NA VT Valve Disc 1SV-14 Replacement No 1/12104 1/21/04 98542866-05 B NV NA VT Valve Disc 1NV186A Replacement No 1/12/04 1/27/04 98562071-03 B NA NA VT Weld stud to disc Repair No 7/29/03 8/4/03 98579406-06 B ND NA Pressure Test Valve 1ND-35 Replacement No 1/7/04 1/8/04 98579407-05 B ND NA Pressure Test Valve 1ND-38 Replacement No 1/6/04 1/19/04 98579408-05 B ND NA Pressure Test Replace 1ND-64 Replacement No 12/15/03 12/23/03 98579554-06 B NI NA Pressure Test Replace 1NI-102 Replacement No 12/15/03 12/23/03 98579555-06 B NI NA Pressure Test Replace 1Nl-1 19 Replacement No 12/15/03 12/23/03 98579556-06 B NI NA Pressure Test Replace 1NI-151 Replacement No 12/15/03 12123/3 98579557-06 B NI NA Pressure Test Replace 1NI-161 Replacement No 12/15/03 12/23/03 98580152-07 B NV NA Pressure Test Replace 1NV-87 Replacement No 1/5/04 1/12/04 98580153-06 B NV NA Pressure Test Repl. 1NV-222 Replacement No 12/8/03 12/123/03 98580154-07 B NV NA Pressure Test Valve 1NV-223 Replacement No 1/12/04 1/21/04 98580155-06 B NV NA Pressure Test Valve 1NV-273 Replacement No 1/7/04 1/8/04 98582138-01 B SV NA VT Replace 1SV-5 Disc Replacement No 1/5/04 1/12/04 98582139-01 B SV NA VT Disc for 1SV-12 Replacement No 1/19/04 1/28/04 98582140-01 B SV NA VT Repl. Disc for 1SV-16 Replacement No 12/8/03 12/22/03 98582141-01 B SV NA VT Repi. Disc for 1SV-21 Replacement No 12/8/03 12/22/03 98582142-01 B SV NA VT Valve Disc 1SV-22 Replacement No 1/12/04 1/27/04 98583695-01 B ND NA Pressure Test Valve 1ND-3 Replacement No 1/7/04 1/8/04 98588027-01 B NV NA VT Disc for 1NV338 Replacement No 5/10/04 5/10/04 98589613-01 B SM NA VT Bolting for Valve 1SM-1 Replacement No 1/6/04 1/20/04 98598683-01 B SV NA VT Disc for 1SV003 Replacement No 2/25/04 2/26/04 98598685-01 B SV NA VT Valve Disc 1SV-6 Replacement No 1/12/04 1/27/04 98598686-01 B SV NA VT Valve Disc 1SV-17 Replacement No 1/12/04 1/21/04 98598687-01 B SV NA VT Replace 1SV-18 Disc Replacement No 1/5/04 1/12/04 98598689-08 B ND NA Pressure Test Valve 1ND-31 Replacement No 1/7/04 1/8/04

• If Yes, state Maint or ISI and list PIP Number

C, Section Xl Repair/Repla( nt Activities For 1EOC1 4 Replace Snubbers 1-R-ND-C-

98599292-01 B ND NA VT 391 _ Replacement No 7/1/03 7/2/03 98608103-01 B NV NA Pressure Test Replace valve 1NV14 Replacement No 8/26/03 8/27/03 Rotating Assembly for RHR 98617265.01 B ND NA Pressure Test Pump 1B Replacement No 1/6104 1/6/04 98624220-10 B NS 11446/01 Press. TestiUT/RT/PT NS HX 1B Replacement No 1/19/04 1/20/04 98626503-03 B ND NA Pressure Test/RT Weld 1ND50-15,16 Replacement No 1/20/04 1/28/04 98626503-14 B NS 11446/01 VT Weld Repair to NS HX lB Repair No 2/11/04 2/11/04 98626936-07 B NS NA VT Repl. Bolting to NS HX 1A Replacement No 12/9/03 1/5/04 98626936-07 B NS NA VT NS HX 1B End Cover Replacement No 12/9/03 1/5/04 98630051-01 B NV NA VT Valve Disc 1NV-75 Replacement No 1/12/04 1/21/04 98630052-01 B NV NA VT Disc for 1NV-81 Replacement No 1/7/04 1/8/04 98634236-11 B NI NA Pressure TesVPT Valve 1N1168 Replacement No 1/19/04 1/28/04 98635803-01 B SM NA VT Snubber 1-R-SM-1 578 Replacement No 1/6/04 1/19/04 98636819-01 B NV NA VT Bolting for 1NVFE5150 Replacement No 1/12/04 1/21/04 Bolting for NC Pump Motor 98053998-02 C NC NA VT "1An Replacement No 1/5/04 1/8/04 Replace Piping and Clean 98055715-09 C RN NA Pressure Test Valve Replacement No 5/28/03 6/3/03 98055716-07 C RN NA Pressure Test Replace RN Piping Replacement No 6/5/03 6/5/03 98127762-01 C KC CE-70747 Pressure Test Replace 1KC-7 Replacement No 1/5/04 1/21/04 98127763-01 C KC CE-70747 Pressure Test Valve 1KC-9 Replacement No 1/12/04 1/27/04 98391120-01 C YC NA VT Replace Disc & plug to lYC65 Replacement No 9/17/02 9/17/02 98464539-01 C RN NA VT Replace Disc for 1RNE1 4 Replacement No 7/1/03 7/2/03 98477579-01 C YC NA VT BMR End Bell Cover Repair No 4/9/02 4/9/02 98477579-03 C YC NA VT BMR End Bell Cover Repair No 4/9/02 4/9/02 98479788-01 C RN NA Pressure Test Replace 42K RN Piping Replacement No 2/4/03 2/12/03 98491077-02 C KD CE-72054 Pressure Test Replace 1KD-27 Replacement No 1/5/04 2/9/04 98494197-06 C VG NA VT Re-tube & Replace Endbell Replacement No 10/22/02 10/30/02 Base Metal Repair to valve 98497966-03 C KC NA VT disc for 02B-326 Repair No 2/5/03 2/10/03 Base Metal Repair to valve 98502929-03 C KC NA VT disc for 02B-326 Repair No 2/6/03 2/10/03 98504434-05 C NS NA VT Add bolting for NS HX 1A Replacement No 5/29/03 6/3/03 98524432-05 C KC NA Pressure Test Replace Rotating Element Replacement No 1/16/03 1/20/03 98542240-02 C VG NA VT Retube Aftercooler 1B2 Repair No 3/6/03 3/7/03 Maint C 98547481-01 C RN NA Pressure Test Weld Repair 1RN523-4 & 5 Repair 5258 11/4/02 11/6/02 98578753-01 C CA NA VT Repl. Disc for 1CA-173 Replacement No 12/8/03 1/5/04

• If Yes, state Maint or ISI and list PIP Number

C 98578835-03 p-C

.9. -

CF NA Section Xl Repair/Repla(

VT nt Activities For 1EOC14 Valve 1CF-37 Plug p -

Replacement No P - -

1/6/04 (1/20/04 98580279-01 C KD NA VT Studs for DIG HX Replacement No 117/04 1/19/04 98580320-01 C KC NA Pressure Test 1KC-5 Valve Bonnet Replacement No 1/7104 1/20/04 98580345-04 C KC NA Pressure Test Replace 1KC-281 Replacement No 1/5/04 1/20/04 98580367-22 C RN NA VT Replace 1-R-RN-0195 Replacement No 12/8/03 12/22/03 98580367-34 C YC NA VT Repl. Clamp for 1-A-YC-3392 Replacement No 12/8/03 12/22/03 98585666-06 C NV NA Pressure Test Valve 1NV-182 Replacement No 1/13/04 1/19/04 98585667-01 C RN NA Pressure Test Replace 1RN-288 Replacement No 1/6/04 1/21/04 98585676-04 C KC NA Pressure Test Valve 1KC-61 Replacement No 1/19/04 1/27/04 98587157-01 C RN NA VT Disc for 1RN244A Replacement No 2/11/04 2/12/04 98588380-01 C KC NA Pressure Test KC Pump 1B1 Replacement No 1/12/04 1/21/04 98592156-02 C RN NA Pressure Test NSW 1B Pump Assembly Replacement No 1/20/04 1/28/04 98597950-04 C RN NA Pressure Test Replace RN Piping Replacement No 6/2/03 6/2/03 98598049-06 C RN CE62231 Pressure Test Add Flush Connection New No 6/3/03 6/4/03 Add Inspection Ports to NS HX 98598083-03 C NS CE-72486 Pressure Test 1A Repair No 5/29/03 6/2/03 98599190-06 C RN CE62232 Pressure Test Add Connection for RN New No 7/2/03 7/7/03 98600348-01 C RN NA VT Disc for 1RN304A Replacement No 2/11/04 2/12/04 98601549-15 C RN CE62235 Pressure Test Add RN Flush Line New No 8/7/03 8/11/03 Add Inspection Ports to NS HX 98602830-01 C NS CE62237 Pressure Test 1A New No 8/26/03 8/27/03 98617674-01 C RN NA VT Disc for 1RN-854 Replacement No 2/5/04 2/9/04 98617674-04 C RN NA Pressure Test Replace Valve 1RN854 Replacement No 11/11/03 11/16/03 98621567-01 C VG NA VT 2VG HX Tubes Replacement No 1/7/04 1/19/04 98621997-01 C RN NA Pressure Test RN Piping Replacement No 2/5/04 2/9/04 98632492-10 C NC NA VT Attachment Weld Replacement No 1/19/04 1/28/04 98646314-01 C RN NA Pressure Test Valve body for 1RN351 Replacement No 2/5/04 2/9/04 98053998-01 NF KC CNCE72918 VT S/R 1-R-KC-1211 Replacement No 2/10/04 2/11/04 98585632-05 NF CA NA VT 1-R-CA-1 682 Replacement No 1/20/04 1/28/04 98633113-01 NF KC NA VT Surge Tank 1A" Support New No 2/10/04 2/11/04 98633114-01 NF KC NA VT Surge Tank N1BNSupport New No 2/10/04 2/11/04

• If Yes, state Maint or ISI and list PIP Number

,IC ASME Section XI Manual Section E Exhibit A FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required By The Provisions Of The ASME Code Section XI 1.Owner DUKE POWER COMPANY la Date 5/10/04 Sheet 1 of 1 Address 526 S. CHURCH STREET. CHARLOTTE N.C. 28201-1006

2. Plant CATAWBA NUCLEAR STATION 2a Unit 1 E2 F ]3 LI Shared (specify UnitsML )

Address 4800 CONCORD RD. YORK, S.C. 29745

3. Work Performed By Duke Power Company 3a Work Order # 98588027-01 Address 526 S. Church St. Charlotte. N.C. 28201-1006 Type Code Symbol Stamp N/A Authorization No. N/A 3b NSM or MN # NA Expiration Date N/A 4 Identification of System Class B NV CNEMICAL VOLUME CONTROL SYSTEM

5. (a) Applicable Construction Code m 1974 Edition, S'75 Addenda, Code Cases_

(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 1989 Addenda NONE

6. Identification of Components Repaired or Replacement Components Column I Column 2 Column 3 Column Column 5 Column Column 7 Column 4 6 8 Name of Name of Manufacturer N B Other Identification (Size) Year Repaired, ASME Component Manufacturer Serial Number Built Replaced. or Code Number Vae NAA(yes Replacement Starnped or no)

A Valve Disc Anchor NA NA For Valve lNV338 with SN# E1581 NA Replaced No Darling 1 and NB# 694 B Valve Disc Anchor See attached NA Valve INV338 NA Replacement No Darling Data Report P

Dt1IIlI1 E =

Revision 6

ASME Section XI Manual Form NIS-2 ( Back) Section E Exibit A qOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 81/2in. x 11 in. (2)

\ .nformation in items I through 6 on this reports included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.

7. Description of Work Replace Disc for INV338_

8. Test Conducted: Hydrostatic [i1 Pressure psig Pneumatic [I Nominal Operating Pressure Test Temp. deg.F.

n Other E1 Exempt Z

9. Remarks _Code Cases _NONE_

_Reference PIP C-04-2215 (Applicable Manufacturers Data Records to be attached)

CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this repair or replacement conforms to the rules of the rules of the ASME Code,Section XI.

Type Code Symbol Stamp N/A Expiration Date N/A Certificate of A thorization No. N/A Sirned

-- Cal----

- J Am C7 n TECH SPEC Date - 2 ,203A

/ - Owner or Owner's Dsignee, Titic K.

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of NORTH CAROLINA and employed by HSB I AND I Company of Connecticut have inspected the components described in this Owners Report during the period i1 "03 to Boy-'1 and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measure described in this Owners Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

RLASiwz In ector's Signature A Commissions NC 978 Date )JD_,20_Q-0 -

Revision 6

/17 7fl'- 7vCf<%a~

FORM N.2 NPT CERTlICAThLOLDERS' DATA REPORT FOR NUCLEAR P r AND APPIRTENANCES-As required by the Provisioaof the ASM.E Code Rule3. Scction III. Div. I 1ffc?-,dOff I y Anchor/Darling Valve Co., 701 First St., Williamsport, PA 17701

($am. AR4 a44ie CCMr7 C9M CLC2 . Helden (b)Magcted tot Mill Power SuoplyvCo./Duke Power, P.O. Box 32307, Charlotte, NC 28232-2307 (Nas" a" 0ddvu= et n Cursdeatt idder fix elns14 nudea* tompoftu

2. Idtcntlat-certUrcate Holder`3 Scrl2l No. of Pm t-aei " No. N/A

,a) Csciucred ~oa~Ziz D^, ^N 63796 RI/- DrAWtng~FrLd Anchor/Darlinq Valve Company (b) Dascript~ad of`Patltapecd (6) 2"-1878-DD Disc, Heat No. 229I D-STL6 (c) Applical(E CodeiSodlEdidca 1980 . ddedade1 e Sum '80 CeNa I~ls 1

3. Rcs 2"-1878-DD Disc (Ietal d..ei .< @.C t oe wnica d,.-,, Ww.dual.i Wd A/DV S.O. & Item P.4571-50 Original S.0. E-1581 No Hydrotest Performed le certify tmtctbe stacements mde in dthi report are coriwv acid this vessel put oe appnenance &a.defined in the Code cook IcnsM to the ruleu of Coosastciod of the ASWE Codw Section M.

(Tne awpvicable Dcsig Specinfctcon and Suse Report are not Me responslbilitY of the NFr Certificate Holder for pdm. An .NPT CertU-icatc Holder for appunrtcnsae Is repoasibM for humishing a sparate Dcsign Specilkazlon and Stress Repon. if the appurtcaee ih not included In the component D gnSpecdflcaton and Stes Repo.)

Dat J1e1 9 2IL S,.,d Anchor/Darling Valve Co. 5

)

t" Ca~cuto "4de

.,.rxcoc f Autohadt ti Espirsu. 4/15/86 Cettificace of Auchoirzstion No. N1713 CERTIFICATION OF DESIGN FOR APPURTENANCE (when pplicsble)

Design ifonmtion oa (tiC Stess mailysia repaet on file a_ ____

Design pecificidous eetnified by Prof. ELg. State Reg. Ne..

Stress analyii meport certified b Prof.EngaStRe _ g.No.

r ...........

• CER FICATE OF SHOP INSPECTION 1, the undeesigned, bolding a valid coina *o iisxed by dhe National Board of Bailef and Ptessure Vessel nrapectoes ftnoe the Stt exxUAr4o Pennsyvani a __d L sploy4 byCommercial Union Insurance Company or Bo5ton, Mass. have iapected the p_ of a pressuge 'eszel described in this Par" Dataneorton R .-IL 0 U 1LI - 1sLJ.,ndstatet cote b-stotmy knowledse and bellef, the NP? Certniteste Holder itt* codstructed tis part in accotdance with the ASME Code Secton U!.

By signing this cerificare. tich-er the Inspector nor his esmployer makes air waatrahy expecszed or implied, concern-Ing the part described In thits Partial Data Report. Frurthermor.. neither the Insvector nor his employer 3hall be liabl in y manner toe &ay persooal injury orpropeM damage or a Ia atoany kind £tisiag Ifar or connerdrd iwch dhis inspection.

Da /- I - 9 f Y orlwxons -

PPnn-lvva a

• nai 2236 I - . *.i-Gardoer./ Ktfe4a" Uo-d. Stat. PVVu1fC aond N..

, _.d-.JA8h4 &. f- 41 &1W2e. thsu Qqfdas.dg 1 b. *A.e4 5

,Visi6 tl) *&BO to 1- a I,()

'. Weft.cse. . i-.* 1 lIS*

. £q000 W %Mt r" 04.4. .. .. . - 3 E. .. 4....,. .4...s a-i. VY,. ..

(01772 Th-i form K004oi may be obtsiftod from t m. Order O~a'i.. ASME, 34G5 C. Altht St.. Now York. N.Y. 10017

6.0 Pressure Testing This summary is a pressure test completion status for the third period of the second ten-year interval. Table 6-1 shows the pressure tests completed from refueling outage EOC-14 through refueling outage EOC-15. There was no through-wall leakage observed during these pressure tests.

Table 6-1 Total Examinations Examination Test Requirement Credited For This Outage Category B-E System Hydrostatic Test (IWB-5222) 0 B-P System Leakage Test (IWB-5221) 1 B-P System Hydrostatic Test (IWB-5222) 2 C-H System Inservice/Functional Test (IWC-5221) 0 C-H System Hydrostatic Test (IWC-5222) 22 Table 6-2 shows a completion status of pressure tests conducted during the third period K> of the second ten-year interval.

Table 6-2 Total Total (%)

Examination Test Requirement Examinations Examinations Examinations Category Required For Credited For Complete For This Period This Period This Period B-E System Hydrostatic 1 1 100%

Test (IWB-5222)

B-P System Leakage Test 1 1 100%

(IWB-5221)

B-P System Hydrostatic 12 12 100%

Test (IWB-5222)

_ . , P i. rt!-.--. i*1. -' ' '_,

C-H System 0 0 0%

Inservice/Functional Test (IWC-5221)

C-H System Hydrostatic 31 22 100%

Test (IWC-5222)

EOC 15 Refueling Outage Report Page 1 of 3 Catawba Unit 1 Revision 0 Section 6 June 15, 2005

A~I- Table 6-3 shows the completion data of the Class 1 (Category B-P) Leakage and Hydrostatic tests conducted during ref uelina cycle EOC1 5.

Table 6-3 Detailed Class 1 Listina EOC15 Zone Completion EOC15 VT-2 Test Type Number Boundary Dwg Status Examination Date Leakage 1NC-001 L-A CN-ISIL-1553-1.0 Complete 04-Jun-05 CN-ISIL-1553-1.1 Complete 04-Jun-05 CN-ISIL-1554-1.0 Complete 04-Jun-05 CN-ISIL-1554-1.5 Complete 04-Jun-05 CN-ISIL-1561-1.0 Complete 04-Jun-05 CN-ISIL-1561-1.1 Complete 04-Jun-O5 CN-ISIL-1562-1.0 Complete 04-Jun-05 CN-ISIL-1562-1.1 Complete 04-Jun-05 CN-ISIL-1562-1.2 Complete 04-Jun-05 CN-ISIL-1 562-1.3 Complete 04-Jun-05 1MJ-001L-A CN-ISIL-1553-1.0 Complete 14-May-05 CN-ISIL-1 553-1.1 Complete 14-May-05 CN-ISIL-1554-1.0 Complete 14-May-05 CN-ISIL-1562-1.1 Complete 14-May-05 Hydrostatic 1NC-004H-A CN-ISIH-1554-1.0 Complete 04-Jun-05 K> 1NC-009H-A CN-ISIH-1562-1.0 Complete 04-Jun-05 Table 6-4 shows the completion data of the Class 2 (Category C-H) Hydrostatic tests conducted during refueling cycle EOC15.

Table 6-4 Detailed Class 2 Listing EOC15 EOC15 VT-2 Completion Examination Zone Number -Boundary Dwg Status Date 1 1FW-001 H-B CN-ISIH-1554-1.2 Complete 27-Jan-04 CN-ISIH-1554-1.7 Complete 27-Jan-04 CN-ISIH-1561-1.0 Complete 27-Jan-04 CN-ISIH-1562-1.2 Complete 27-Jan-04 CN-ISIH-1563-1.0 Complete 27-Jan-04 CN-ISIH-1570-1.0 Complete 27-Jan-04 CN-ISIH-1571-1.0 Complete 27-Jan-04 2 1FW-002H-B CN-ISIH-1571-1.0 Complete 02-Jun-04 3 1KF-001 H-B CN-ISIH-1570-1.0 Complete 12-Jan-04 4 1Nl-002H-B CN-ISIH-1562-1.1 Complete 03-Jun-05 CN-ISIH-1562-1.2 Complete 03-Jun-05 5 1 NI-003H-B CN-ISIH-1562-1.2 Complete 26-May-05 CN-ISIH-1 562-1.3 Complete 26-May-05 EOC 15 Refueling Outage Report Page 2 of 3 Catawba Unit 1 Revision 0 Section 6 June 15, 2005

EOC15 EOC15 VT-2 Completion Examination Zone Number Boundary Dwg Status Date 6 1NI-005H-B CN-ISIH-1 562-1.2 Complete 25-Mar-04 7 1NI-006H-B CN-ISIH-1562-1.2 Complete 04-Jun-05 8 1NI-007H-B CN-ISIH-1562-1.2 Complete 26-May-05 9 1NI-008H-B CN-ISIH-1562-1.2 Complete 26-May-05 10 1NI-009H-B CN-ISIH-1 562-1.2 Complete 26-May-05 11 1NI-01OH-B CN-ISIH-1562-1.0 Complete 26-May-05 12 1NM-001 H-B CN-ISIH-1572-1.0 Complete 04-Jun-05 13 1NM-002H-B CN-ISIH-1572-1.0 Complete 04-Jun-05 14 1NS-001 H-B CN-ISIH-1563-1.0 Complete 07-Apr-04 15 1NS-002H-B CN-ISIH-1563-1.0 Complete 24-Jun-04 16 1NV-002H-8 CN-ISIH-1554-1.7 Complete 01 -Jun-04 17 1NV-003H-B CN-ISIH-1554-1.7 Complete 19-Apr-04 18 1NV-004H-B CN-ISIH-1,554-1.2 Complete 28-Feb-O_

19 1NV-005H-B CN-ISIH-1 554-1.2 Complete 16-Feb-05 20 1NV-006H-B CN-ISIH-1554-1.0 Complete 21-Apr-04 CN-ISIH-1554-1.1 Complete 21 -Apr-04 CN-ISIH-1554-1.2 Complete 21 -Apr-04 CN-ISIH-1 554-1.4 Complete 21-Apr-04 CN-ISIH-1554-1.5 Complete 21 -Apr-04 CN-ISIH-1554-1.6 Complete 21 -Apr-04 CN-ISIH-1554-1.7 Complete 21 -Apr-04 CN-ISIH-1556-1.0 Complete 21 -Apr-04 CN-ISIH-15562-1.0 Complete 21 -Apr-04 CN-ISIH-1562-1.2 Complete 21 -Apr-04 21 1NV-008H-B CN-ISIH-1554-1.2 Complete 04-Jun-05

_ CN-ISIH-1 554-1.0 Complete 04-Jun-05 22 1SA-001 H-B CN-ISIH-1593-1.1 Complete 12-Jan-05 Section 6 Prepared By: Date:

1 c ,K 6a, - 6 / 5 /

Section 6 Reviewed By: Date:

£. (a I (O EOC 15 Refueling Outage Report Page 3 of 3 Catawba Unit 1 Revision 0 Section 6 June 15, 2005

Steanz GeneratorOutage Summary Report Catawba Unit 12005 Outage EOC 15 Location: 4800 Concord Road, York South Carolina 29745 NRC Docket No. 50-413 National Board No. 130 Commercial Service Date: June 29, 1985 Owner: Duke Energy Corporation 526 South Church St.

Charlotte, N.C. 28201-1006 Revision 0 Prepared By: zy ,m Date: . -/, -Ze Reviewed By: 1. f- Date: _ F____ _

Approved By: Date: ___

. Copy No. - I Assigned To: -AIeC atei toI, 10°2 Controlled: X Uncontrolled: ____

V\./I 0

ControlledDistribution Copy No. Assigned To Original Catawba Nuclear Station Document Control Master File CN-208.21 NRC Document Control 1

UncontrolledDistribution 2 Hartford Steam Boiler Inspection and Insurance Co. (AIA)

Electronic Steam Generator Desktop

-33 Pages FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules

1. Owner: Duke Energv Corporation. 526 S. Church St.. Charlotte. NC 28201-1006 (Name and Address of Owner)

2. Plant: Catawba Nuclear Station. 4800 Concord Road. York, S. C. 29745 (Name and Address of Plant)

3. Plant Unit: 1

4. Owner Certificate of Authorization (if required) N/A

5. Commercial Service Date: June 29. 1985

6. National Board Number for Unit 130

7. Components Inspected:

Manufacturer State or National Component Manufacturer Serial No. Province No. Board No.

Steam Generator 1A BWI 770101 N/A 151 Steam Generator 1B BWI 769304 N/A 150 Steam Generator 1C BWI 769302 N/A 147 Steam Generator 1D BWI 769303 N/A 149 Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1) size is 81/2 in. x 11 in., (2) informationin items lthrough 6 on this data report is-included on each sheet, and (3) each sheet is numbered'and the number of sheets is recorded at the top of this form.

I oII-3

c.

FORM NIS-1 (Back)

8. Examination Dates /, - 3/-V to /x - /0 - a -

9. Inspection Period Identification: Third

10. Inspection Interval Identification: Second

11. Applicable Edition of Section XI 1989 Addenda None

12. Date/Revision of Inspection Plan: Per CNS Technical Specification

13. Abstract of Examinations and Test. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan.

14. Abstract of Results of Examination and Tests.

15. Abstract of Corrective Measures.

We certify that a) the statements made in this report are correct b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI, and c) corrective measures taken conform to the rules of the ASME Code,Section XI.

Certificate of Authorization No. (if applicable) NA Expiration Date NA Date i>124/Zcc5 Signed Duke Energy Corp. By ___ __ l____

Owner CERlIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State of Province of NC . . employed by *The Hartford Steam Boiler Inspection & Insurance Company of Connecticut have inspected the components described in this Owners' Report during the period I ' 1 I- )° to 8 -2. Co S and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in the Ownersi Report in accordance with the Inspection Plan and as required by the ASME Code, Section XL..

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations, test, and corrective measures described in this Ownersi Report.

Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection

@Qcffi y 4 Commissions NC978 Inspect'oris Signature National Board, State, Province, and Endorsements Date 2;iS 20 OS

• The Hartford Steam Boiler Inspection & Insurance Company of Connecticut 200 Ashford Center North '

Suite 205 Atlanta, GA. 30338

August 16,2005

Subject:

Catawba Nuclear Station, Unit 1 Steam Generator Tube Inspection Report End of Core (EOC) 15 The following provides the quantity of tubes inspected and tubes removed by from service by plugging.

Steam Tubes Inspected Tubes Removed Generator Full Length (Bobbin) by Plugging A 3761 0 B 3775 0 C 3740 0 D 3758 0 In addition to the full length analysis of the bobbin data; some portions of the tubes were evaluated using array data to better detect or characterize indications. Following is a summary of the array probe evaluations.

Steam Tubes Inspected Examination Generator with Array Probe Extent A 809 Periphery tubes from tube end to J." support (hot leg) 809 Periphery tubes from tube sheet to 1 st support (cold leg) 25 Special Interest locations identified by bobbin B 814 Periphery tubes from tube end to I" support (hot leg) 814 Periphery tubes from tube sheet to 1St support (cold leg) 929 Hot Leg Tubesheet sample

• -* (TEH to TSH +2")

52 Special Interest locations identified by bobbin.

.9? ..

C 803 Periphery tubes from tube end to 1It support (hot leg) 803 Periphery tubes from tube sheet to 15' support (cold leg) 920 Hot Leg Tubesheet sample (TEH to TSH +2")

44 Special Interest locations identified by bobbin.

D 812 Periphery tubes from tube end to 1st support (hot leg) 812 Periphery tubes from tube sheet to ['t support (cold leg) 22 Special Interest locations identified by bobbin.

Attachments 1, 2, 3, and 4 identify tube imperfections in steam generators A, B, C, and D respectively. The location and size of the imperfections are also provided.

Table 1 lists all the eddy current codes and figure 1 represents the tubesheet row and column configuration. Figure 2 is provides the support structure profile for location orientation.

A 773:3

Table 1 Characterization Codes

1. CODE DESCRIPTION I ADI Absolute Drift Indication 2

• AXI Axial Indication 3 BLG Bulge 4 BOR Boron 5 CHT Chatter 7 DNT Dent 8 DWI Dent With Indication 9 FC Final Calibration 10 FCL Final Calibration Late 11 ICR Incomplete Roll 12 IC Initial Calibration 13 IV Independent Verification of tube identification 14

• IDOK Tube ID Verified; This code shall be used to identify tubes acquired more than once during the current outage. Use of this code requires tube to tube comparison or fingerprinting of the affected tube(s).

15 INF Indication Not Found 16 INR Indication Not Reportable 17 IRR Irregular Roll 18

• L3R Level III Review 19 MSG Analyst Message 20 NEX No Expansion 21 NFC No Final Calibration 22 NQI Non-Quantifiable Indication 23 NSR Needs SGME Review 24 OBS Obstructed 25 OVR Over Roll 26 OXP Over Expansion 27 PID Positive Identification 28

• PLG Plugged Tube 29 PLP Possible Loose Parts 30 PVN Permeability Variation 31 RBD Retest - Bad Data 32 RFB . Retest - Fan Bar using a wear standard for sizing 33 RIC Retest-- Incomplete 34 RNC Retest - Tube Number Check 35 ROB Retest - Obstructed 36 RRC Retest - Rotating Coil 37 RPD Retest - Positive Identification 38 SAT Satisfactory 39 SLG Sludge 40 SKR Skip Roll 41

• WAR Wear 42 WTG Wetting/Leaking

• Denotes code to be used in the "UTIL 1" field Page I of 2

Table 1 Three Letter Characterization Codes CODE DESCRIPTION 1

• AXI Axial Indication 2 DNT Dent 3

• L3R Level III Review 4 MAI Multiple Axial Indication 5 MCI Multiple Circumferential Indication 6 MMI Mixed-Mode Indication 7 MSG Analyst Message 8 MVI Multiple Volumetric Indications 9 NDF No Defect Found 10 OBS Obstructed 11 PID Positive Identification 12 PLP Possible Loose Part 13 PVN Permeability Variation 14 RBD Retest - Bad Data 15 RIC Retest - Incomplete 16 RNC Retest - Tube Number Check 17 ROB Retest - Obstructed 18 SAI Single Axial Indication 19 SCI Single Circumferential Indication 20 SVI Single Volumetric Indication 21 VOL Volumetric 22

• WAR Wear

• Denotes code to be used in the "UTIL 1" field.

Page 2 of 2

/Z'6?

V; 3

1a I so GO st 90 loa Ito st in 1ic t4 ItNWAY NOZZLE Figure 1

Figure 2 CFR 80 Steam Generator EFIi -. F.B.5F15 CFR 80 Tube Information:

l CBH CBC No. of Tubes 6633 Material: Inconel 690 09H 09C Nominal Dia: 0.688" Nominal Wall: 0.040" Row 1 Radius: 3.973" 08H 08C Straight Length: 31.9'/32.7' Tube Pitch: .930" 07H 07C Tube Support Information Type: Lattice 06H 06C Material 410 Stainless Thickness:

High: 3.150" 05H 05C Med.: 2.562" Low: 1.000" Connector Bar 04H 04C Material: 410 Stainless 03H 03C Fan Bars Material: 410 Stainless Thickness 0.110" Width . 1.25" . -

02H 02C 01H 01C NOTE: Dimensions are to the TSH TSC centerline of the tube support structures.

TEH TEC

iFramatome ANP Inc. 05/21/05 11:13:39 Customer Name: Catawba - Unit One Replacement Component: S/G A Page 1 of 3 Query Name : bobbin query.qry Query

Title:

Current bobbin non retest codes Selected Outages/Scopes:.05/05 - EOC15 BOBBIN EXAM Input Selected  : All Tubes Output File Selected :

Selected Indications : ADI,CHT,DNT,DPS,DWI,HNI,,ICR,IRR,NEX,NQI,NQS,ODI,OVR,OXP, PLP, PVN,SKR,TWD, Selected Probes  : ALL Selected Channels  : ALL Selected Cals  : ALL Selected Extentl  : ALL Selected Extent2  : ALL Selected Util 1 Selected Util 2 Selected Tube Heat TWD Range Volts Range Degrees Range Radius from Center Range Location Range  :

Inspection Leg Queried : BOTH Include In-Service or Out-Service Tubes : Both Advanced User Query :

ti rk,#vr I

.> "11714 // 4

/ P~9 -5'

Frdmatome ANP Inc. 05/21/05 11:13:39 Customer Name: Catawba - Unit One Replacement Component: S/G A Page 2 of 3 Current bobbin non retest codes QUERY: bobbin query ROW COL VOLTS DEG CHN IND ITW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 1,_ 0-22 80

___ __+__3,_--___________,.

6 A-- 09C TEC ____ ------- ,____________

1 40 0.22 80 6 ADI 04C +32.64 09C TEC 4 COLD 540UL 4 35 1.00 60 6 HNI 08H +26.49 09C TEA 103 HOT 54OUL

__________. .______________TE_________

5 14 0.85 62 6 ADI 08H 4+34.85 09C TEH 105 HOT 54OUL

.______ ____ __ _4__ __ _ __ _

9 26 0.29 83 6 ADI 04C 4+23.87 09C TEC 4 COLD 54OUL

.__________. _ ____0 ___ _ _

9 52 0.22 75 6 ADI 08C ++32.50 09C TEC 4 COLD

.__________. _ EC TE__ ___A _ _ _ __ _ _ __ . H__ ___ -_

14 81 0.26 79 6 HNI 03C . +25.46 TEC TEH 68 HOT 54OUL

.__________. ____E__________TEA________ .___OT____ _ _ ___O__ _ __L 15 64 0.21 156 1 HNI 07H - 15.35 TEC TEH 54 HOT 54OUL

_____. T_______C______TEA________ .HOT_ _ _ 54________UL___

540UL 17 32 0.21 163 1 HNI 04H 4-21.72 TEC TEH 38 HOT 54OUL T_______C______T__________ .___O_____ 54___________L_

20 91 0.15 153 1 ANI 02H . -7.13 TEC TEH 68 HOT 54OUL

,_______C______TEA________ HOT_______ ____________L__

540UL 22 53 0.47 80 6 HNI 02C +-3.48 TEC TEH 52 HOT 540UL' 0.24 70 6 ADI 03C +-14.22 TEC TEH 52 HOT

_____. 60 .___OT____

S40UL 27 10 0.42 171 1 HNI 03H ++3.57 TEC TEH 42 HOT 540UL

_______. _____. __________ 38 27 124 0.33 71 6 ADI 06C ++19.27 TEC TEH 40 HOT 540UL 28_____. ____________ ______ __________________________ ______. ._________ _______________

52 28 11 0.13 150 1 HNI 01H +26.59 TEC TEH 52 HOT 540UL 40 28 13 0.09 163 I HNI 04H ++23.21 SEC TEH HOT 540UL

____________ >- - z .- - -- -- - - -- __________________________

29 36 3.27 180 1 DNT TSH ++2.53 TEC TEH 38 540UL l---.

HOT 30 51 0.53 71 6 ADI FB3 ++4.62 TEC SEH 52 HOT 540UL 0.26 69 6 HNI 03H ++36.67 SEC SEH 52 32 49 0.21 70 6 HNI 02H +27.39 TEC TEH 52 HOT 54OUL 0.57 84 6 HNI 02H +19.30 TEC TEH 52 HOT 540UL 33 10 0.24 164 1 HNI 04C +25.10 TEC TEH 40 HOT 540UL 33_____24_____0.61_________8___6____A___!______________7____96_______EC____TE_______38_____HOT________________

33 24 0.61 78 6 ADI 06C +7.96 TEC TEH 38 HOT 540UL 33 36 0.62 80 6 ADI 07C +24.86 TEC TEH 38 HOT 540UL 34 55 0.41 74 6 HNI O1H +20.37 TEC TEH 52 HOT 540UL 35 52 0.43 85 6 HNI 01H +30.94 TEC TEH 52 HOT 54OUL 37 36 2.64 182 P1 DNT! FB3 +0.42 TEC TEH 38 HOT 540UL 37 50 0.54 80 6 HNI TS8 +12.02 TEC TEH 54 HOT 540UL 37 58 0.36 85 6 ADI 01H +30.43 TEC TEH 50 HOT 540UL 37 60 0.27 75 6 HNI 06H +25.50 TEC TEH 50 HOT 540UL 39 28 0.59 172 1 NI 09H +8.42 TEC TEH 36 HOT 540UL 40 53 0.64 85 6 HNI 06C +21.34 TEC TEH 52 HOT 540UL 93 46 2.31 183 1 DNT CBH +12.95 TEC TEH 52 HOT 540UL 43 104 2.47 181 1 DNT 07C +30.02 TEC TEH 64 HOT 540UL 49 66 0.29 79 6 HNI 01C +20.68 TEC TEH 48 HOT 540UL 49 82 0.17 82 P2 TWD 6 FB2 +1.35 SEC TEH WAR 70 HOT 540UL S1 78 0.21 122 PI HNI 01H -1.65 TEC TEH 68 HOT 540UL

52. SS 0.16 .161 1 - HNI 02H +8.37 TEC TEH. 48 HOT 540UL 0.26 163 1 HNI 02H +6.63 TEC TEH 48 NOT 540UL 57 38 0.15 48 P2 TWD S FB3 41.09 TEC TEH WlAR .50 HOT 540UL 59 122 1.28 71 6 HNI TSH +6.19 TEC TEH 60 HOT 540UL

, -: 0 S3 -- 8r! _.

,Framatome ANP Inc. 05/21/05 11:13:39 Customer Name: Catawba - Unit One Replacement Component: S/G A Page 3 of 3 Current bobbin non retest codes QUERY: bobbin query.qry ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 61 70 0.30 75 P2 TWD 13 FB4 +0.62 TEC TER WAR 48 HOT 540UL 63 50 0.22 162 1 HNI 04C +35.09 TEC TER 52 HOT 540UL 73 106 2.18 178 1 DNT 01H +20.15 TEC TER 6 HOT 540UL 75 50 0.32 161 1 RNI 05H +9.85 TEC TEH 30 HOT 540UL 75 70 3.56 183 1 DNT FB1 -2.79 TEC TEH 16 HOT 540UL 77 82 0.29 99 P2 TWD 9 FB5 -0.68 TEC TEH WAR 12 HOT 54OUL 77 90 0.26 99 P2 TWD 10 FB5 -0.64 TEC TER WAR 10 HOT 54OUL 81 80 0.26 107 P2 TWD 10 FB7 -0.67 TEC TER WAR 10 HOT 540UL 84 27 0.93 78 6 HNI FB4 +4.96 TEC TEH 32 HOT 54OUL 85 86 0.27 66 6 ADI 04H +26.13 TEC TEH 12 HOT 540UL 89 78 0.33 103 P2 TWD 12 FB5 -0.59 TEC TER WAR 10 HOT 540UL 89 80 -0.34 105 P2 TWD 13 FBS . -0.67 TEC TEH WAR 10 HOT 54OUL 91 80 0.31 116 P2 TWD 10 FB6 +1.72 TEC TER WAR 12 HOT 540UL 91 84 0.25 99 P2 TWD 9 FB4 -0.73 TEC TEH WAR 10 HOT 54OUL 92 79 0.35 92 P2 TWD 13 FB4 -0.53 TEC TER WAR 10 HOT 54OUL 94 81 0.21 111 P2 TWD 8 FBS +1.73 TEC TER WAR 10 HOT 54OUL 95 74 0.30 69 6 ADI 03H +17.24 TEC TER 16 HOT 54OUL 95 88 0.25 119 P2 TWD 8 FB4 -0.68 TEC TEH WAR 12 HOT 540UL 0.33 58 6 ADI 02H +6.31 TEC TER CHG 12 HOT 540UL 96 47 0.70 82 6 HNI 02H +16.53 TEC TER 28 HOT 540UL 96 109 0.20 101 P2 TWD 7 FBS +1.26 TEC TER WAR 58 HOT 540UL 99 46 0.20 72 6 HNI 08C +20.96 TEC TEH 28 HOT 540UL 99 72 3.12 182 P 1 DNT FB6 -0.31 TEC TER 16 HOT 540UL 101 78 0.35 123 P2 TWD 13 FB4 -1.67 TEC TEH WAR 10 HOT 540UL 103 78 0.31 0 P2 TWD 10 FB5 -0.56 TEC TER WAR 12 HOT 540UL

--- - - - - -- - = -- ------- = ------ - - -- - -- -- -- ---- =-- -- =--- ------------- - ------ -  : - - -- -- -- -----

105 38 0.32 79 6 HNI 02H +21.82 - TEC TEH 34 HOT - 540UL 114 75 0.38 69 6 HNI 05H +35.37 TEC TER 14 HOT 54OUL Total Tubes  : 62 Total Records: 67 I ,/ 9-3

Framatome ANP Inc. 05/21/05 11:13:51 Customer Name: Catawba - Unit One Replacement Component: S/G A Page 1 of 2 Query Name : array query.qry Query

Title:

Current array codes Selected Outages/Scopes: 05/05 - EOC15 TTS Array Exam 05/05 - EOC15 Special Interest Input Selected  : All Tubes Output File Selected :

Selected Indications : DNT,MAI,MCI,MMI,MVI,NQI,,ODIPLP,PVN,SAI,SCI,SVI,TWD,VOL, Selected Probes  : ALL Selected Channels  : ALL Selected Cals  : ALL Selected Extentl  : ALL Selected Extent2  : ALL Selected Util 1 Selected Util 2 Selected Tube Heat TWD Range Volts Range Degrees Range Radius from Center Range Location Range Inspection Leg Queried : BOTH Include In-Service or Out-Service Tubes : Both Advanced User Query :

/2 of 33

Framatome ANP Inc. 05/21/05 11:13:51 Customer Name: Catawba - Unit One Replacement Component: S/G A Page 2 of 2 Current array codes QUERY: array query ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 9 26 0.26 96 82 VOL 04C +22.36 05C 04C 3 COLD 540XP 39 28 1.01 86 130 VOL 09B +8.66 CBH 09H 35 HOT 540XP 37 ___

ROT ._ _ _ __ __

29 36 3.30 189 6 DNT TSH +2.57 01H TSH 37 HOT 540XP 37 36 1.87 188 42 DNT FB3 +0.42 FB3 FB3 37 HOT 540XP 1 40 0.43 116 86 VOL 04C +32.12 05C 04C 3 COLD 540XP

.__________. ________. ._ _ _ _ __ _ _ _ _ _ __1 HOT____ _ _ O__ ._ _ _ _ _ _ _ _

43 46 1.72 188 18 DNT CBH +12.83 FB3 CBH 51 HOT S40XP 30 51 1.16 24 10 VOL FB3 +5.42 FB4 FB3 51 HOT S40XP 37 58 0.31 87 78 VOL 01H +30.09 02H 01H 49 HOT 540XP 15 OT___ _______

99 72 1.72 12 138 DNT FB6 -0.31 FB6 FB6 15 HOT 540XP 95___74_ 0.23___. 102___VOL +17__.23 04____0_. ____________ _______

95 74 0.23 107 102 VOL 03H +-17.23 04H 03H 15 HOT 540XP 49 82 0.35 87 09 VOL FB2 +0.98 FB2 FB2 WAR 69 ROT 540XP 85 86 0.24 57 110 VOL 04HR- +25.97 04H 05H I 11 HOT 540XP 95 88 0.51 76 Q9 VOL FB4 +0.00 09C 09H WAR 11 HOT 540XP 43 104 3.57 188 90 DNT 07C +29.77 07C 08C 63 HOT 540XP Total Tubes  : 14 Total Records: 14

/ -,6 ,9

'Framatome ANP Inc. 05/21/05 11:14:04 Customer Name: Catawba - Unit One Replacement Component: SIG B Page 1 of 4 Component: S/G B Page 1 of 4 Query Name : bobbin query.qry Query

Title:

Current bobbin non retest codes Selected Outages/Scopes: 05/05 - EOC15 BOBBIN EXAM Input Selected  : All Tubes Output File Selected :

Selected Indications : ADI,CHT,DNT,DPS,DWI,HNI,,ICR,NEX,NQI,NOS,NSR,ODI,OVR,OXP,PLP,PVN,TWD, Selected Probes  : ALL Selected Channels . : ALL Selected Cals  : ALL Selected Extentl  : ALL Selected Extent2  : ALL Selected Util 1 Selected Util 2 Selected Tube Heat TWD Range Volts Range Degrees Range Radius from Center Range Location Range Inspection Leg Queried : BOTH Include In-Service or Out-Service Tubes : Both Advanced User Query :

Ar Av--r -

7 96*s.

i9, 7

/a 3

Framatome ANP Inc. 05/21/05 11:14:04 Customer Name: Catawba - Unit One Replacement Component: S/G B Page 2 of 4 Current bobbin non retest codes QUERY: bobbin query ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE 1 54 1.75 52 1 OVR TSC +0.32 09C TEC 10 COLD 540UL 12 103 0.41 81 6 HNI TSH +3.73 09C TEH 69 HOT 540UL 13 28 0.41 82 6 HNI 02C +28.06 TEC TEH 40 HOT S40UL 13 38 0.37 168 1 NQI 01C +25.07 TEC TEH 34 HOT 54oUL 16 39 0.42 167 1 HNI 01C +18.57 TEC TEH 36 HOT 540UL 17 10 0.58 82 6 ADI 01C +3.14 TEC TEH 40 HOT 540UL 17 22 0.35 83 6 ADI O1C +6.27 TEC TEH 40 HOT 54OUL 19 72 0.95 63 6 HNI CBH +6.79 TEC TEH 62 HOT 54OUL 20 33 0.37 75 6 ADI 04C +14.33 TEC TEH 34 HOT 54OUL 22 25 0.23 75 6 ADI 03C +31.58 TEC TEH 36 HOT 54OUL 23 36 0.25 82 6 ADI 02H +6.73 TEC TEH 34 HOT 54OUL 25 24 0.21 70- 6 {HNI 07H +35.57 TEC TEH 38 HOT 54OUL 0.18 76 6 HNI 07H +23.76 TEC TEH 38 HOT 54OUL 25 106 0.31 80 6 ADI 02C +34.93 TEC TEH 20 HOT 540UL 28 13 0.27 80 6 ADI 02H +25.64 TEC TEH 38 HOT 540UL 28 141 0.08 172 1 NQI 04H +23.52 TEC TEH 66 HOT 540UL 33 54 0.24 82 6 HNI 03H +25.83 TEC TEH 34 HOT 540UL 33 140 0.44 82 6 ADI 02C +7.71 TEC TEH 66 HOT 540UL 34 13 0.25 72 6 ADI TSH +12.00 TEC TEH 40 HOT 540UL 35 136 7.18 182 P1 DNT FB6 +2.29 TEC TEH 58 HOT 540UL 37 24 0.33 162 1 HNI 03C +23.56 TEC TEH 38 HOT 540UL 39 40 0.20 82 6 ADI 01H +22.61 TEC TEH 34 HOT 54OUL 39 48 0.98 85 6 ADI O1C +20.56 TEC TEH 32 HOT 540UL 39 58 0.45 81 6 HNI 01H +20.31 TEC TEH 66 HOT 540UL 39 88 0.21 76 6 ADI 08C +8.79 YEC TEH 16 HOT 540UL 40 65 0.39 82 6 ADI 01H +20.09 TEC TEH 66 HOT 54OUL 41 20 0.34 b2 6 ADI 04C +6.37 TEC TEH 40 HOT 540UL 41 58 0.26 83 6 ADI 01H +21.24 TEC TEH 68 HOT 540UL 41 60 0.38 78 6 HNI 01H +14.09 TEC TEH 68 HOT 540UL 45 60 0.32 80 6 ADI 06C +24.01 TEC TEH 68 HOT 540UL 45 66 0.26 166 1 HNI 02H +21.88 TEC TEH 66 HOT 540UL 47 58 0.29 74 6 ADI 03C +33.47 TEC TEH 66 HOT 540UL 49 100 0.33 73 6 HNI 01H +25.17 TEC TEH 20 HOT 540UL 50 83 0.28 75 6 ADI 05C +9.88 TEC TEH IV 14 HOT 540UL 52 63 0.39 75 6 ADI 02C +15.69 TEC TEI 66 HOT 540UL 59 92 0.33 80 6 ADI 04C +27.19 TEC TEII 16 HOT 54OUL 60 11 0.24 79 6 ADI 04C +20.76 TEC TEH 38 HOT 540UL 61 96 0.35 71 6 HNI 02H +25.13 TEC TEH 18 HOT 54OUL 63 60 0.12 118 P1 HNI 02C +0.22 TEC TEH 66 HOT 54OUL

, _ .I 4 :g 41 7

.Framatome ANP Inc. 05/21/05 11:14:04 Customer Name: Catawba - Unit One Replacement Component: S/G B Page 3 of 4 Current bobbin non retest codes QUERY: bobbinquery.qry ROW COL VOLTS DEG CHN IND ITW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE

---

--- a-----------

--- --- --- --- ---- ------- ------ e---- -------- -------------

64 35 0.26 71 6 ADI 01H +24.01 TEC TEH 34 HOT 540UL 66 73 0.31 96 P2 TWD 10 FB5 +0.63 TEC TEH WAR 10 HOT 540UL 69 70 0.44 94 P2 TWD 14 FB4 +1.38 TEC TEH WAR 30 HOT 540UL 69 72 0.29 79 6 ADI 07C +27.21 TEC TEH 30 HOT 540UL 69 104 0.23 159 1 NOI 08H +3.69 TEC TEH 14 HOT 540UL 0.21 81 6 HNI 03H +28.52 TEC TEH 14 HOT 540UL 74 83 0.36 116 P2 TWD 11 FB4 +1.26 TEC TEH WAR 62 HOT 540UL 77 106 0.41 81 6 ADI 07C +16.46 TEC TEH 14 HOT 540UL 79 24 0.14 148 1 HNI FB1 +10.83 TEC TEH 42 HOT 540UL 79 96 0.67 168 8 PLP TSH +0.68 TEC TEH 60 HOT 540UL 80 105 0.62 110 6 HNI 07H +35.62 TEC TEH 14 HOT 540UL 0.16 166 1 HNI 08H +3.93 TEC TEH IV 14 HOT 540UL 82 67 0.17 166 1 NO! 05H +10.21 TEC TEH 32 HOT 54OUL 82 _ _ 75_ _ 0. 33_ _ _ 99__ P2__ T WD__10 _ _ _ _B _ _ - 1 .10 _ _ _ T E_CTE_ EWA _ R_5_ _ _ _ _8_HO

_ _T_ _ _ _ - _40-82 75 0.33 99 P2 TWD 10 FB4 -1.10 TEC TEH WAR 62 HOT 540UL 82 83 0.37 81 P2 TWD 11 FB4 +1.16 TEC TEH WAR 62 HOT 54OUL

_______________0.39_____85___P2____TWD____12_____B_____+1.29_____TEC_____TEE______A__.___62___HOT_____________

84 115 0.80 48 7 PLP TSH +3.50 TEC TEH 46 HOT 540UL 85 98 0.29 82 6 HNI 01H +15.57 TEC TEH 10 HOT 54OUL 86 83 0.43 87 P2 TWD 13 FB5 -1.04 TEC TEH WAR 62 HOT 540UL 0.39 85 P2 TWD 12 FB4 +1.29 TEC TEH WAR 62 HOT 540UL 86 115 0.45 51 7 PLP TSH +3.51 TEC TEH 48 HOT 540UL 87 36 1.33 59 6 HNI TSH +3.77 TEC TEH 42 HOT 540UL 87 64 0.75 66 6 ADI 02C +7.00 TEC TEH 32 HOT 540UL 89 60 0.29 86 P2 TWD 10 FB6 -1.23 TEC TEH WAR 28 HOT 540UL 91 70 0.28 74 P2 TWD 10 FB6 +1.37 TEC TEH WAR 32 HOT 540UL 94 95 0.29 169 1 NLI 06H +7.87 TEC TEH 10 HOT 540UL 95 64 0.24 123 P2 TWD 9 FB5 -1.13 TEC TEH WAR 32 HOT 540UL 0.36 77 6 HNI 02H +19.43 TEC TEH 32 HOT 540UL 97 70 0.18 106 P2 TWD 6 FB8 +1.98 TEC TEH WAR 30 HOT 540UL 0.39 102 P2 TWD 12 FB6 -1.18 TEC TEH WAR 30 HOT 540UL 0.61 100 P2 TWD 18 FB5 -1.28 TEC TEH WAR 30 HOT 540UL 98 83 0.57 85 P2 TWD 17 FB5 +1.04 TEC TEH WAR 62 HOT 540UL

_________70____0.33______82_____6___________________+4.63________T___C___TE_________2___ROT_______4___________

99 100 1.31 154 8 PLP TSH +0.69 TEC TEH 14 HOT 540UL 100 99 0.64 149 8 PLP TSH +0.77 TEC TEH 14 HOT 540UL 102 39 0.73 84 6 HNI 01H +19.01 TEC TEH 22 HOT 540UL 103 70 0.28 83 P2 TWD 10 FB4 -1.01 TEC TEH WAR 32 HOT 540UL 103 78 0.40 78 6 HN1 05H +37.49 TEC TEH 60 HOT 540UL 105 104 0.57 47 7 PLP TSH +13.24 TEC TEH LAR 14 HOT 540UL 106 103 0.13 157 1 NQI TSH +6.93 TEC TEH 14 HOT 540UL 0.28 79 6 ADI O1C +29.88 TEC TEH IV 14 HOT 540UL 0.50 55 7 PLP TSH +13.37 TEC TEH 14 HOT 540UL 107 88 0.25 85 6 HNT 03H +8.82 TEC TEH 8 HOT 540UL 111 70 0.33 82 6 ADT 05H +4.63 TEC TEH 32 HOT 540UL

• - - -2 _, a /,Z 7

Ftamatome ANP Inc. 05/21/05 11:14:04 Customer Name: Catawba - Unit One Replacement Component: S/G B Page 4 of 4 Current bobbin non retest codes QUERY: bobbin query.qry ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG PROBE 119 74 2.57 179 1 DNT TSC +2.18 TEC TEH 60 HOT 54OUL 119________4.32___183___1_____T________+__.41. ._____________________TEC______TE______64_______OT_______________

119 80 4.32 183 1 DNT FB 4 +6.41 TEC TEN 64 NOT 540UL Total Tubes  : 74 Total Records: 83

/ '? 5 3 c7 4 o,- 7

Framatome ANP Inc. 05/21/05 11:14:18 Customer Name: Catawba - Unit One Replacement Component: S/G B Page 1 of 3 Query Name : array query.qry Query

Title:

Current array codes Selected Outages/Scopes: 05/05 - EOC15 TTS Array Exam 05/05 - EOC15 Special Interest 05/05 - EOC15 SSI PLP bounding Input Selected  : All Tubes Output File Selected  :

Selected Indications  : DNT,MAI,MCIMMI,MVI,NQI ,ODI,PLP,PVN,SAI,SCI,SVI,TWD,VOL, Selected Probes  : ALL Selected Channels  : ALL Selected Cals  : ALL Selected Extentl  : ALL Selected Extent2  : ALL Selected Util 1 Selected Util 2 Selected Tube Heat TWD Range Volts Range Degrees Range Radius from Center Range Location Range Inspection Leg Queried : BOTH Include In-Service or Out-Service Tubes : Both Advanced User Query :

35 al/7

t ramatome ANP Inc . 05/21/05 11:*14:18 Customer Name: Catawba - Unit One Replacement Component: S/G B Page 2 of 3 Current array codes QUERY: array query ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG PROBE 17 10 0.45 101 86 VOL 01C +3.12 01C 02C 39 HOT 540XP 17 22 0.29 102 38 VOL 01C +6.00 01C 02C 39 HOT 540XP 22 25 0.27 97 114 VOL 03C +31.73 03C 04C 35 HOT S40XP 20 33 0.38 80 18 VOL 04C +14.51 04C 05C 33 HOT 540XP 13 38 0.56 107 94 VOL 01C +25.04 01C 02C 33 HOT 540XP 70 45 5.92 87 12 PLP TSH +0.51 TSH TEH LAR 21 HOT 540XP 39 48 0.34 116 46 VOL 01C +20.94 01C 02C 31 HOT 540XP 45 60 0.44 107 26 VOL 06C +24.42 06C 07C 67 HOT 540XP 82 67 0.35 86 162 VOL 05H +10.43 06H 05H 31 HOT 540XP 69 70 0.49 51 04 VOL FB4 +1.38 FB4 FB4 WAR 29 HOT 540XP 91 70 0.42 74 Ql1 VOL FB6 +1.76 FB6 FB6 WAR 31 HOT 540XP 97 *70 0.55 96 Ql0 VOL - FB6 -1.18 FB6 FB6 WAR 29 HOT 540XP 0.30 103 Q4 VOL FB8 +1.91 FB8 FB8 WAR 29 HOT 54OXP 0.75 87 0l1 VOL FBS -1.28 FB5 FBS WAR 29 HOT 540XP 103 70 1.31 62 102 VOL FB4 -1.40 FB4 FB4 WAR 31 HOT 540XP 111 70 0.35 102 102 VOL 05H +5.47 06H OSH 31 HOT S40XP 0.20 113 114 VOL 05H +4.33 06H 05H 31 HOT S40XP 69 72 0.22 91 30 VOL 07C +27.09 07C 08C 29 HOT S40XP 119 74 2.87 175 22 DNT TSC +1.90 TSC 01C 59 HOT 540XP 82 75 0.43 58 03 VOL FB4 -1.35 FB4 FB4 WAR 57 HOT 540XP 119 80 4.39 177 62 DNT FB4 +6.22 FBS FB4 63 HOT 540XP 74 83 0.76 88 P19 VOL FB4 +1.65 FB4 FB4 WAR 61 HOT 540XP 82 83 0.43 67 010 VOL FB4 +0.63 FB4 FB4 WAR 61 HOT 540XP 86 83 0.57 109 010 VOL FB4 +0.71 F84 FB4 WAR 61 HOT 540XP 0.48 68 010 VOL FBS +1.15 FBS FB5 WAR 61 HOT 540XP 98 83 0.61 59 Q10 VOL FB5 +1.18 FBS FBS WAR , 61 HOT 540XP, 48 85 13.09 99 132 PLP TSH +0.50 TSH.TEH LAR . 1S HOT S40XP 6,1 88 11.40 106 140 PLP TSH +0.35 TSH TEH LAR 15 HOT - '540XP 63 88 12.84 96 104 PLP TSH +0.13 01H TEH LAR 15 HOT 540XP 44 95 6.64 100 164 PLP TSH +0.20 TSH TEH LAR 17 HOT 540XP 46 95 3.08 68 144 PLP TSH +0.35 01H TEH LAR 19 HOT 540XP 80 95 6.09 109 60 PLP TSH +0.74 TSH TEH LAR 9 HOT 540XP 86 95 5.10 87 168 PLP TSH +0.40 TSH TEH LAR 9 HOT S40XP 94 95 0.57 109 94 VOL 06H +7.93 07H 06H 9 HOT S40XP 79 96 9.56 128 96 PLP TSH +0.77 01H TEH LAR 59 HOT S40XP 87 96 8.52 109 132 PLP TSH +0.45 01H TEH LAR 57 HOT 540XP 111 96 3.51 84 164 PLP TSH +0.23 01H TEH LAR 9 HOT 540XP 112 97 6.82 108 128 PLP TSH +0.42 01H TEH LAR 9 HOT 540XP 109 98 14.39 107 140 PLP TSH +0.44 011 TEH LAR 9 HOT 540XP 100 99 10.38 104 56 PLP TSH +0.79 01H TEH LAR 13 HOT 540XP

/ j or 3 A 7

x ' kramatome ANP Inc. 05/21/05 11:14: 1E Customer Name: Catawba - Unit One Replacement Component: S/G B Page 3 of 3 Current array codes QUERY: array query.qry ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG PROBE 110 99 18.79 110 8 PLP TSH +0.47 01H TEH LAR 13 HOT 540XP 99 ____100 _____11.52______114_____72___PLP_____________+0.8_______T_______TE_____L___R___13___HOT______________

99 100 11.52 114 72 PLP TSH +0.88 TSH TEH

______________________________________________________________________________________________________________ LAR 13 HOT 540XP 101 100 11.69 104 80 PLP TSH +0.42 TSH TEH

_______________________________________________________________________________________________-_____-________ LAR 13 HOT 540XP 105 102 9.85 123 144 PLP TSH +0.54 O1H TEH LAR 13 HOT 540XP 107 102 8.98 123 104 PLP TSH +0.52 O1H TEH LAR

______________________________________________________________________________________________________________ 13 HOT 540XP 106 103 10.89 126 32 PLP TSH +13.54 01H TEH LAR 13 HOT 540XP 0.20 95 30 VOL TSH +7.17 01H TSH 13 HOT 540XP 69 104 0.51 105 114 VOL 08H +3.81 09H 08H 13 HOT 540XP 105 104 12.04 116 44 PLP TSH +13.61 01H TEH LAR 13 HOT 540XP 10.93 121 44 PLP TSH +13.58 01H TSH 13 HOT 540XP 25 106 0.48 82 30 VOL 02C +34.31 02C 03C 19 HOT 540XP 84 115 15.34 117 108 PLP TSH +3.79 01H TEH LAR 45 HOT 540XP 86 115 12.42 116 104 PLP TSH +6.78, TSH TEH LAR . 47 HOT 540XP 15 128 9.82 101 108 PLP TSH +0.21 TSH TEH LAR 53 HOT 540XP 33 140 0.39 77 46 VOL 02C +7.94 02C 03C 65 HOT 540XP 28 141 0.29 101 46 VOL 04H +23.36 05H 04H 65 HOT 540XP Total Tubes  : 50 Total Records: 56 7c97

Framatome ANP Inc. 05/21/05 11:14:42 Customer Name: Catawba - Unit One Replacement Component: S/G C Page 1 of 4 Query Name  : bobbin query.qry Query

Title:

Current bobbin non retest codes Selected Outages/Scopes: 05/05 - EOCi5 BOBBIN EXAM Input Selected  : All Tubes Output File Selected :

Selected Indications :ADI,CHT,DNT, DPS, DWI,HNI, ICRNEX, NQI,NQS,ODI,OXP, PLP, PVN,TWD, Selected Probes  : ALL Selected Channels :ALL Selected Cals :ALL Selected Extentl :ALL Selected Extent2 :ALL Selected Util 1 Selected Util 2 Selected Tube Heat TWD Range Volts Range Degrees Range Radius from Center Range Location Range Inspection Leg Queried : BOTH Include In-Service or Out-Service Tubes : Both Advanced User Query A rr,4chA L /-5 -3 7 ,%z ff

.2/ fetf / >I 7

. Framatome ANP Inc. 05/21/05 11:*14:42 Customer Name: Catawba - Unit One Replacement Component: S/G C Page 2 of 4 Current bobbin non retest codes QUERY: bobbin query ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG PROBE

___ 70- ------ --- _.__.____.________,

1 N--- --- TS +.39 .316 TC4.... COLD =----=

1 70 0.33 164 1 NOI TSC +1.53 09C TEC 4 COLD 540UL 2 67 0.24 157 1 HNI TSC +1.39 09C TEC 4 COLD 540UL 3 66 0.09 156 1 NOI TSC +1.93 09C TEC 2 COLD 54OUL

-- -- -- - - - - h--- -------------- e 5 54 2.68 12 1 HN2 TSH +0.87 09C TER 85 HOT 540UL z----

-- -- -- - - - - - -- -- -- -- -- -- -- -- - .- -- -- -- -- - 54____UL ___

5 132 0.90 85 6 HNI 05C +27.07 09C TEC 6 COLD 54OUL b-- -- z

-- -- -- -- -- - l---- -- ------ ------ b- - - - -

7 50 2.77 183 P1 DNT 09H -0.49 09C TEH 85 HOT COLD 54OUL TEC TE___ _______________

19 34 0.15 164 1 HNI 02H +29. 64 TEC TEN 26 HOT 540UL 21 66 0.35 170 1 HNI 09H -2.99 TEC TER 82 HOT 540UL 23 4 0.60 185 8 PLP TSH +1.34 TEC TEH 82 HOT 540UL 24 5 0.32 69 7 PLP TSH +1.44 01H TEH 62 HOT 540UL 0.27 50 7 PLP TSH +0.76 TEC TEN LAR 30 HOT 540UL 25 4 0.33 192 8 PLP TSH +0.50 TEC TEN 30 HOT 540UL 27 10 6.01 10 1 NQI TSC +0.92 TEC TEN 32 HOT 540UL 29_____10_____3.17_____________1____N_______T__________0__________TEC______TEN______30_____HOT________________

29 10 3.17 11 1 HNI TSC +0.95 TEC TEN 30 HOT 540UL 31 10 3.53 11 1 NOI TSC +0.95 SEC TER 32 HOT 540UL 34 85 1.11 53 6 HNI 08C +10.92 TEC TEN 80 HOT 540UL 43 10 0.80 178 8 PLP TSH +1.88 TEC TER 32 HOT 54OUL 0.53 188 8 PLP TSR +0.73 TEC TEN 32 HOT 540UL 43 138 2.23 177 1 DNT 03H +11.52 TEC TEN 70 HOT 540UL 44 11 0.92 175 8 PLP TSH +1.75 TEC TEN 30 HOT 54OUL 46 7 0.12 158 1 NQI TSH +9.35 TEC TEN 30 HOT 540UL 46 9 1.03 62 6 HNI 01C +28.78 TEC TEN 30 HOT 54OUL 52 95 0.54 86 6 ADI 02C +31.45 TEC TEN 72 HOT 54OUL 54 19 0.70 87 6 HNI 02H +23.35 TEC TEN 26 HOT 54OUL 59 122 0.18 75 6 ADI 02H +4.84 TEC TEH 58 HOT . 54OUL 63 44 0.17 99 P2 TWD 5 FB4 -1.72 TEC TEN WAR 30, HOT 540UL 67 88 1.11 82 6 .jNI 07C +24.41 TEC TEN 6 , HOT 540Ur 0.38 162 1 HNI 07C +29.45 TEC TEN 6 HOT 540UL 0.42 164 1 HNI 07C +24.70 TEC TEN 6 HOT 540UL 70 55 0.30 72 P2 TWD 9 FB5 -1.19 TEC TEN WAR 14 HOT 54OUL 72 23 0.24 82 6 H1I 01C +15.54 TEC TEN 24 HOT 540UL 72 61 0.45 0 P2 TWD 12 FB5 +1.59 TEC TEN WAR 10 HOT 540UL 73 62 0.17 0 P2 TWD 6 FB6 -0.69 TEC TEN WAR 12 HOT 540UL 74 65 0.20 0 P2 TWD 5 FB6 -1.94 TEC TEN WAR 10 HOT 540UL 0.23 0 P2 TWD 6 FB5 +1.54 TEC TEN WAR 10 HOT 540UL 0.18 0 P2 TWD 5 FB4 +0.62 TEC TEN WAR 10 HOT 540UL 74 87 0.44 0 P2 TWD 12 FB4 -1.77 TEC TEN WAR 6 HOT 540UL 75 60 0.50 82 P2 TWD 14 FB4 -1.13 TEC TEN WAR 14 HOT 54OUL 0.27 107 P2 TWD 8 FB6 -0.70 TEC TEN WAR 14 HOT 54OUL 75 62 0.61 P2 TWD 15 FB4 -0.67 TEC TEH WAR 10 HOT 540UL 75 76 0.60 P2 TWD 16 FB5 +1.24 TEC TEN WAR 6 HOT 540UL 76 59 0.23 0 P2 TWD 8 FB6 -1.76 TEC TEN WAR 16 HOT 540UL Z2Zz'93 9 2iV 7

Framatome F ANP Inc. 05/21/05 11:14:42 Customer Name: Catawba - Unit One Replacement Component: S/G C Page 3 of 4 Current bobbin non retest codes QUERY: bobbin query.qry ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG PROBE 76 61 0.51 P2 TWO 13 FB5 +1.59 TEC TEH WAR 10 HOT 540UL 77 68 0.23 0 P2 TWD 6 FB6 -0.59 TEC TEH WAR 10 HOT 54OUL 79 34 0.45 85 6 HNI 02H +26.96 TEC TEH 22 HOT 540UL 79 60 0.28 103 P2 TWD 8 FB4 -0.89 TEC TEH WAR 14 HOT 540UL 79 62 0.31 0 P2 TWD 6 FB5 +0.68 TEC TEH WAR 10 HOT 540UL 0.71 0 P2 TWD 17 FB4 -1.24 TEC TEH WAR 10 HOT 54OUL 79 66 0.16 0 P2 TWD 4 FB8 +0.81 TEC TEH WAR 10 HOT 540UL 79 80 0.18 0 P2 TWD 6 FB4 +0.63 TEC TEH WAR 8 HOT 540UL 79 86 0.26 0 P2 TWD 9 FB6 -0.49 TEC TEH WAR 8 HOT 540UL 0.34 0 P2 TWD 11 FB5 -0.87 TEC TEH WAR 8 HOT 540UL 80 59 0.25 0 P2 TWD 9 FB5 +1.71 TEC TEH WAR 16 HOT 540UL 80 81 0.39 0 P2 TWD 11 FB4 -1.11 TEC TEH WAR 6 HOT 540UL 83 76 1.02 P2 TWD 23 FBS -0.60 TEC TEH WAR 6 HOT 540UL 85___62__0.20__0__P2__TWO__7_______-0.69_________TEC_______TE________WAR_______12______HOT___________________

85 62 0.20 0 P2 TWD 7 FBS -0.69 TEC TEH WAR 12 HOT 540UL 85 64 0.31 0 P2 TWD 8 FBS -0.65 TEC TEH WAR 10 HOT 54OUL 85 76 0.91 0 P2 TWD 25 FB5 -0.67 TEC TEH WAR 8 HOT 540UL 86 59 0.28 78 P2 TWD 8 FB4 +1.73 TEC TEH WAR 14 HOT 54OUL 86 61 0.52 0 P2 TWO 13 FBS +0.59 TEC TEH WAR 10 HOT 540UL 0.27 0 P2 TWD 7 FB4 -0.67 TEC TEH WAR 10 HOT 540UL 86 77 0.34 0 P2 TWD 11 FB8 +0.69 TEC TEH WAR 8 HOT 540UL 90 87 0.51 0 P2 TWD 14 FB5 +1.66 TEC TEH WAR 6 HOT 540UL 90 115 0.34 89 6 HNI 02H +13.81 TEC TEH 40 HOT 54OUL 91 40 1.00 10 P HNI 02C +4.65 TEC TEH 18 HOT 540UL 91 62 0.42 0 P2 TWD 11 FB5 +0.62 TEC TEH WAR 10 HOT 540UL 0.38 0 P2 TWD 10 FB5 -0.67 TEC TEH WAR 10 HOT 540UL 0.24 0 P2 TWD 6 FB4 +0.59 TEC TEH WAR 6 HOT 54OUL

___ __ __ ___0.17_0 P2 _____TWO_____5_____________1_____5___TEC______TEH_____WAR_____6___HOT _______________

92 87 0.42 0 P2 TWD 14 FB5 -1.617 TEC TEH WAR 8 HOT 540UL 94 63 0.25 0 P2 TWD 7 FB6 -1.70 TEC'TEH WAR 10 HOT 540UL 96 87 0.38 0 P2 TWD 11 FBS +1.63 TEC TEH WAR 6 HOT 540UL 0.28 0 P2 TWD 8 FB4 +1.61 TEC TEH WAR 6 HOT 54OUL 97 86 0.31 0 P2 TWD 9 FB6 -0.63 TEC TEH WAR 6 HOT 540UL 98 77 0.62 0 P2 TWD 19 FB5 -1.12 TEC TEH WAR 8 HOT 540UL 98 85 0.22 0 P2 TWD 6 FB5 -1.76 TEC TEH WAR 6 HOT 540UL 0.21 0 P2 TWD 6 FB4 +1.87 TEC TEH WAR 6 HOT 540UL 0.17 0 P2 TWD S FB3 +1.85 TEC TEH WAR 6 HOT 540UL 98 87 0.35 0 P2 TWD 12 FB6 -1.61 TEC TEH WAR 8 HOT 54OUL 0.34 0 P2 TWD 11 FB5 -1.53 TEC TEH WAR 8 HOT 540UL 99 68 0.15 0 P2 TWD S FB7 -0.64 TEC TEH WAR 12 HOT 540UL 100 49 0.62 14 1 HN1 TSH +0.85 TEC TEH 14 HOT 540UL 0.40 77 6 ADI 04H +8.04 TEC TEH 14 HOT 540UL 100 87 0.46 0 P2 TWD 13 FB4 +1.66 TEC TEH h'AR 6 HOT 540UL 101 78 0.51 P2 TWD 14 FB5 -1.68 TEC TEII WAR 6 HOT 540UL 0.49 P2 TWD 13 FB4 +1.66 TEC TEII h'AR 6 HOT 540UL 0.42 P2 TWD 12 FB4 -0.71 TEC TEII WAR ,6 HOT 540UL

. f Framatome ANP Inc. 05/21/05 11:14:42 Customer Name: Catawba - Unit One Replacement Component: S/G C Page 4 of 4 Current bobbin non retest codes QUERY: bobbinquery.qry ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL 4 LEG PROBE

__- --- ------ --- --- _e

--- --- ------------- e_______ .... ...-------_._ ------ _._____

0.42 P2 TWD 12 FB4 -1.68 TEC TEH WAR 6 HOT S40UL 102 77 0.51 0 P2 TWD 16 FB7 -1.04 TEC TEH WAR 8 HOT 540UL 0.52 0 P2 TWD 16 FB5 -1.15 TEC TEH WAR 8 HOT 540UL 0.75 0 P2 TWD 22 F84 -1.15 TEC TEH WAR 8 HOT 540UL 0.39 0 P2 TWD 13 FB3 +0.98 TEC TEH WAR 8 HOT 54OUL 102__8___0__30_0__P2___W___10______---_1.64_________TEC_______TEN_______WAR_______8____H_____________________

102 83 0.30 0 P2 TWD 10 FB5 -1.64 TEC TEH

______________________________________________________________________________________________________________ WAR 8 HOT 540UL 102 87 0.45 0 P2 TWD 14 FB5 -1.67 TEC TEH

______________________________________________________________________________________________________________ WAR 6 HOT 540UL 104 37 0.85 194 8 PLP TSH +0469 TEC TEH 24 HOT 540UL 104 75 0.20 0 P2 TWD 6 FB4 -0.65 TEC TEH WAR 6 HOT 540UL 105 38 0.64 188 8 PLP TSH +1.04 TEC TEH

______________________________________________________________________________________________________________ 20 HOT 540UL 106 69 0.39 P2 TWD P 0 F86 +1.73 TEC TEH

______________________________________________________________________________________________________________ WAR 10 HOT 540UL 109 62 0.14 0 P2 TWD 5 FB4 -0.83 TEC TEH

______________________________________________________________________________________________________________ WAR 12 HOT 540UL 110 99 0.96 151 8 PLP TSH +3.78 TEC TEH 4 HOT 540UL 111 98 0.62 90 7 PLP TSH +4.35 01H TEH 62 HOT 540UL 0.56 90 7 PLP TSH +3.46 TEC TEH 4

______________________________________________________________________________________________________________ HOT 540UL 113 70 0.20 83 6 HNI 02H -3.52 TEC TEH 10 HOT 540UL 118______73_____0.10______1____7___8___P____P___TSH______45.24________TE______TEN______4___HOT________________

116 73 0.67 86 6 ADI 03C +26.94 TEC TEH 2 HOT 540UL 117 62 0.44 79 6 HNI 05C +13.74 TEC TEH 12 NOT 540UL 117 66 0.55 93 6 HNI TSC +17.99 TEC TEH 10 HOT 540UL 118 73 ,0.10 117 8 PLP TSH 45.24 TEC TEH 4 HOT 540UL Total Tubes  : 82 Total Records: 106

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I I Ftamatome ANP Inc. 05/21/05 11:14:59 Customer Name: Catawba - Unit One Replacement Component: S/G C Page 1 of 3 Query Name : array query.qry Query

Title:

Current array codes Selected Outages/Scopes: 05/05 - EOC15 TTS Array Exam 05/05 - EOC15 Special Interest Input Selected  : All Tubes Output File Selected :

Selected Indications : DNT,MAI,MCI,MMI,MVI,NQI ,ODI,PLP,PVN,SAI,SCI,SVI,TWD,VOL, Selected Probes :ALL Selected Channels  : ALL Selected Cals  : ALL Selected Extentl  : ALL Selected Extent2  : ALL Selected Util 1 Selected Util 2 Selected Tube Heat TWD Range Volts Range Degrees Range Radius from Center Range Location Range Inspection Leg Queried : BOTH Include In-Service or Out-Service Tubes : Both Advanced User Query :

!~ ; - 7

-9 I _ a 2 3

I v -Framatome ANP Inc. 05/21/05 11:14:59 Customer Name: Catawba - Unit One Replacement Component: S/G C Page 2 of 3 Current array codes QUERY: array query ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL A LEG PROBE 24 3 4.75 99 84 PLP TSH +0.19 01H TEH 61 HOT 540XP 3.58 72 164 PLP TSH +0.06 01H TEH LAR 29 HOT 540XP 23 4 10.22 130 144 PLP TSH +0.89 01H TEH LAR 81 HOT 540XP 25 4 10.06 124 24 PLP TSH +1.72 01H TEH 61 HOT 540XP 5.30 121 152 PLP TSH +1.27 01H TEH 61 HOT 540XP 5.46 113 128 PLP TSH +0.65 01H TEH LAR 29 HOT 540XP 24 5 8.55 120 144 PLP TSH +1.54 01H TEH 61 HOT 540XP 6.63 118 156 PLP TSH +1.02 01H TEH LAR 29 HOT 540XP 7.35 126 156 PLP TSH +0.47 01H TEH LAR 29 HOT 540XP 46 7 0.24 112 126 VOL TSH +9.07 01H TEH 29 HOT 540XP 43 10 7.02 113 164 PLP TSH +1.84 01H TEH 61 HOT 540XP 3.90 83 56 PLP TSH +0.16 01H TEH 61 HOT 540XP 5.68 121 104 PLP TSH +1.91 TSH TEH LAR 31 HOT 540XP 7.96 117 68 PLP TSH +0.75 TSH TEH LAR 31 HOT 540XP 42 11 11.10 124 84 PLP TSH +0.75 01H TEH LAR 31 HOT 540XP 44 11 .21.70..131 48 PLP TSH +1.72 01H TEH LAR 29 HOT. ,. 540XP 102 37 4.58 108 144 PLP TSH +0.40 01H TEH 61 HOT 540XP 4.62 113 156 PLP TSH +0.43 01H TEH LAR 51 HOT 540XP 104 37 16.30 125 168 PLP TSH +0.37 01H TEH 61 HOT 540XP 12.08 126 44 PLP TSH +0.40 01H TEH LAR 23 HOT 540XP 103 38 4.70 124 128 PLP TSH +0.37 01H TEH 61 HOT 540XP 5.70 116 72 PLP TSH +0.58 01H TEH LAR 17 HOT 540XP 105 38 10.70 123 152 PLP TSH +0.88 01H TEH 61 HOT 540XP 9.63 119 36 PLP TSH +0.92 01H TEH LAR 19 HOT 540XP 100 49 0.34 95 10 VOL 04H +8.08 05H 04H 13 HOT 540XP 80 59 0.55 89 05 VOL FB5 +1.86 FBS FB5 WAR 15 HOT 540XP 75___60__0.43__75____14__VOL_______-1.08_____________________________WAR_______13______NOT___________________

75 60 0.43 75 Q14 VOL FB4 -1.08 FB4 FB4 WAR 13 HOT 540XP 79 60 0.43 58 Q14 VOL FB4 -1.10 FB4 FB4 WAR 13 HOT 540XP 85___62__0.26___54__05__VOL________-0.78______________________B5_____WAR_______________NOT___________________

75 62 0.56 51 Q14 VOL FB4 -0.94 FB4 FB4 WAR 9 HOT 540XP 85 62 0.26 54 95 VOL FB5 -0.78 FB5 FB5 WAR 11 HOT 540XP 91 62 0.51 43 Q8 VOL FB4 +0.92 FB4 FB4 WAR 9 HOT 540XP 109 62. 0.28 76 98 VOL FB4 -0.75 FBi1FB4 WAR 1r' HOT 540XP-74 65 0.34 97 214 VOL FB5 +1.54 FB5 FB5 WAR 9 HOT 540XP 0.61 44 Q14 VOL FB4 +0.43 FB4 FB4 WAR 9 HOT 540XP 3 66 0.25 103 18 VOL TSC +1.95 01C TSC 1 COLD 540XP 2 67 0.43 97 22 VOL TSC +1.72 01C TSC 3 COLD 540XP 77 68 0.44 76 Q14 VOL FB6 -0.84 FB6 FB6 WAR 9 HOT 540XP 1 70 0.28 73 18 VOL TSC +1.44 01C TSC 3 COLD 540XP 49 70 18.21 103 156 PLP TSH +0.24 TSH TEH LAR 71 HOT 540XP 118 73 2.26 125 120 PLP TSH +6.10 O1H TEH LAR 3 HOT 540XP 2.40 124 164 PLP TSH +5.73 01H TEH 61 HOT 540XP 104 75 0.22 86 013 VOL FB4 -1.33 FB4 FB4 WAR 5 HOT 540XP 98 77 0.88 61 Q4 VOL FB5 -0.86 F85 FB5 WAR 7 HOT 540XP 102 77 1.07 76 Q5 VOL FB7 -0.69 FB7 FB7 WAR 7 HOT S40XP 0.53 109 05 VOL FBS -0.74 FB5 FB5 WAR 7 HOT 540XP 1.19 74 Q5 VOL FB4 -1.09 FB4 FB4 WAR 7 HOT 540XP 0.55 84 Qll VOL FB3 +0.63 FB3 FB3 WAR 7 HOT 540XP

- v z% 6 of 7

• Framatome ANP Inc. 05/21/05 11:14:59 Customer Name: Catawba - Unit One Replacement Component: S/G C Page 3 of 3 Current array codes QUERY: array query.qry ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL # LEG PROBE

--- ------ --- --- __=- --- ------- =- - - -- - - - --- --- _--- -- -- - -- --- -__ -_ -- _ -- _-- ____---

98 85 0.44 61 06 VOL FB4 +1.41 FB4 FB4 WAR 5 HOT 540XP 0.57 97 Q13 VOL FB5 -1.25 FB5 FB5 WAR 5 HOT 540XP 0.32 54 Q6 VOL FB3 +1.30 FB3 FB3 WAR 5 HOT 540XP 79 86 0.45 71 Q12 VOL FB6 -1.16 FB6 FB6 WAR 7 HOT 540XP 0.59 79 012 VOL FB5 -1.19 FB5 FB5 WAR 7 HOT 540XP 97 86 0.41 33 Q6 VOL FB6 -0.88 FB6 FB6 WAR 5 HOT 540XP 96 87 0.38 54 06 VOL FB4 +1.42 FB4 FB4 WAR 5 HOT 540XP 0.49 64 Q6 VOL FB5 +1.69 FB5 FB5 WAR 5 HOT 540XP 52 95 0.45 87 78 VOL 02C +30.76 02C 03C 71 HOT 540XP 111 98 11.42 132 96 PLP TSH +4.55 01H TEH 61 HOT 540XP 12.34 130 68 PLP TSH +4.82 01H TEH LAR 3 HOT 540XP 110 99 7.37 122 84 PLP TSn 44.47 01H TEH 61 HOT 540XP 7.92 117 84 PLP TSH +5.12 01H TEH LAR 3 HOT 540XP Total Tubes : 37 Total Records: 60 77 w ; -

Framatome ANP Inc. 05/21/05 11:15:32 Customer Name: Catawba - Unit One Replacement Component: S/G D Page 1 of 4 Query Name : bobbin query.qry Query

Title:

Current bobbin non retest codes Selected outages/Scopes: 05/05 - EOC15 BOBBIN EXAM Input Selected  : All Tubes Output File Selected :

Selected Indications : ADI,CHT,DNT,DPS,DWI,HNI,,,ICR,NEX,NQI,NQS,NSR,OBS,ODI,OVR,OXP, PLP, PVN,TWD, Selected Probes  : ALL Selected Channels :ALL Selected Cals  : ALL Selected Extentl  : ALL Selected Extent2  : ALL Selected Util 1 Selected Util 2 Selected Tube Heat TWD Range Volts Range Degrees Range Radius from Center Range Location Range Inspection Leg Queried : BOTH Include In-Service or Out-Service Tubes : Both Advanced User Query :

A , hectT- 4 6 I.,65

- r *Framatome ANP Inc. 05/21/05 11:15:32 Customer Name: Catawba - Unit One Replacement Component: S/G D Page 2 of 4 Current bobbin non retest codes QUERY: bobbinquery ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL V LEG PROBE 4 45 0.27 76 6 HNI 04H +21.16 09C TEH 95 HOT 540UL 4 133 10.84 182 1 DNT 09H +6.42 09C TEH 91 HOT 54OUL 5 96 0.31 78 6 ADI TSC +9.29 09C TEC 4 COLD 540UL 7 32 0.24 67 6 HNI 03H +36.37 09C TEH 95 HOT 540UL 7 112 0.63 83 6 HNI 08C +3.37 09C TEC 2 COLD 540UL 1.25 86 6 HNI 06C +34.37 09C TEC 2 COLD 540UL 0.24 163 1 HNI 04H +8.80 09C TEH 91 HOT 540UL 8 83 5.64 183 1 DNT CBC +10.70 09C TEH 95 HOT 540UL 11 108 0.43 167 1 HNI 08H +30.81 09C TEH 91 HOT 540UL 12 131 0.57 85 6 HNI 05H +33.37 09C TEH 91 HOT 540UL 15 46 0.78 59 6 HNI 09H +4.76 TEC TEH 66 HOT 54OUL 19 32 0.36 75 6 HNI 05H +24.79 TEC TEH 38 HOT 54OUL 21 74. 0.89 70 6 ADI CBH +9.23 TEC TEH 68 HOT 540UL 23 40 0.51 70 6 ADI 08C +7.57 TEC TEH 66 HOT 540UL 0.41 68 6 ADI 08H +18.65 TEC TEH 66 HOT 54OUL 28 9 0.42 172 1 HNI 09C +4.40 TEC TEH 30 HOT 540UL 29 82 0.36 73 6 ADI 02H +38.06 TEC TEH 56 HOT 540UL 32 65 0.05 53 1 HNI TSH +13.35 TEC TEH 70 HOT 540UL 32 139 0.21 158 1 HNI 06H +21.72 TEC TEH 44 HOT 54OUL 35 104 2.40 9 1 NQI 04H +5.90 TEC TEH 62 HOT 540UL 37 42 0.31 76 6 HNI 02C +6.38 TEC TEH 68 HOT 540UL 37 104 1.38 11 1 NOI 04H +6.85 TEC TEH 64 HOT 540UL 52__79__0.36__103__P2_TW___12______-0.84_________T____C____TE________WAR_______56______HOT___________________

52 79 0.36 103 P2 TWD 12 FB5 -0.84 TEC TEH WAR 56 HOT 540UL TWD 12 FB4 -0.90 TEC TEH WAR 62 HOT 540UL 52 91 0.31 120 P2 53 76 0.69 74 P2 TWD 21 FB4 +1.66 TEC TEH WAR 56 HOT 54OUL 53 116 0.28 82 6 ADI TSC +10.52 TEC TEH 52 HOT 540UL 56 83 17.62 180 P1 DNT 09C +1.53 TEC TEH 54 HOT 54OUL 57 46 2.12 178 P1 DNT 08C +1.52 TEC TEH 68 HOT 54OUL 57 66 0.67 P2 TWD 20 FB5 -1.23 TEC TEH WAR 72 HOT 540UL 62 53 0.08 144 1 HNI FB4 +6.50 TEC TEH 70 HOT 540UL 62 95 0.08 83 P2 TWD 4 FB4 -0.93 TEC TEH WAR 62 HOT 540UL 65 72 0.89 81 6 HNI 08C +3.43 TEC TEH 18 HOT 540UL 66 85 0.37 104 P2 TWD 14 FB4 +1.50 TEC TEH WAR 10 HOT 540UL 67 74 0.37 84 P2 TWD 13 FB5 +0.51 TEC TEH WAR 8 HOT 540UL 69 74 0.32 0 P2 TWD 13 FB5 +0.71 TEC TEH WAR 6 HOT 540UL 71 66 0.23 100 P2 TWD 8 FB5 +1.49 TEC TEH WAR 20 HOT 540UL 75 42 0.28 73 6 HNI 07H +22.37 TEC TEH 28 HOT 540UL 77 66 0.13 P2 TWD 6 FB5 +1.09 TEC TEH WAR 78 HOT 54OUL 79 66 0.29 109 P2 TWD 10 FB5 +1.58 TEC TEH WAR 20 HOT 54OUL 80 45 0.64 84 6 HNI TSC +3.59 TEC TEH 26 HOT 540UL

.912 - -7 oi.

14 6

. T N~ramatome ANP Inc. 05/21/05 11:15:32 Customer Name: Catawba - Unit One Replacement Component: S/G D Page 3 of 4 Current bobbin non retest codes QUERY: bobbin query.qry ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG PROBE 80 73 0.59 0 P2 TWD 22 FB5 +1.67 TEC TER WAR 6 HOT 540UL 0.39 0 P2 TWD 16 FB4 +1.36 TEC TER WAR 6 HOT 540UL 80 95 0.33 77 6 HNI 05H +33.89 TEC TER 14 HOT 54OUL 0.15 92 6 HNI OSH +32.53 TEC TEN 14 HOT 540UL B1 68 0.44 P2 TWD 16 FB6 -1.75 TEC TER WAR 78 HOT 540UL 0.38 P2 TWD 15 FB4 +1.67 TEC TER WAR 78 HOT 540UL 85 84 0.33 87 P2 TWD 12 FB5 -1.13 TEC TEN WAR 12 HOT 540UL 86 73 0.74 0 P2 TWD 26 FB5 +1.62 TEC TEN WAR 6 HOT 540UL 0.60 0 P2 TWD 22 FB4 +1.45 TEC TEN WAR 6 HOT 540UL 0.57 0 P2 TWD 21 FB6 -1.70 TEC TEN WAR 6 HOT 54OUL 87 82 0.42 85 6 HNI 03C +17.43 TEC TEN 10 HOT 540UL 88 73 0.53 92 P2 TWD 17 FB5 +1.60 TEC TEN WAR 8 HOT 54OUL 88 77 0.89 65 6 HNI 08H +14.80 TEC TEN 6 HOT 54OUL 89 62 0.31 ' P2 TWD 12 FB5 -0.56 TEC TEN WAR 78 HOT 540UL 90 69 0.33 115 P2 TWD 12 FB4 +0.79 TEC TEN WAR 18 HOT 540UL 91 62 0.23 67 P2 TWD 9 FB5 -0.51 TEC TEH WAR 18 HOT 540UL 92 69 0.36 99 P2 TWD 12 FB4 +0.65 TEC TEN WAR 20 HOT 540UL 92 73 0.44 0 P2 TWD 16 FB5 +1.62 TEC TEN WAR 6 HOT 540UL 93 62 0.64 90 P2 TWD 20 FB5 -0.62 TEC TEN WAR 20 HOT 540UL 93 70 0.20 P2 TWD 8 FB6 -1.19 TEC TEN WAR 18 HOT 540UL 0.51 0 P2 TWD 18 FB5 -1.08 TEC TER WAR 18 HOT 540UL 95 62 0.20 117 P2 TWD 8 FB5 -0.68 TEC TEN WAR 18 HOT 540UL 95 68 0.43 97 P2 TWD 14 FB7 -0.73 TEC TEN WAR 20 HOT 54OUL 0.59 106 P2 TWD 18 FB5 -1.30 TEC TEN WAR 20 HOT 540UL 0.37 81 P2 TWD 12 FB3 -0.54 TEC TEN WAR 20 HOT 540UL 97 68 0.69 0 P2 TWD 23 FB5 -1.24 TEC TEN WAR 18 HOT 540UL 99 64 0.19 P2 TWD 9 FB5 +1.70 TEC TEN WAR 78 HOT 540UL 100 69 0.34 62 P2 TWD 13 FB6 +1.84 TEC TEN WAR 18 HOT 540UL 0.29 101 P2 TWD 11 FB5 +0.68 - TEC TEHN WAR 18 HOT - 540UL 101 80 0.38 92 P2 TWD 15 FB6 -0.99 - TEC TEN WAR- 10- -HOT 540UL 102 55 0.09 158 1 HNI 07H +34.38 TEC TEN 22 HOT 540UL 108 71 0.21 81 P2 TWD 8 FB5 +0.48 TEC TEN WAR 18 HOT 54OUL 108 73 0.27 0 P2 TWD 10 FB4 +1.45 TEC TEN WAR 6 HOT 540UL 110 65 0.24 107 P2 TWD 9 FB4 -1.66 TEC TEN WAR 18 IOT 540UL 0.37 0 P2 TWD 14 FB5 -1.21 TEC TEH WAR 18 HOT 540UL 113 64 0.24 109 P2 TWD 9 FB5 -1.63 TEC TEN WAR 18 HOT 540UL 114 53 0.55 84 6 ADI 02H +30.29 TEC TER 24 HOT 540UL 114 61 0.39 0 P2 TWD 15 FB4 -1.12 TEC TEH WAR 22 HOT 54OUL 114 69 0.23 102 P2 TWD 9 FB5 +0.71 TEC TEN WAR 18 HOT 540UL 0.21 136 P2 TWD 8 FB4 +1.47 TEC TEN WAR 18 HOT 540UL Total Tubes  : 66 Total Records: 80 3 ,z~

-' Tramatome ANP Inc. 05/21/05 11:15:32 Customer Name: Catawba - Unit One Replacement Component: S/G D Page 4 of 4 Current bobbin non retest codes QUERY: bobbinquery.qry ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG PROBE 4 a ll6

i' Tramatome ANP Inc. 05/21/05 11:15:43 Customer Name: Catawba - Unit One Replacement Component: S/G D Page 1 of 2 Query Name : array query.qry Query

Title:

Current array codes Selected Outages/Scopes: 05/05 - EOC15 PROXIMITY TUBES 05/05 - EOC15 TTS Array 05/05 - EOC15 Special Interest Input Selected  : All Tubes Output File Selected :

Selected Indications : DNTMAIHCIMMI,MVI,NQI,,ODI,PLP, PVN, SAI,SCI, SVI, TWD, VOL, Selected Probes  : ALL Selected Channels  : ALL Selected Cals  : ALL Selected Extentl  : ALL Selected Extent2  : ALL Selected Util 1 Selected Util 2 Selected Tube Heat TWD Range Volts Range Degrees Range Radius from Center Range Location Range Inspection Leg Queried : BOTH Include In-Service or Out-Service Tubes : Both Advanced User Query :

,,. *LFramatome ANP Inc. 05/21/05 11:15:43 Customer Name: Catawba - Unit One Replacement Component: S/G D Page 2 of 2 Current array codes QUERY: array query ROW COL VOLTS DEG CHN IND %TW LOCATION EXT EXT UTIL 1 UTIL 2 CAL I LEG PROBE 60 19 2.93 88 60 PLP TSH +0.28 TSH TEH LAR 33 HOT 540XP 59____20____17.26______114_____156____PL______TSH______0.22________S_____TE_____LA______33___HOT______________

59 20 17.26 114 156 PLP TSH +0.22 TSH TEH LAR 33 HOT 540XP 61 20 5.91 104 144 PLP TSH +0.57 TSH TEH LAR 35 HOT 540XP 99 34 1.61 109 150 TWD 24 TSC +0.00 TO+0.12 TSC 01C 0.32 0.12 25 HOT 540XP 1.98 84 150 VOL TSC +0.11 TSC 01C 25 HOT 540XP 114 53 0.40 85 90 VOL 02H +30.33 03H 02H 23 HOT 540XP 89 62 0.66 28 02 VOL FB5 -0.64 FB5 FB5 WAR 77 HOT 540XP 99 64 0.56 24 Q10 VOL FB5 +1.51 FB5 FB5 WAR 77 HOT 540XP 77 66 0.36 87 010 VOL FB5 +1.45 FB5 FB5 WAR 77 HOT 540XP 81 68 0.95 38. 03 VOL FB6 -1.39 FB6 FB6 WAR 77 HOT 540XP 0.40 58 Q10 VOL FB4 +1.14 FB4 FB4 WAR 77 HOT 540XP 8 83 3.53 191 154 DNT CBC +10.59 CBC CBH 115 HOT 540XP 56 83 23.68 182 Qll DNT 09C , +1.67 . 09C 09C 53 HOT 540XP 5 96 0.30 103 102 VOL TSC +9.06 01C TSC 3 COLD 540XP 4____133_____2.88_______175_____98_________T______________6___20____C________________87____HOT________________

4 133 2.88 175 98 DNT 09H +6.20 CBH 09H 87 HOT 540XP Total Tubes : 13 Total Records: 15 ev*0;9 :33