Text

J. M. Farley Unit 2, Inservice Inspection Report, Refueling 15, Interval 3, Period 1, Outage 1, Index - Well Examination Summary Sheet
	ML030300235
Person / Time
Site:	Farley
Issue date:	01/21/2003
From:	; Southern Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	NL-03-0167
	Download: ML030300235 (158)
	v • d • e

INSERVICE INSPECTION REPORT Date of Document Completion: January 17,2003 REFUELING 15 INTERVAL 3 PERIOD 1 OUTAGE 1 J. M. FARLEY UNIT 2 NUCLEAR GENERATING PLANT COLUMBIA, ALABAMA 36319 Commercial Service Date: July 30, 1981 Southern Nuclear Operating Company 40 Inverness Parkway Birmingham, Alabama 35242

INDEX SECTION TAB NIS-1 OWNERS REPORT A

SUMMARY

B EXAMINATION PROGRAM C

EXAMINATION RESULTS D

ADDITIONAL EXAMINATIONS E

INDICATIONS F

PERSONNEL, EQUIPMENT, MATERIAL, & CALIBRATION BLOCK CERTIFICATIONS G

EXAMINATION PROCEDURES H

REACTOR VESSEL INSPECTION TOOL DATA AND RESULTS I

NIS-2 FORM-OWNER'S REPORTS FOR REPAIRS AND REPLACEMENTS J

Page 1 of4 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules Southern Nuclear Operating Co. 40 Inverness Center Parkway,

1.

Owner Birmincham. Al 35242 (as agent for Alabama Power Co)

(Name and Address of Owner)

2.

Plant

3.

Plant Unit 2 J. M Farlev Nuclear Plant.

Hwv95 South. Columbia. Al. 36319 (Name and Address of Plant)

4. Owner Certificate of Authorization (if required)

5.

Commercial Service 07/30/81 N/A

6. National Board Number for Unit See Listed N. B.

for each component

7.

Components Inspected Note. Supplemental sheets in the form of lists, sketches, or drawings may be used, provided (1) size is 8 1/2 in. x II in, (2) information in items I through 6 on this 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 Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No.

Province No.

Board No.

Reactor Vessel Combustion CE 69105 N/A 21385 Engineering Reactor Vessel Combustion CE 69105 N/A 21385 Closure Head Engineering Reactor Vessel Westinghouse APR-RCRIUI N/A N/A Internals Pensacola Pressurizer Westinghouse 1561 N/A W10793 Tampa Steam Generator Westinghouse ALAD-40307 N/A 73 A

Pensacola Reactor Coolant Westinghouse APR-RCPPA-N/A N/A Pumps A & C EMD 01 & 03 Reactor Coolant Southwest N/A N/A N/A Piping Fabricating RHR Heat Joseph Oat &

2046-IA N/A 633 Exchanger A Sons, Inc.

RHR Pump A Ingersoll-Rand Co.

1170-18 N/A N/A Class 1 Piping Daniel N/A N/A N/A Construction Class 2 Piping Daniel N/A N/A N/A Construction 1

4 4

i i

J. M Farley Nuclear Plant Hwv95South Columbia Al 36319

Page 2 of 4 FORM NIS-1

8.

Examination Dates 09/14/02 to 10/28/02

9.

Inspection Period Identification: First Period 07/30/01 to 11/30104

10.

Inspection Interval Identification: Third Interval 07/30/01 to 07/30/11

11.

Applicable Edition of Section XI 1989 Addenda None

12.

Date/Revision of Inspection Plan:

FNP-2-M-097; 05/15/02; Revision 3

13.

Abstract of Examinations and Tests. Include a list of examinations and tests and a statement concerning status of work required for the Inspection Plan. See Tabs B, C and E

14.

Abstract of Results of Examinations and Tests. See Tab B

15.

Abstract of Corrective Measures. See Tab B 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, SectionXI, 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

_QneJ.

2Q 0 S Signed Southern Nuclear Operating Co. By_

(Owner)

Date _____7 20::)-3 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 &,,X!A and employed by Factory Mutual Insurance Company of Johnston, Rhode Island have inspected the components described in this Owner's Report during the period to,Z Z '"./

,and state that to the best of my knowledge and belief, the Owner has performed examinations and tests and taken corrective measures described in this Owner's 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, tests, and corrective measures described in this Owner's 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.

nset Commissions Boar t

i Inspecto ~i~gnature National Board, State, Province, and Endorsements

OWNER'S REPORT FOR INSERVICE INSPECTION 01/17/03 OWNER NAME AND ADDRESS:

NAME AND ADDRESS OF NUCLEAR GENERATING PLANT:

NAME ASSIGNED TO NUCLEAR POWER UNIT:

OWNER CERTIFICATE OF AUTHORIZATION:

COMMERCIAL SERVICE DATE:

NATIONAL BOARD NUMBER:

NAME OF COMPONENTS OR PARTS OF COMPONENTS INVOLVED:

Southern Nuclear Operating Co.

40 Inverness Parkway Birmingham, Al 35242 (as agent for Alabama Power Co.)

Joseph M. Farley Nuclear Plant Highway 95 South Columbia, Alabama 36319 Joseph M. Farley Nuclear Plant Unit 2 N/A July 30, 1981 See listed NBs for each component Representative samples of the following components and systems were examined using nondestructive examination techniques.

CLASS 1 DATE:

Page 3 of 4 COMPONENT OR SYSTEM SYSTEM APR SKETCH DESIGNATION Reactor Vessel BI1 1-1100, 1-1100B, 1-1200 Reactor Vessel Closure Head B11 1-1300, 1-1300A, 1-1300B, 1-1300C Pressurizer B31 1-2100A Steam Generator B21 1-3100 Reactor Coolant Pump B41 1-5100, 1-5100B, 1-5300 Reactor Coolant System B13 1-4100, 1-4501 RHR System Eli 1-4101 Safety Injection System E21 1-4102, 1-4302 CVCS System E21 1-4109

Page 4 of 4 CLASS 2 COMPONENT OR SYSTEM SYSTEM APR SKETCH DESIGNATION RHR Heat Exchanger El1 2-3500 RHR Pump Ell 2-5130 Main Steam System NIl 2-4100,2-4101 HYDROSTATIC TESTING:

SEE TABS B AND E NAME AND ADDRESS OF MANUFACTURER OR INSTALLER OF COMPONENTS:

REACTOR VESSEL AND REACTOR VESSEL REACTOR COOLANT PUMPS CLOSURE HEAD Westinghouse Electric Corporation Combustion Engineering, Inc.

Electro Mechanical Division Chattanooga, Tennessee Cheswick, Pennsylvania REACTOR VESSEL INTERNALS REACTOR COOLANT PIPING Westinghouse Electric Corporation Southwest Fabricating and Welding Co., Inc.

Pensacola, Florida Houston, Texas PRESSURIZER RHR HEAT EXCHANGER Westinghouse Electric Corporation Joseph Oat and Sons, Inc.

Tampa Division Camden, New Jersey Tampa, Florida STEAM GENERATOR RHR PUMP Westinghouse Electric Company Ingersoll-Rand Co.

Pensacola Plant No.5 Cameron Pump Division Pensacola, Florida Phillipsburg, New Jersey CLASS I & 2 PIPING Daniel Construction Co.

Greenville, South Carolina INSERVICE INSPECTION DATES:

09/14/02 TO NAME OF AUTHORIZED NUCLEAR INSPECTOR:

NAME AND MAILING ADDRESS OF INSPECTOR'S EMPLOYER:

ABSTRACT:

SEE TABS B AND C 10/28/02 Charles G. Ward Factory Mutual Insurance Company 1301 Atwood Ave.

P. 0. Box 7500 Johnston, RI. 02919

J. M. FARLEY NUCLEAR PLANT UNIT NO 2 INTERVAL 3 PERIOD 1 OUTAGE 1 BALANCE OF PLANT/REACTOR VESSEL EXAMINATION

SUMMARY

INTRODUCTION The Inservice examination of Class 1 and 2 components and piping systems was conducted at Farley Nuclear Plant Unit 2 from September, 2002 to October, 2002. The examinations were performed in accordance with an approved Examination Program Plan located under Tab C of this report.

The program utilized ultrasonic, visual, and surface nondestructive testing methods in accordance with the requirements of ASME Section Xl 1989 Edition and Technical Specifications 5.5.7, 5.5.8 and 5.5.16. The primary areas of examination included the Reactor Vessel, RCS piping, RHR/CVCS piping and supports and Main Steam piping and supports.

Selected examinations and related activities were witnessed by representatives of Southern Nuclear Operating Company and its Authorized Inspection Agency. All examinations were performed to the extent practical within geometric and physical limitations.

RESULTS Examinations resulted in recordable indication areas being noted on the basis of procedure recording criteria, which generally are more conservative than specified in the ASME Section XI Acceptance Standards. Indications were evaluated and dispositioned by Indication Evaluation Reports (IER), shown in Tab F of this report. The results are summarized below.

SUMMARY

OF INDICATIONS CLASS 1 (A)

VOLUMETRIC EXAMINATIONS There were no Class 1 Volumetric indications.

(B)

SURFACE EXAMINATIONS There were no Class 1 Surface indications.

(C)

VISUAL EXAMINATIONS There were thirty-two (32) bolted connections which had varying degrees of boron accumulation, which was removed and re-inspections performed satisfactorily.

There was one (1) Reactor Vessel Stud Washer which had a dent on its outer edge. A supplemental surface examination was performed and found acceptable.

CLASS 2 (A)

VOLUMETRIC EXAMINATIONS There were no Class 2 Volumetric indications.

(B)

SURFACE EXAMINATIONS There were no Class 2 Surface indications.

(C)

VISUAL EXAMINATIONS There were forty-four (44) bolted connections which had varying degrees of boron accumulation, which was removed and re-inspections performed satisfactorily.

There was one (1) spring can with indications of damage to the load indicator. This condition had been previously reported (RF12) and evaluated as acceptable.

AUGMENTED EXAMINATIONS Augmented surface examinations were performed on the C Reactor Coolant Pump Flywheel.

No indications were identified.

ADDITIONAL EXAMINATIONS Results from additional examinations which were performed during this outage are as follows:

Class 1 System Leakage Test In accordance with ASME Section XI 1989 Edition IWB-5221, leak testing of the Class I Reactor Coolant System Pressure Boundary was performed prior to startup following the fifteenth refueling outage. The VT-2 examinations were completed by plant personnel on 10/14/02. A copy of the completed test procedure FNP-2-SOP-1.4 is retained by the Farley Nuclear Plant Document Control. A copy of the VT-2 data sheets are located behind Tab 1.7.

Subsequent to the Class 1 leakage test, control rod problems developed when rod B-8 was not able to be completely inserted into the core during testing. The plant was returned to cold shutdown, the reactor head disassembled and the control rod assembly and associated drive shaft were replaced. The inability to insert the control rod was attributed to a foreign object, which damaged the control rod assembly. An extensive search by plant personnel was not able to locate the foreign object believed responsible. The control rod replacement delayed the end of the outage until 10/28/02. VT-2 examinations associated with equipment disassembled after the initial completion of procedure FNP-2-SOP-1.4 and the end of the outage were performed.

In addition, to meet the 1989 Section XI IWA-5242(a) requirement for removal of insulation from bolted connections in "systems borated for the purpose of controlling reactivity" the alternative exam requirements of Relief Request RR 27 were used. This Relief Request allowed the insulation to be removed and the bolted connection to be examined for evidence of leakage at static conditions. If evidence of leakage was apparent the bolting was either removed and examined per IWA-5250(2) or the provisions of Relief Request RR 23 were followed. This allowed an evaluation to be performed instead of removal and examination of the bolting.

2

Class 1 and 2 Hydrotesting No Class I or 2 hydrostatic testing was performed during the fifteenth refueling outage.

Class 2 Functional/Inservice Testing Functional/Inservice tests Class 2 systems were performed in accordance with the requirements of ASME Code Section XI, Articles IWA-5000 and IWC-5000. Systems examined included Main Steam and Feedwater, CTMT Spray, Boric Acid Transfer System, CVCS, Service Water and Component Cooling Water. A copy of the completed test report(s) is maintained in FNP Document Control.

STATUS OF EXAMINATIONS REQUIRED FOR CURRENT INTERVAL This refueling was the 1 outage, I' period of the current interval and the examinations completed to date represent approximately 40% of the total Class I and 2 scope for the current period. Approximately 15% of the examinations required for the current interval have been completed.

3

U2R15 ISI Report U2R15 was the first in-service inspection of the new replacement Model 54F steam generators which were replaced during U2R14. The inspection scope for all three SG's was:

0 100% full length bobbin (with exception of low row U-bends)

20% hot leg top of tubesheet plus point 100% low row U-bend plus point a Plus point of bobbin signals which were not observed during the Pre-Service Inspection (PSI) or which had changed since the PSI.

No indications of degradation were observed and the inspections were completed ahead of schedule.

Work was performed in accordance with NEI 97-06 Rev 1 and EPRI SG NDE Guidelines, Rev 5.

EXAMINATION PROGRAM PLAN UNIT 2 RF 15 INTERVAL 3 PERIOD 1 OUTAGE 1 2002

FNP-2-STP-157.0 1

UNIT 2 FIGURE 2 FARLEY NUCLEAR PLANT INSERVICE INSPECTION PROGRAM CHANGE Unit No.

2 10 Year Interval 3

Change No.

001 40 Month Period 1

Page 1

of Outage 1

BOP ISI Description of Change:

Component Number:

Delete examination:

APRI-1300-SOI APRI-1300-S14 APRI-1300-S15 APR1-1300-S24 APRI-1300-S25 APRI-1300-S27 APR1-1300-S28 APRI-1300-S29 APRI-1300-S30 "APRI-1300-S31 APRl-1300-S32 APRI-1300-S51 APRl-1300-S52 APRl-1300-S53 APRI-1300-S54 APRl-1300-S55 APRl-1300-S56 APRl-1300-S57 APRl-1300-S58 Reason for Change:

Method SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE SURFACE Component number:

Change Procedure APR2-3500-A FNP-0-NDE-100.31 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Surface examination deleted per RR-49 Reason for Change Component is a vessel less than 2". Code requirement is Appendix III,Section XI. The proper NDE procedure is FNP-0-NDE-100.31.

APPROVED BY:

P L

(IQ Vendor Coordinator APPROVED BY:

S-NC Crdinato Da-t 1 eV 2_

Date Date Revision 17

FNP-2-STP-157.0 UNIT 2 FIGURE 2 FARLEY NUCLEAR PLANT INSERVICE INSPECTION PROGRAM CHANGE Unit No.

2 10 Year Interval 3

Change No.

002 40 Month Period 1

Page 1

of 1

Outage 1

BOP ISI Description of Change:

Component Number:

Delete examination:

EG2-045-2AFW-R50 EG2-046-2AFW-R76 EG2-046-2AFW-R76 (ATT)

EG2-046-2AFW-R83 EG2-211-2SW-R88 (ATT)

EG2-21 1-SW-2A13 (ATT)

EG2-218-2SW-R568 (ATT)

EG2-22 1 -SW-2A09 (ATT)

EG2-255-2CCW-R245 EG2-481-AFW-2A6 EG2-481-AFW-2A6 (ATl')

EG2-496-2SW-R268 (ATT)

EG2-548-AS-2A4 (ATT) 24 - B-M-2 VALVE INTERNALS 3 - B-L-2 PUMP INTERNALS Component number:

UPFLOW MODIFICATION Reason for Change:

Method VT-3 VT-3 VT-i VT-3 VT-i VT-i VT-I VT-I VT-3 VT-3 VT-i VT-1 VT-i VT-3 VT-3 DEFER TO NEXT OUTAGE / CRAFT SUPPORT/ (TRENCH)

DEFER TO NEXT OUTAGE / CRAFT SUPPORT/ INSULATION SAMPLE DEFER TO NEXT OUTAGE / CRAFT SUPPORT/ INSULATION SAMPLE DEFER TO NEXT OUTAGE / CRAFT SUPPORT/ (TRENCH)

DEFER TO NEXT OUTAGE / CRAFT SUPPORT/ SCAFFOLD / INSUL.

DEFER TO NEXT OUTAGE / CRAFT SUPPORT/ SCAFFOLD DEFER TO NEXT OUTAGE / CRAFT SUPPORT/ SCAFFOLD / INSUL.

DEFER TO NEXT OUTAGE / CRAFT SUPPORT/ SCAFFOLD / INSUL.

DEFER TO NEXT OUTAGE CRAFT SUPPORT/ SCAFFOLD I INSUL.

VALVES NOT DISASSEMBLED PUMPS NOT DISASSEMBLIED Reason for Change VT-3 REACTOR VESSEL INTERNAL MODIFICATION PSI PERFORMED APPROVED BY:

APPROVED BY:

Vendor Ciordinator DaZte6L Date Date Revision 17

Page 1 of k.

J. M. FARLEY i,,jCLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage I C

.lP-2-M-097 (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Via NDE Procedures Remarks B-A APR1-1100-1 UPPER SHELL TO FLANGE ALA-RV.2, ALA-VOL FNP-ISI-54 RG 1.150 RR-17 RV-5 B1.30 Figure 001 B-G-1 APRI-1100-L04 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI.55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L05 RPV STUD HOLE ALA.RV-6 VOL FNP-ISI-55 B6 40 Figure 016 THREADS/LIGAMENTS B-G-1 APRI-1100-L06 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APRI-1100-L07 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6 40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L08 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/OGAMENTS B-G-1 APRI-1100-L09 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L28 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6 40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L29 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6 40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L30 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 86.40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L31 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L32 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L33 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-134 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6,40 Figure 016 THREADS/LIGAMENTS

Page 2of u J. M. FARLEY hLICLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage I (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Via NDE Procedures Remarks B-G-1 APR1-1100-L35 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6 40 Figure 016 THREADS/LIGAMENTS B-G-1 APRI-1100-L36 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L37 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6 40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L44 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L45 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L46 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LUGAMENTS B-G-1 APRI-1100-L47 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APRI-1100-1_48 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6 40 Figure 016 THREADS/LIGAMENTS B-Go1 APR1-1100-L49 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-150 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6 40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-L51 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6 40 Figure 016 THREADS/LIGAMENTS B-G-1 APR1-1100-1-52 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/UGAMENTS B-G-1 APR1-1100-L53 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-G-1 APRI-1100-L54 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/UGAMENTS B-G-1 APR1-1100-L55 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS

.t4P-2-M-097

Page 3 of 2u J. M. FARLEY r, CLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage 1 (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Via NDE Procedures Remarks B-G-1 APR1-1100-L56 RPV STUD HOLE ALA-RV-6 VOL FNP-ISI-55 B6.40 Figure 016 THREADS/LIGAMENTS B-N-1 APRI-1200-VS INT VESSEL INTERIOR VT-3 FNP-ISI-88 B13.10 Figure Accessib B-O APR1-1300-58 CRD HOUSING WELDS SUR FNP-0-NDE-100.5 10% of peripheral CRD housings B14.10 Figure 022 B-G-1 APRl-1300-NO1 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-1 APRI-1300-N14 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100 21 RR-13 B6.10 Figure B-G-1 APR1-1300-N15 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-1 APRI-1300-N24 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-1 APR1-1300-N25 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100 21 RR-13 B6.10 Figure B-G-1 APRI-1300-N27 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-1 APR1-1300-N28 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-1 APRl-1300-N29 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-1 APR1-1300-N30 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-10021 RR-13 86.10 Figure B-G-1 APR1-1300-N31 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100 21 RR-13 B6.10 Figure B-G-1 APR1-1300-N32 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-1 APR1-1300-N51 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100 21 RR-13 B6.10 Figure

(

NP-2-M-097

Page 4 of 21 J. M. FARLEY hu.CLEAR PLANT OUTAGE PLAN Interval 3 Period I Outage I (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Via NDE Procedures Remarks B-G-1 APR1-1300-N52 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-1 APR1-1300-N53 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-1 APR1-1300-N54 REACTOR VESSEL NUTS VT-I FNP-0-NDE-100 21 RR-13 B6.10 Figure B-G-1 APR1-1300-N55 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B.G-1 APR1-1300-N56 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100 21 RR-13 86.10 Figure B-G-1 APR1-1300-N57 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-1 APR1-1300-N58 REACTOR VESSEL NUTS VT-1 FNP-0-NDE-100.21 RR-13 B6.10 Figure B-G-2 APR1-1300-PEN 51 CRD HOUSING BOLTING VT-1 FNP-0-NDE-100 21 B7.80 Figure B-G-1 APRI-1300-S01 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016

-B-G-1

-APR1-1300-S01 REACTOR VESSEL STUDS ALA-36 SUR FNP-0-NDE-100.11..---

B6.30 Figure 016 1-G-1 APR1-1300-S14 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100 39 B6.30 Figure 016

-B-G-I-

-APR1-1300-S14.....

REACTOR VESSEL STUDS ALA-36 SUR-----.

FNP-0-NDE-100,11.

B630 Figure 016 B-G-1 APR1-1300-S15 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016

"-R -G-1.

-APR!- *~-°4 10S1; REAG TOR-VESSEL STUDS.

A SUR--

-FNP-O-DE-10M1 1-B6.30 Figure 016 B

-APR1z1300-S24 REACTOR VESSEL STUDS

- ALA-36.....

SUR ----

-FNP-0-NDE;100.11-.

B6.30 Figure 016 rCo

-v C,

0 d

0 AJIP-2-M-O97

Page 5 of2U J. M. FARLEY hJCLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage I (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Vie NDE Procedures Remarks B-G-1 APR1-1300-S24 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016

-B-G--

APR-1300-S25---

-REACTOR VESSEL STUDS ALA-36 SUR ----

FNP-0-NDE-1001 1 B6 30 Figure 016 B-G-1 APRI-1300-S25 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6 30 Figure 016

-B-G-1* -APR1-1300-S27 REACTOR VESSEL STUDS.....-

ALA SUR

-FNP-0-NDE-100.11-

,e,,e B6.30 Figure 016 B-G-1 APR1-1300-S27 REACTOR VESSEL STUDS ALA.36 VOL FNP-0-NDE-100.39 B6.30 Figure 016

-- B-G1-

-APF11-1300-S28 REACTOR VESSEL STUDS..

ALA UR

-FNP-O-NDE-100;11-B6 30 Figure 016 B-G-1 APR1-1300-S28 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6 30 Figure 016

-- B-G-1

,APR1-1300-S29 REACTOR VESSEL-STUDS-ALA-36 UR

-FNP-0-NDE-10O;1 1-B6.30 Figure 016 B-G-1 APR1-1300-S29 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016 0-G.-

-APRI4300-S30 REACTOR VESSEL-STUDS-A LA-36 SUR---- -FNP-0-NDE-100,1-1 B6.30 Figure 016 B-G-1 APRI-1300-S30 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100 39 B6 30 Figure 016

-- B-G -APRI-1300-tS31

-REACTOR VESSEL-&TUDS-ALA-6-.

UR--

-FNP-0-NDE-100I 1-t B6.30 Figure 016 B-G-1 APR1-1300-S31 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100 39 B6 30 Figure 016 B-G-1 APR1-1300-S32 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6 30 Figure 016

~--G1----- APR1-I¶00-S32 REACTOR VESSEL STUDS ALA-36 SUR FNP-0-NDE-100.11 et},4 B6.30 Figure 016

,NP-2-M-O97

Page 6 of 2u C

J. M. FARLEY iwuCLEAR PLANT OUTAGE PLAN Interval 3 Period I Outage I (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol VIa NDE Procedures Remarks Rl00-S51------

-- REACTOR VESSEL-STUDS----

ALA-36---

-SUR----

-FNP-0-NDE-1004.1-B6.30 Figure 016 B-G-1 APR1-1300-S51 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016 n-0-1

.A.PR.300-'-52 REACTORXVESSEL STUDS ALA SUR--- -FN.4)-NDE400,4-i-Ael, B6.30 Figure 016 B-G-1 APR1-1300-S52 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6 30 Figure 016

-8 G--.

A....

1.00 953 REAoTOR

,,ESE,,

STUDS Al.A I _-"6

-'SUR -.-

'-- 0'DE-10011 B6 30 Figure 016 B-G-1 APRI-1300-S53 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016

--6-i APR1-100 C64 AlECT EU,

,CTUDS ALA 6sP 0,N-DURI-P 904:1 B6.30 Figure 016 B-G-1 APR1-1300-S54 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016 B-G-1 APR1-1300-S55 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016

-B--

-APRt-153O-S55 REAOTOR-VESSEL-STUDS A----ALA-86 sUR

-FNP-O-NDE-100 e teJ B6.30 Figure 016 "B

C 1 APl4-18,0-656 REACGTOR-VESSEL'STUOS ALA 36 UR

-FNP O,DE-100-4 "e-e-44 B630 Figure 016 B-G-1 APR1-1300-S56 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016

-B-G-1

-- APRI-4300-857

-REAGTGR-VESSEL-STUELS-

-A 6UR--

-FNP--NDE-100-41 le B6.30 Figure 016 B-G-1 APRI-1300-S57 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016 R.t*,.1 AP_.,n300-S5-

-RfA.CTORVESSEL, TnUDS..

AL.3A.

26JR-S

-FNP-O-NDE-100-11 B630 Figure 016

.-NP-2-M-097

Page 7 of 2u J. M. FARLEY i=wCLEAR PLANT OUTAGE PLAN Interval 3 Period I Outage I (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Vie NDE Procedures Remarks B-G-1 APR1-1300-S58 REACTOR VESSEL STUDS ALA-36 VOL FNP-0-NDE-100.39 B6.30 Figure 016 B-G-1 APR1-1300-WOI REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100 21 B6.50 Figure B-G-1 APR1-1300-W14 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6 50 Figure B-G-1 APR1-1300-W15 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6.50 Figure B-G-1 APR1-1300-W24 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 86.50 Figure B-G-1 APRI-1300-W25 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6.50 Figure B-G-1 APR1-1300-W27 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6.50 Figure B-G-1 APR1-1300-W28 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6.50 Figure B-G-1 APRI-1300-W29 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6.50 Figure B-G-1 APRI-1300-W30 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100 21 86.50 Figure B-G-1 APR1-1300-W31 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6 50 Figure B-G-1 APR1-1300-W32 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6.50 Figure B-G-1 APR1-1300-W51 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6 50 Figure B-G-1 APR1-1300-W52 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100 21 B6.50 Figure B-G-1 APR1-1300-W53 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100 21 B6.50 Figure

NP-2-M-097

Page 8 of 20 J. M. FARLEY NUCLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage 1 (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Via NDE Procedures Remarks B-G-1 APR1-1300-W54 REACTOR VESSEL WASHERS VT-I FNP-0-NDE-100 21 B6 50 Figure B-G-1 APR1-1300-W55 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6 50 Figure B-G-1 APR1-1300-W56 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6.50 Figure B-G-1 APR1-1300-W57 REACTOR VESSEL WASHERS VT-i FNP-0-NDE-100 21 B6 50 Figure B-G-1 APR1-1300-W58 REACTOR VESSEL WASHERS VT-1 FNP-0-NDE-100.21 B6 50 Figure B-D APR1-2100-10 PRZ UPPER HD. TO NOZZLE WELD APR-7 SUR FNP-0-NDE-100.11 (SUPPLEMENTAL SURFACE EXAM)

B3.110 Figure 008 RR-6 B-D APR1-2100-10 PRZ UPPER HD. TO NOZZLE WELD APR-7 VOL FNP-0-NDE-100.34 (SUPPLEMENTAL SURFACE EXAM)

B3.110 Figure 008 RR-6 B-D APR1-2100-1OIR PRZ NOZ-INSIDE RADIUS ALA-38 VOL FNP-0-NDE-100.38 B3.120 Figure 008 B-D APR1-2100-9 PRZ UPPER HD. TO NOZZLE WELD APR-7 SUR FNP-0-NDE-100.11 (SUPPLEMENTAL SURFACE EXAM)

B3.110 Figure 008 RR-6 B-D APR1-2100-9 PRZ UPPER HD. TO NOZZLE WELD APR-7 VOL FNP-0-NDE-100.34 (SUPPLEMENTAL SURFACE EXAM)

B3.110 Figure 008 RR-6 B-D APR1-2100-91R PRZ NOZ-INSIDE RADIUS ALA-38 VOL FNP-0-NDE-100 38 B3.120 Figure 008 B-G-2 APRI-3100-NO1 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N02 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N03 STEAM GEN. NUTS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N04 STEAM GEN NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure

.-NP-2-M-097

Co Page 9 of 2u J. M. FARLEY IrUCLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage I rNP-2-M-097 (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Vie NDE Procedures Remarks B-G-2 APR1-3100-N05 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-N06 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N07 STEAM GEN. NUTS VT-i FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N08 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N09 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N10 STEAM GEN. NUTS VT-I FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N11 STEAM GEN. NUTS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N12 STEAM GEN. NUTS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N13 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N14 STEAM GEN. NUTS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N15 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-N16 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N17 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-N18 STEAM GEN NUTS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7 30 Figure B-G-2 APR1-3100-N19 STEAM GEN. NUTS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7 30 Figure

Page 10 of 2u J. M. FARLEY rh CLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage I NP-2-M-097 (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Vis NDE Procedures Remarks B-G-2 APR1-3100-N20 STEAM GEN. NUTS VT-I FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N21 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N22 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N23 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-N24 STEAM GEN. NUTS VT-i FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-N25 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N26 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N27 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N28 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-N29 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-N30 STEAM GEN. NUTS VT-i FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-N31 STEAM GEN. NUTS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-N32 STEAM GEN. NUTS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S01 STEAM GEN. STUDS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure AN1-1 -. tuu-bu2 Figure STEAM GEN. STUDS B7.30 V'T-I FNP-0-NDE-1 00 21 PSI DONE AT ENSA,

Page 11 of 2u J. M. FARLEY huCLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage 1 (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Via NDE Procedures Remarks B-G-2 APR1-3100-S03 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S04 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S05 STEAM GEN. STUDS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S06 STEAM GEN. STUDS VT-1 FNP-O-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S07 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S08 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S09 STEAM GEN. STUDS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S10 STEAM GEN. STUDS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-S11 STEAM GEN. STUDS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S12 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S13 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B730 Figure B-G-2 APR1-3100-S14 STEAM GEN. STUDS VT-I FNP-0-NDE-100 21 PSI DONE AT ENSA.

67.30 Figure B-G-2 APR1-3100-S15 STEAM GEN. STUDS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure APR1-3100-S16 Figure APR1-3100-S17 Figure STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

t Vi:

FNP-0-NDE-100 21 PSI DONE AT ENSA STEAM GEN STUDS

.-NP-2-M.097 B-G-2 B7 30 B-G-2 B7 30 SV T-1*

FNP-0-NDE-IO00 21 PSI DONE AT ENSA I

Page 12 of ku J. M. FARLEY NuCLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage I (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol VIe NDE Procedures Remarks B-G-2 APR1-3100-S18 STEAM GEN. STUDS VT-I FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S19 STEAM GEN. STUDS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S20 STEAM GEN. STUDS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S21 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-S22 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S23 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S24 STEAM GEN. STUDS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S25 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APRI-3100-S26 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S27 STEAM GEN. STUDS VT-1 FNP-0-NDE-100.21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S28 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S29 STEAM GEN. STUDS VT-i FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure B-G-2 APR1-3100-S30 STEAM GEN. STUDS VT-1 FNP-0-NDE-100 21 PSI DONE AT ENSA.

B7.30 Figure APR1-3100-S31 Figure APR1-3100-S32 Figure STEAM GEN. STUDS STEAM GEN STUDS VT-i VT-i FNP-0-NDE-100 21 FNP-0-NDE-100 21 PSI DONE AT ENSA PSI DONE AT ENSA,

) )

.i4P-2-M-097 B-G-2 B7 30 B-G-2 17 30

Page 13 of ku J. M. FARLEY NUCLEAR PLANT OUTAGE PLAN Interval 3 Period I Outage I (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Via NDE Procedures Remarks B-F APR1-4100-25RDM SAFE-END TO NOZZLE ALA-53 SUR FNP-0-NDE-100.5 ADDED PER STEAM GENERATOR B5.70 Figure 012 REPLACEMENT DURING 2R14. PSI DONE AT ENSA. RR-46 B-F APR1-4100-25RDM SAFE-END TO NOZZLE ALA-53 VOL FNP-0-NDE-1 00.31 ADDED PER STEAM GENERATOR B5.70 Figure 012 REPLACEMENT DURING 2R14. PSI DONE AT ENSA. RR-46 B-F APRI-4100-26RDM NOZZLE TO SAFE-END ALA-53 SUR FNP'0-NDE-100.5 ADDED PER STEAM GENERATOR B5.70 Figure 012 REPLACEMENT DURING 2R14.

IPSI I

I DONE AT ENSA. RR-46 B-F APR1-4100-26RDM NOZZLE TO SAFE-END ALA-53 VOL FNP-0-NDE-100.31 ADDED PER STEAM GENERATOR B5.70 Figure 012 REPLACEMENT DURING 2R14. PSI DONE AT ENSA. RR-46 B-G-2 APR1-4101-QV001B (B)

VALVE BOLTING VT-1 FNP-0-NDE-100 21 Group 1. RR-23 B7.70 Figure 5-111-2 O

A1M -4101 OV601 4 eOPEq"VL BOBD12LGATE.V-mV RHR.

I,--

T--,------- -

Figure Internal disassembled.

B-G-2 APR1-4101-QV016B (B)

VALVE BOLTING VT-1 FNP-0-NDE-100.21 Group 1. RR-23 B7.70 Figure 13.M-2

,APR-4-101OQV01 COPES-VL-V BODY-12t GATE VLV RHR VT-3

-FNP-0-NDE-100 -Groupl: Inspect unepergmup If-"

B12.50 Figure Internal disassembled.

B-G-2 APR1-4102-QV032A (B)

VALVE BOLTING VT-1 FNP-0-NDE-100.21 Group 5. RR-23 B7.70 Figure B-BM2-APR! 41e2avo-~

[

e..2...i...

LV...

,UM-DISCH-VT----

-FNP-0-NDE-100-2P.- -Group 5. Inspect one pergroup-If B12.50 Figure Internal disassembled. m.i A

4102 QV037A rnPE HK.V _ V..I IM nI..

19-F r

B12.50 Figure Internal dsassembled.

-3 M 2 APR-.4103-QV021C VELAN-VALVE BODY 6!-GHK-VL--RHR-VT

-FNP-0-NDE-1008-- -Group4In tpeet one per grip-if B12 50 Figure Internal disassembled.

APR1-4103-OV051G- --

Figure Internal VELAN VALVE BODY 6 CHK VLV RHR VT-3 FNP-0-NDE-100 23 Group 2 Inspect one per group, 4f disassembled

".If e,'P-2-M-097 B12.50 B12 50

Page 14 of "i

J. M. FARLEY NuCLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage 1 (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Via NDE Procedures Remarks 1-M-2 APR! 4104-Q87-A VE.-,AIVE-BODV-" CHKA4LV..Sl.'.q

_ FN:-O-NDE*-002.

.Group3-nspectoeper.group-it B12.50 Figure Internal disassembled.

B-M-2-. A.PRl:4104:QV077A VELAN VALVE BODY 6" CHK VLV SI V-r-3--

-FNP-0-NDE-100 Group 3-Inspect-ionpergrouplt B12.50 Figure Intemal disassembled.

B-G-2 APR1-4109-FLG-1 FLANGE BOLTING VT-1 FNP-0-NDE-100 21 RR-23 B7.50 Figure B-M:2-

-ARii

-uQVo32B

,COPES12'CHK-VL--AC-eUM-DSC

-V VT

-FNP-0-NDE-10023-Group-6p one parqgoap-#

B12.50 Figure Internal disassembled.

B-M-2---APR1-4201-QV037B COPES 12t CHK VLV ACCUM DISCH

-V I3.-

-F-NP--0,NDE-I0023

-Group-5.-InspecLonnApAromupjL B12.50 Figure Internal disassembled.

B-M APR1.4202-QV021B VELAN VALVE BODY 6t CHK.VLV RHR.

.VT-3-.....

FNP-0-NDE-100.23-.-Group 2.-Inspeet one-per-greup-ff B12.50 Figure Intemal disassembled.

B-M-2..

-APRI-4203-QV051B VELAN VALVE BODY 6 CHK VLV RHR-

VT-3......

FNP-0-NDE-100.23 -Group 2-Inspect oneper grouplf" B12.50 Figure Internal disassembled.

-B-M-2

- -APR1-4204-QV076B--

.VELAN-VALVE-BODY 6" CHK VLV SI......-.

VT FNP-0-NDE-100 23 Group 3. Inspect one per group if B12.50 Figure Internal disassembled.

-B-M

-APR1-4204-0V077B

,VELAN-MAL-VE-BODY-6"-GHK-VLV-SI-VT--

-FNP-O-NDE-100 Group-3ispec-en,

,p B12.50 Figure Internal disassembled.

- B-M-2 APRI-4301-QV001A COPES VLV BODY 12" GATE VLV RHR VT-3 FNP-0-NDE-100.23 Group 1. Inspect one-per group if B 12.50 Figure Internal disassembled.

-B-M -APR1-4301-QV016A -

COPES VLV BODY 120 GATE VLV RHR

--- VT-3--- --FNP-O-NDE-100 23- -Group-l.-tnspect-on ji B12.50 Figure Internal disassembled.

B-G-2 APR1-4302-QV032C (B)

VALVE BOLTING VT-1 FNP-0-NDE-100 21 Group 5. RR-23 B7.70 Figure

_B-M 2 APR1-4302-QV032G COPES 12 CHK-VLV ACCUM DISCH-VT-3a

-FNP-0-NDE-100 23- -Group 5.-lnspect on, pergrouptf B12.50 Figure Internal disassembled.

B-G-2 APR1-4302-QV037C (B)

VALVE BOLTING B7 70 Figure I--APR1-4W2-OV037G..---

GOPEG-12' CHK VLV ACCUM DISCH I

B12 50 Figure Internal VT-1 V-T.3 FNP-0-NDE-10021 Group 5, RR-23 FNP-0-NDE-100 23 Group 5 Inspect one per group f disassembled

4, 10 V 4'

In k 10<

,NP-2-M-097

Page 15 of ku J. M. FARLEY NuCLEAR PLANT OUTAGE PLAN Interval 3 Period I Outage 1 (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol VIa NDE Procedures Remarks

-QoAPR1-430-QY021A VELAN VALVE BODY 6' CHK VLV RHR..

VT-3 -_

_FNP-0-NDE.100.23-.Group2. Inspect one per-group if.

B12.50 Figure Internal disassembled.

...M.

.. APR! 430..

-VEL.

ALBO DY-6L.HK-ViLRHR.

VT. - -FNP-O-NDE-100----

Greu.-2-nspeet-onf.per-group-if B12.50 Figure Internal disassembled.

B-M-----APR 1-4305V0770----

VELAN VALVE BODY 6" CHK.VLV 61-VT.-3

--FNP-O-NPE-100 -roup-lnspect-oneiper-group*

B12.50 Figure Internal disassembled.

B-F APR1-4501-1DM PRZ NOZZLE TO SAFE-END ALA-5 SUR FNP-O-NDE-100.5 B5.40 Figure 012 B-F APR1-4501-1DM PRZ NOZZLE TO SAFE-END ALA-5 VOL FNP-0-NDE-100.31 B5.40 Figure 012 AP_-1=4501-QV031A_

CROSBY VLVBODY.6! RLFVLV PZR -

VT-3-. - -

- FNP-0-NDE-100.23 - -Group-4-lnspect one pergroup-lt B12.50 Figure Internal disassembled.

B--M "APR1z4502-OV031B CROSBY VLV BODY 16 RLF'VL-V PZR--

VT'3

-FNP-O=NDEz10023- -Grup 4. iuspuCt uu pi,

,uui B12.50 Figure Internal disassembled.

-B-M

-APRt-4503-QV031C-CROSBY V-V BODY-6t-RLF-VLV-PZR--

VT-3.-..

FNP-0ONDE-100 23- -Group 4_Inspect one pergroup tf B12.50 Figure Internal disassembled.

-B-L-2--- -APR1-5100-1C------.........

R.CrPUMP CASINGS VT -----

FNP-O-NDE-100.23 INSPECT ONE PUMP CASING IF-A B12.20 Figure Internal PUMP IS DISASSEMBLED.

F-A APR1-5100-CS-1 REACTOR COOLANT PUMP 2A VT-3 FNP-0-NDE-100.23 Fl.40 Figure 037 Q2B41PO01A F-A APR1-5100-CS-2 REACTOR COOLANT PUMP 2A VT-3 FNP-0-NDE-100.23 F1.40 Figure 037 Q2B41P001A F-A APR1-5100-CS-3 REACTOR COOLANT PUMP 2A VT-3 FNP-0-NDE-100.23 F1.40 Figure 037 02B41P001A

-B-L-2---- -APRI-52004IC--

R C. PUMP CASINGS

_VT-3 FNP-0-NDE-100.23 INSPECT ONE PUMP CASING-1F-A B12.20 Figure Internal PUMP IS DISASSEMBLED.

B-L-2 APR1-5300-1C R C PUMP CASINGS VT'3 FNP-0-NDE-100 23 INSPECT ONE PUMP CASING IF A,

,NP-2-M-097

.14 At PUMP IS DISASSEMBLED B12 20 Figure Internal

Page 16 of eu J. M. FARLEY NuCLEAR PLANT OUTAGE PLAN Interval 3 Period I Outage I (89) Code Cat.

Component No.

IMethod (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol VIa NDE Procedures Remarks R-G/AUG APR1-5300-FW1 R C. PUMP FLYWHEEL SUR-AUG FNP-0-NDE-100.5 Perform surface exam on any B1.14 Figure flywheel that Is disassembled. Any "flywheel not previously disassembled

& surface examined, will be given a volumetric exam on Inner half-radius during third period.

C-B APR2-3500-4 RESID HX REINF PLATE/VSL WELD SUR FNP-0-NDE-100.5 C2.31 Figure 027 C-A APR2-3500-A RESIDUAL HX SHELL TO FLANGE ALA-32 VOL FNP-0-NDE-100A,4 C1.10 Figure 023

-tO.1" F-A APR2-4100-2MS-R613 SPRING CAN W/ATT VT-3 FNP-0-NDE-100.23 F1.20 Figure 037 F-A APR2-4101-2MS-R511 2 DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-100 23 F1.20 Figure 037 W/STANC (3)

F-A APR2-5130-CS-1 RHR PUMP (A) 02E1P001A-A VT-3 FNP-0-NDE-10023 F1.40 Figure 037 F-A APR2-5130-CS-2 RHR PUMP (A) Q2E11P001A-A VT17-3 FNP-0-NDE-100.23 F1.40 Figure 037 F-A APR2-5130-CS-3 RHR PUMP (A) Q2E11P001A-A VT-3 FNP-0-NDE-100.23 F1.40 Figure 037 F-A D200039-1 -CS TANK ANCHOR BOLT RING W/ATT VT-3 FNP-0-NDE-100.23 F1.40 Figure 037 D-A D200039-1-CS TANK (ATT)

ANCHOR BOLT RING W/ATT VT-I FNP-0-NDE-100.21 D1.10 Figure F-A D200039-1-RM P 2A RMW PUMP 02P12P001A-A VT-3 FNP-0-NDE-100.23 F1.40 Figure 037 D200089-1 -SW 501A Figure 037 D200089-1-SW 501A (ATT)

Figure SW STRAINER Q2P16F501A SW STRAINER Q2P16F501A VT-3 FNP-0-NDE-100 23 VT-1 FNP-0-NDE-100,21

,-dP-2-M-0g7 F-A F1 40 D-A D1 10

Page 17 of ku J. M. FARLEY NuCLEAR PLANT OUTAGE PLAN Interval 3 Period I Outage 1 (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol VIa NDE Procedures Remarks F A E.2 045,2A,-,,-......

REGTOWL.R.STRAIN. -

-VT-3--

.FNP-0-NDE400,23 F1.30 Figure 038 F-A EG2-046-2AFW-R62 ONE DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-100.23 F1.30 Figure 038 F-A--- - -EG2-046-2AFW-R76 TWO DIRECTIONAL RESTRAINT VT-3

-FNP-0-NDE-100.23 F1.30 Figure 038 W/ATT D-A -...

EG2-046-2AFW-R76 (ATr)

TWO DIRECTIONAL RESTRAINT VT-1 FNP-0-NDE-100 21 D1.20 Figure W/ATT F-A-...

EG2-046-2AFW-R83-

-TWOtDIREGTIONAL-RESTRAINT-VT-3S

-FNPONDE-100.23 F1.30 Figure 038 F-A EG2-077-2SW-R22 IWO DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-100.23 F1.30 Figure 038 W/A'T D-A EG2-077-2SW-R22 (ATl)

TWO DIRECTIONAL RESTRAINT VT-1 FNP-0-NDE-100.21 D1.20 Figure W/ATT F-A EG2-200-2SW-R726 SWAY STRUT VT-3 FNP-0-NDE-100.23 F1.30 Figure 038 F-A EG2-202-2SW-R716 TWO DIRECTIONAL RESTRAINT W/

VT-3 FNP-0-NDE-100.23 F1.30 Figure 038 ATT F-A EG2-203-2SW-R736 TWO DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-100.23 F1.30 Figure 038 F-A EG2-203-2SW-R823 ONE DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-100 23 F1.30 Figure 038 F-A EG2-203-2SW-R831 SWAY STRUT VT-3 FNP-0-NDE-100.23 F1.30 Figure 038 F-A EG2-210-2SW-R48 SWAY STRUT VT-3 FNP-0-NDE-100.23 F1.30 Figure 038 F-A EG2-211.2SW-R88 ONE DIRECTIONAL RESTRAINT VT-3 FNP-0l-NDlE-100 23q Figure 038 EG2-214-2SW-R88 (AU-)

Figure W/ATT ONE DIRECTIONAL RESTRAINT W/ATT I

VT-1 FNP.0-NDE.10Q.2L.

.,4P-2-M-O97 F1.30 D1 20

Page 18 of :,u J. M. FARLEY NuCLEAR PLANT OUTAGE PLAN Interval 3 Period I Outage I (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Vie NDE Procedures Remarks F-A EG2-211-SW-2A13 ANCHOR W/AATT VT-3 FNP-0-NDE-100 23 F1.30 Figure 038

. D-A EG2-211-SW-2A13(ATT)

ANCHOR W/ATT -....................-

v'-V -.-

FNP-0-NDE-100 21 D1.20 Figure F-A EG2-218-2SW-R568 ONE DIRECTIONAL RESTRAINT V`r-3 FNP-0-NDE-100.23 F1.30 Figure 038 W/ATT D-A--

-EG2-218-2SW-R568 (ATT) --

ONE DIRECTIONAL RESTRAINT vr-

-VTl-----

FNP-0-NDE-0021 D1.20 Figure W/ATT F-A EG2-220-2SW-BR12 SNUBBER (H)(2) W/ATT VT-3 FNP-0-NDE-100 23 RR-12 F1.30 Figure 038 D-A EG2-220-2SW-BR12 (ATr)

SNUBBER (H)(2) W/ATT VT-1 FNP-0-NDE-100.21 RR-12 D1.20 Figure F-A EG2-221-2SW-R505 TWO DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-100.23 F1.30 Figure 038 Figure ANCHOR WIA' i

-VT I -FNP-fA-NfI'Fzi (o

>1-F-A EG2-248-2CCW-R213 3 DIRECTIONAL RESTRAINT W/ATT VT-3 FNP-0-NDE-100 23 F1.30 Figure 038 D-A EG2-248-2CCW-R213 (ATT) 3 DIRECTIONAL RESTRAINT W/ATT VT-1 FNP-0-NDE-100.21 D1.20 Figure F-A EG2-251-2CCW-R83 TWO DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-100.23 F1.30 Figure 038

- F-A---

EG2-255-2CCW-R245----

SNUBBER (2)-W/STANCHION (2)-

VT-3-.......

FNP-0-NDE-100:23-RR-12 F1.30 Figure 038 Figure 038 D-A EG2-255-CCW-2A28 (ATT)

D1.20 Figure F-A EG2-260-2CCW-R445 F1 30 Figure 038 ANCHOR W/ATT

-4 ANCHOR W/ATT IONE DIRECTIONAL RESTRAINT W/ATT VT-3 FNP-0-NDE-100.23 4-L ________________

VT-1 VT-3 FNP-0-NDE-100 21 FNP-0-NDE-100 23 I'

k Al P

NP-2-M-097 D1.20 F1.30

..p

Page 19 of kv J. M. FARLEY NuCLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage I (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol Via NDE Procedures Remarks D-A EG2-260-2CCW-R445 (ATT)

ONE DIRECTIONAL RESTRAINT VT-I FNP-0-NDE-100.21 D1.20 Figure W/ATT F-A EG2-317-2PA-R34 ONE DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-100.23 F1.30 Figure 038 F-A EG2-448-2CCW-R165 TWO DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-1 00.23 F1.30 Figure 038 F-A EG2-449-2CCW-R147 SPRING CAN VT-3 FNP-0-NDE-100.23 F1.30 Figure 038 F-A EG2-480-2AFW-R149 SWAY STRUT VT-3 FNP-0-NDE-100.23 F1.30 Figure 038

.F-A------

1,AF'3N2A6 ANCHOR.WIATT"--

-V't-3

-E-I6O-26 F1.30 Figure 038

-D-A------

EG2-481-AFW-2A6(ATr)--...

ANCHOR WIATT

-- VT-1.......

FNP-0-NDE-100 21.

D1.20 Figure F-A EG2-482-2AFW-R143X SPRING CAN (2) W/STANCHION VT-3 FNP-0-NDE-100 23 F1.30 Figure 038 F-A EG2-482-2AFW-R66 TWO DIRECTIONAL RESTRAINT V1VT-3 FNP-0-NDE-100 23 F1.30 Figure 038 F-A EG2-494-2SW.R288 TWO DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-100 23 F1.30 Figure 038 F-A EG2-496-2SW.R264 TWO DIRECTIONAL RESTRAINT VT-3 FNP-0-NDE-100 23 F1.30 Figure 038 F-A EG2-496-2SW-R268 3 DIRECTIONAL RESTRAINT W/ATT VT-3 FNP-0-NDE-100 23 F1.30 Figure 038 r% A nat

n.

.n D1 20 Figure 3 DUIHR I IONAL-RESTRAINT WIA-'T--

_VT-rI FNP-0-NDE-100.2t L__

F-A F1 30 D-A D1 20 EG2-548-AS.2A4 Figure 038 EG2-548-AS-2A4 (ATT)

Figure ANCHOR W/ATT 7 ANCHOR W/ATT

1.

VT-3 VT-1 FNP-0-NDE-100 23 FNP-0-NDE-10021 C

.NP-2-M-0g7 I',

p tI C.,

I IC

Page 20 of 20 J. M. FARLEY NuCLEAR PLANT OUTAGE PLAN Interval 3 Period 1 Outage 1

..4P-2-M-097 (89) Code Cat.

Component No.

Method (89) Item No.

Figure No.

Component Desc.

Cal Block No.

Sur Vol VIa NDE Procedures Remarks F-A EG2-620-2RM-R133 TWO DIRECTIONAL RESTRAINT V1VT-3 FNP-0-NDE-100.23 F1.30 Figure 038

INDEX TAB D DESCRIPTION TAB CLASS 1 REACTOR VESSEL EXAMS 1.1 PRESSURIZER EXAMS 1.2 STEAM GENERATOR EXAMS 1.3 PIPING WELD EXAMS 1.4 PRESSURE RETAINING BOLTING EXAMS 1.5 REACTOR COOLANT PUMP EXAMS 1.6 VALVE BODIES/BOLTING EXAMS 1.7 CLASS 2 COMPONENT EXAMS 2.1 STEAM GENERATOR EXAMS 2.2 PIPING WVELD EXAMS 2.3

1.1

EXAMINATION

SUMMARY

FOR UNIT 2 INTERVAL 3 PERIOD 1 OUTAGE 1 DRAWING APRI-1100 REACTOR VESSEL ITEM NO VOLUMERIC SURFACE VISUAL REMARKS NI NRI RI NI NRI RI NI NRI RI 1

x t1-t-I-4-4-I-4-4-4 1-T-t-t-1-t-.I-I I-I.

0-4-4-4-4-4-I-I I-4-9.-*-4-I-4-4-J-I.

i i

w w

REACTOR VESSEL 02-BIIHO01 FLANGE T3 vE2SE1 CIRC WELD NOZZLE TO VESSEL WELD(RET ARi-1IIOOA)

"LOWER SHELL TO LOWER HEAD CIRC.

WELD LOWER HEAD TO INTERMEDIATE RING CIRC. WELD i 7-21-97 HSK TLS IREVISED PER REA 96.

0 111-22-91 SDH JAR ISSUED PER PCN S-91 REv

-DATE I Y CH-'f1 I DESCRIDTION Southern Comoany Services, Incro' ALABAMA POWER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT UNIT 2

-r-,,*.

lAB/RI HGM PKC/AH DML I APPRI I AP*P*2 APPR 3 APPR 4 RLEACTER VESSEL SCS DRAV./ING NUME*R SHEET PEV A-356454 7 T

C

(

C WESTINGHOUSE NUCLEAR SERVICES DIVISION PLANT UNIT SKETCH INSPECTION SERVICES J. M. Farley 2

APR1-1100 SYSTEM / COMP.

PROCEDURE WELD ULTRASONIC EXAMINATION REACTOR VESSEL FNP-ISI-54, REV. 0 INSERVICE EXAMINER DATE

'-/fkz~jiiuldiJ09/19/02 EQUIPMENT TRANSDUCER SCAN DIRECTION CALIBRATION CHECK INST. S I N INITIAL TIME Staveley SIN G03136 G03136 G03136 03:17 / 09-19-02 136-897K SIZE 1.0 1.0 1.0 REP. RATE 1K FREQ.

2.25 MHz 2.25 MHz 2.25 MHz REJECT ANGLE 00 00 00 OFF DISTANCE FROM FINAL TIME DAMPING CALIBRATION SIGNAL SWEEP METAL PATH SCRIBE I REF. LINE TO 06:20 / 09-19-02 500 OHMS REFLECTOR AMPLITUDE POSITION LOCATION

-20%

-50%

PEAK

+50%

+20%

-20%

-50%

PEAK

+50%

+20%

FILTER D

80%

45 32" 32" 32" 32" 32"

-2.5" -1.5" 0

1.5" 2.5" LIN. CHECK C

80%

5.2 38" 38" 38" 38" 38"

-3"

-2" 0

2" 3"

SAT B

70%

6.2 44" 44" 44" 44" 44"

-3.5" -2.3" 0

2.3" 3 5" S. U. CABLE 125' / RG 174 CAL. BLOCK ALA-IV-2

_OUPLANT THICKNESS 14" DEMIN WATER CAL. GAIN 72.8 dB SURFACE THERMOMETER SIN 48881 DEINATTEMPERATURE 8CA G

WELD BEAM EXAM WER TEMP.

AM SCAN EXAMINATION LIMITATIONS SURFACE RESULTS REMARKS ANGLERESLT REMRK NUMBER AGESRAE N

1020F 00 YES NONE SMOOTH x

REFERENCE ULTRASONIC INDICATION DATA SHEET FOR GEOMETRY

C C

C PLANT J M. FARLEY UNIT 2

SKETCH APRI-ilCO WESTINGHOUSE NUCLEAR SERVICES DIVISION SYST. I COMP.

REACTOR VESSEL PROCEDURE FNP-ISI-54, REV. 0 ULTRASONIC INDICATION DATA EXAMINER DATE 9-19-02 LINEARITY AND CAL. CHECK SAT CAL. BLOCK THICKNESS 14" INDICATION LENGTH MIN 50%

MIN. 100%

PEAK MAX. 100%

MAX. 50%

BEAM THICKNESS WELD NUMBER FROM TO SWP.

IN. TO SWP.

IN. TO SWP IN. TO +1-DAC

SWP, IN. TO

SWP, IN. TO ANGLE DIR.

SURF. 2 WELD SURF. 5 REMARKS REF.

REF.

AMPL, REF.

REF.

(1) 4.4 1.2" 100%

00 (2)

N/A 9.25" NIA REF. SKETCH

-~~~

I J....L.....L............

(1) For 3600 (2) From reactor vessel head seating surface Am.4

/

(7

(

C )

WESTINGHOUSE NUCLEAR SERVICES DIVISION PLANT UNIT SKETCH INSPECTION SERVICES J. M. Farley 2

APRI-1100 SYSTEM I COMP.

PROCEDURE WELD ULTRASONIC EXAMINATION REACTOR VESSEL FNP-ISI-54, REV. 0 INSERVICE EXAMINER

)

r 40 DATE

_,_NM iX,_o,,

, j. A.-

09/19/02 EQUIPMENT TRANSDUCER SCAN DIRECTION CALIBRATION CHECK

INST, INIIILTM Staveley SIN 0094KW 0094KW 0094KW0 INITIAL TIME Stave72F 03:15 / 09-19-02 136-472F SIZE 1.0 1.0 1.0 REP. RATE 1K FREQ.

2.25 MHz 2.25 MHz 2.25 MHz REJECT ANGLE 60 OUT 60 OUT 60 OUT OFF DISTANCE FROM FINAL TIME DAMPING CALIBRATION SIGNAL SWEEP METAL PATH SCRIBE I REF. LINE TO 06.18 / 09-19-02 500 OHMS REFLECTOR AMPLITUDE POSITION 500 LOCATION 80%

-20%

.2

.- 50%

PEAK

+50%

+20%

.20%

-50%

PEAK

+50%

+20%

1 E

80%

4.9 29.2" 29.2" 29.2" 29.2" 29.2" 1.9" 2.2" 2.5" 4.0" 4.6" LIN. CHECK D

50%

6.8 32.2" 32.2" 32.2" 32.2" 32 2" 1.7" 2.6" 3.0" 5.5" 6.2" SAT C

35%

7.9 38.2" 38.2" 38 2" 38.2" 38.2" 1.6" 2.4" 4.7" 6.6" 7.8" S. U. CABLE 125' / RG 17,4 125'/

CAL. BLOCK ALA-RV-2

_OUPLNTTHICKNESS 14' DEMIN WATER CAL. GAIN 66.4 dB SURFACE THERMOMETER SIN 48881 TEMPERATURE 88u t WER TEMP.

AM SCAN EXAMINATION LIMITATIONS EXAM RESULTS REMARKS NUMBER ANGLE SURFACERI 1

102 0F 60 YES NONE SMOOTH X

(7

(.

(

WESTINGHOUSE NUCLEAR SERVICES DIVISION PLANT UNIT SKETCH INSPECTION SERVICES J M. Farley 2

APR1-1100 SYSTEM I COMP.

PROCEDURE WELD ULTRASONIC EXAMINATION REACTOR VESSEL FNP-ISI-54, REV. 0 INSERVICE EXA p

IN

-7;

-ATE 24

ý

,c J

09/19/02 EQUIPMENT TRANSDUCER S

ECTION CALIBRATION CHECK INST. S I N INITIAL TIME Staveley SIN TKMN TKMN TKMN09-19-02 136-911K SIZE 1.0 1.0 1.0 REP. RATE 1K FREQ.

2.25 MHz 2.25 MHz 2.25 MHz REJECT ANGLE 60 IN 60 IN 60 IN OFF DISTANCE FROM FINAL TIME DAMPING CALIBRATION SIGNAL SWEEP METAL PATH SCRIBE I REF. LINE TO 06:16 / 09-19-02 500 OHMS REFLECTOR AMPLITUDE POSITION LOCATION

-20%

-50%

PEAK

+50%

+20%

-20%

-50%

PEAK

+50%

+20%

FILTER E

80%

4.9 29.2" 29.2" 29.2" 29.2" 29.2" 1.9" 2.2" 2.5" 4.0" 4.6" LIN. CHECK D

50%

6.8 32.2" 32.2" 32.2" 32.2" 32.2" 1.7" 2.6" 3 0" 5.5" 6.2" SAT C

50%

7.9 38 2" 38.2" 38.2" 38.2" 38.2" 1.6" 2.4" 4.7" 6.6" 7.8" S. U. CABLE 125'/ RG174

-CAL.

BLOCK ALA-l'V-2 COUPLANT THICKNESS 14" DEMIN WATER CAL. GAIN 76.6 dB SURFACE THERMOMETER SIN 48881 TEMPERATURE 8Bv I WELD BEAM EA WER TEMP.

ANGLE SCAN EXAMINATION LIMITATIONS EXAM RESULTS REMARKS NUMBERNI NRI R

1 102 0 F 60 YES NONE SMOOTH X

C C

(

PLANT J.M. FARLEY UNIT 2

SKETCH APRI-1100 WESTINGHOUSE NUCLEAR SERVICES DIVISION SYST. CO P.

REACTOR VESSEL PROCEDURE FNP-ISI-54, REV. 0 ULTRASONIC INDICATION DATA EXAMINER tc" % Pý.-

DATE 9-19-02 LINEARITY AND CAL. CHECK SAT CAL. BLOCK THICKNESS 14" INDICATION LENGTH MIN. 50%

MIN. 100%

PEAK MAX. 100%

MAX. 50%

BEAM THICKNESS WELD NUMBER FROM TO

SWP, IN.TO

SWP, IN. TO SWP.

IN. TO

+/- DAC SWP.

IN.TO SWP.

IN. TO ANGLE DIR.

SURF. 2 WELD SURF. 5 REMARKS REF.

REF.

AMPL REF.

REF.

(1) 6.3 1 2" 100%

60in (2)

N/A 9.25" N/A REF. SKETCH (1) For 3600 (2) From reactor vessel head seating surface

-\\__

_,.. L

C

(

C WESTINGHOUSE NUCLEAR SERVICES DIVISION PLANT UNIT SKETCH INSPECTION SERVICES J. M. Farley 2

APRI-1100 SYSTEM / COMP.

PROCEDURE WELD ULTRASONIC EXAMINATION REACTOR VESSEL FNP-ISI-54, REV. 0 INSERVICE EXAMINER 0 v~

DATE 0/90 EQUIPMENT TRANSDUCER SCAN DIRECTION CALIBRATION CHECK INST. S I N INITIAL TIME Staveley SIN 00DRRP 00DRRP O0DRRP 03:26 / 09-19-02 136-905K SIZE 1.0 1.0 1.0 REP. RATE 1K FREQ.

2.25 MHz 2.25 MHz 2.25 MHz REJECT ANGLE 120 120 120 OFF DISTANCE FROM FINAL TIME DAMPING CALIBRATION SIGNAL SWEEP METAL PATH SCRIBE I REF. LINE TO 06:14 I 09-19-02 500 OHMS REFLECTOR AMPLITUDE POSITION LOCATION

-20%

-50%

PEAK

+50%

+20%

. -20%

-50%

PEAK

+50%

+20%

1 E

80%

5.2 23.3" 23.4" 23.6" 23.9" 24.4" 2.9" 3.8" 5.3" 7.6" 8.2" LIN. CHECK D

60%

6 8 32.3" 32.4" 32.7" 32.9" 33.2" 4.7" 5 7" 6.2" 7.3" 9.6" SAT C

50%

8.0 38 4" 38 6" 38.8" (1)

(1) 4.2" 5.9" 8.0" (1)

(1)

S. U. CABLE 125'/ RG17 4

-CAL.

BLOCK ALA-RV-2 COUPLANT THICKNESS 14" DEMIN WATER CAL. GAIN 70.2 dB SURFACE THERMOMETER SIN 48581 D C TEMPERATURE 8,

F WELD BEAM EA WER TEMP.

AM SCAN EXAMINATION LIMITATIONS EXAM RESULTS REMARKS NUMBER ANGLE SURFACERI 1020F 120 YES NONE SMOOTH X

REFERENCE ULTRASONIC INDI(ATION DATA SHEET FOR GEOMETRY (1) NO MEASUREMENTS TAKEN DUE TO WIDTH OF BLOCK

C C

C PLANT J.M. FARLEY UNIT 2

SKETCH APR1-1100 WESTINGHOUSE NUCLEAR SERVICES DIVISION SYST. / COMP.

REACTOR VESSEL PROCEDURE FNP-ISI-54, REV. 0 ULTRASONIC INDICATION DATA EXAMINER

~

2AOg AE9-19-02 LINEARITY AND CAL. CHECK SAT CAL. BLOCK THICKNESS 14" INDICATION LENGTH MIN, 50%

MIN. 100%

PEAK MAX, 100%

MAX. 50%

BEAM THICKNESS WELD NUMBER IIN.

TO IN. TO IN. TO +/. DAC IN. TO IN. TO REMARKS FROM TO SWPI. TO SWP.

IE, SWP.

RE. O A

SWP.

IE.

SWP.

RN, ANGLE DIR.

SURF. 2 WELD SURF. 5 REF.

REF.

AMPL REF.

REF.

1(1) 6.3 1.2" 100%

120 (2)

N/A 9.25" N/A REF. SKETCH (1) For 3600 (2) From reactor vessel head seating surface

(7 C

Q)

WESTINGHOUSE NUCLEAR SERVICES DIVISION PLANT UNIT SKETCH INSPECTION SERVICES J. M. Farley 2

APRI-1100 SYSTEM I COMP.

PROCEDURE WELD ULTRASONIC EXAMINATION REACTOR VESSEL FNP-ISI-54, REV. 0 INSERVICE

EXAMINER,

~

().

(7 DATE In 1 09/19/02 EQUIPMENT TRANSDUCER SCAN DIRECTION CALIBRATION CHECK INST. S I N INITIAL TIME Staveley SIN 00DRRJ 00DRRJ O0DRRJ 03:10 /09-19-02 136-904K SIZE 1.0 1.0 1.0 REP. RATE 1K FREQ.

2.25 MHz 2.25 MHz 2 25 MHz REJECT ANGLE 160 160 160 OFF DISTANCE FROM FINAL TIME DAMPING CALIBRATION SIGNAL SWEEP METAL PATH SCRIBE I REF. LINE TO 06:09 / 09-19-02 500 OHMS REFLECTOR AMPLITUDE POSITION LOCATION

.20%

.50%

PEAK

+50%

+20%

.20%

.50%

PEAK

+50%

+20%

FILTER1 E

80%

5.2 29 5" 29.8" 30.2" 30.5" 30.7" 4.0" 4.6" 6.2" 7.8" 8 5" LIN. CHECK D

50%

7.2 32.6" 33.0' 33.3" (1)

(1) 7.8" 8.3" 9.5" (1)

(1)

SAT S. U. CABLE 125'/ RG 174 CAL. BLOCK ALA-IV-2 COUPLANT 1

6

___I_._ITHICKNESS 14' DEMIN WATER CAL GAIN 72.6 dB SURFACE THERMOMETER S/N 48881 1

TEMPERATURE 887F WELD BEAM EXAM i

WER TEMP.

AM SCAN EXAMINATION LIMITATIONS SURFACE RESULTS REMARKS NUMBER ANGLENRI R

1 1020F 160 YES NONE SMOOTH X

REFERENCE ULTRASONIC INDICATION 1DATA SHEET FOR GEOMETRY (1) NO MEASUREMENTS TAKEN DUE TO WIDTH OF BLOCK La-4=

q

Q PLANT J.M. FARLEY UNIT 2

SKETCH APRl-1100 WESTINGHOUSE NUCLEAR SERVICES DIVISION SYST. I COMP.

REACTOR VESSEL PROCEDURE FNP-ISI-54, REV. 0 ULTRASONIC INDICATION DATA EXAMINER DATE 9-19-02 LINEARITY AND CAL. CHECK SAT CAL. BLOCK THICKNESS 14" INDICATION LENGTH MIN. 50%

MIN. 100%

PEAK MAX. 100%

MAX. 50%

BEAM THICKNESS WELD NUMBER FROM T

TO SWP.

ITO IN. TO

+1-DAC IN. TO N. TO REMARKS SW.

SP REF..WPAMPI.

AGLEI DIR.

SURF. 2 WELD SURF. S REF.

REF.

AMPL.

REF.

SPI REF.

(1) 1.2" 100%

160 (2)

N/A 9.25" N/A REF. SKETCH (1) For 3600 (2) From reactor vessel head seating surface

_____i

(

WESTINGHOUSE NUCLEAR SERVICES DIVISION INSPECTION SERVICES GENERAL - INDICATION DATA PLANT J.M. FARLEY UNIT 2

SKETCH APRI-1100 SYSTEM / COMP.

REACTOR VESSEL PROCEDURE FNP-ISI-54, REV. 0 EXAMINER M

jR DETECTED BY UT X

PT MT VT IDENT. NO.

WELD 1 PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE, LOCATION AND TYPE OF INDICATION DESCRIBE EXTRA OR SPECIAL EQUIPMENT IF USED FOR SIZING OR REPORTING. IF NECESSARY INCLUDE SKETCH SHOWING GENERAL CONFIGURATION OF ITEM OR AREA Geometry reflector information for 00, 60, 120 and 160 see sketch below.

(1) 00, SWP. 4.4 =31.5" (2) 60, SWP. 6.3 =31" (3) 120, SWP. 6.3 =31" (4) 160, SWP. 6.7=31" SKETCH ILLUSTRATIVE ONLY

C

(

(.

PLANT / UNIT OUTAGE:

WesDyne J.M. FARLEY 3-1-1 International TRANSDUCER I.D.

PROCEDURE:

REV.

REACTOR VESSEL U.T. EXAMINATION 00 FNP-ISI-54 0

TRANSDUCER RF WAVEFORM TRANSDUCER INFORMATION MANUFACTURER KBA CHANNEL N/A TARGET D

FREQUENCY 2.25 MHz ACTIVE ELEMENT DIMENSION 1.0" CONNECTOR TYPE BNC SERIAL NUMBER G03136 PRE EXAM POST EXAM MONITOR OSCILLOSCOPE MONITOR OSCILLOSCOPE MANUFACTURER TEKTRONIX VERTICAL SCALE 100mv

/ DIV.

MANUFACTURER TEKTRONIX VERTICAL SCALE 100mv

/ DIV.

MODEL NUMBER 2445B HORIZONTAL SCALE 1.0uSEC/DIV.

SERIAL NUMBER B011056 PERFORMED BYA SERIAL NUMBER B011056 PERFORMED BY:

CALIBRATION VALID UNTIL 8-21-03 g

J,-

CALIBRATION VALID UNTIL 8-21-02 Q, e DATE

\\-j 9-18-02 DATE 1'j 9-19-02

C, (17 C

PLANT / UNIT OUTAGE:

W esDyne J.M. FARLEY 3-1-1 International TRANSDUCER I.D.

PROCEDURE:

REV.

REACTOR VESSEL U.T. EXAMINATION 60 OUT FNP-ISI-54 0

TRANSDUCER RF WAVEFORM TRANSDUCER INFORMATION MANUFACTURER KBA CHANNEL NIA TARGET E

FREQUENCY 2.25 MHz ACTIVE ELEMENT DIMENSION 1.0" CONNECTOR TYPE BNC SERIAL NUMBER 0094KW PRE EXAM MONITOR OSCILLOSCOPE MANUFACTURER TEKTRONIX VER MODEL NUMBER 2445B HOR SERIAL NUMBER B011056 PER CALIBRATION VALID UNTIL 8-21-03 TICAL SCALE 100mv

/ DIV.

IZONTAL SCALE 1.0uSEC/DIV.

FORMED BY:

DATE 9-18-02 POST EXAM MONITOR OSCILLOSCOPE MANUFACTURER TEKTRONIX VERTICAL SCALE 100mv

/ DIV.

MODEL NUMBER 2445B HORIZONTAL SCALE 1 OuSEC/DIV.

SERIAL NUMBER B011056 PERFORMED BY:

CALIBRATION VALID UNTIL 8-21-02 A r DATE 9-19-02

(7 C

C'I PLANT I UNIT OUTAGE:

W esDyne J.M. FARLEY 3-1-1 International TRANSDUCER I.D.

PROCEDURE:

REV.

REACTOR VESSEL U.T. EXAMINATION 60 IN FNP-ISI-54 0

TRANSDUCER RF WAVEFORM TRANSDUCER INFORMATION MANUFACTURER KBA CHANNEL NIA TARGET E

FREQUENCY 2.25 MHz ACTIVE ELEMENT DIMENSION 1.0" CONNECTOR TYPE BNC SERIAL NUMBER OOTKMN PRE E; MONITOR OSCILLOSCOPE MANUFACTURER TEKTRONIX MODEL NUMBER 2445B SERIAL NUMBER B011056 CALIBRATION VALID UNTIL 8-21-03 VERTICAL SCALE 100mv

/ DIV.

HORIZONTAL SCALE 1 OuSEC/DIV.

PERFORMED BY.

DATE 9-18-02 POST EXAM MONITOR OSCILLOSCOPE MANUFACTURER TEKTRONIX VERTICAL SCALE 100mv

/ DIV.

MODEL NUMBER 2445B HORIZONTAL SCALE 1 OuSEC/DIV.

SERIAL NUMBER B011056 PERFORMED BY CALIBRATION VALID UNTIL 8-21-02

(?zR.ap-.

DATE

\\-j 9-19-02 4

C C.

(

PLANT i UNIT OUTAGE:

W esDyne J.M. FARLEY 3-1-1 International TRANSDUCER I.D.

PROCEDURE:

REV.

REACTOR VESSEL U.T. EXAMINATION 120 FNP-ISI-54 0

TRANSDUCER RF WAVEFORM TRANSDUCER INFORMATION MANUFACTURER KBA CHANNEL NIA TARGET E

FREQUENCY 2.25 MHz ACTIVE ELEMENT DIMENSION 1.0" CONNECTOR TYPE BNC SERIAL NUMBER OODRRP nnr r:VAA RA rIrý- I MONITOR OSCILLOSCOPE MANUFACTURER TEKTRONIX MODEL NUMBER 2445B SERIAL NUMBER B011056 CALIBRATION VALID UNTIL 8-21-03 VERTICAL SCALE 100mv I DIV.

HORIZONTAL SCALE 1 OuSEC/DIV.

PERFORMED BY DATE 9-18-02 PUOST EXAM MONITOR OSCILLOSCOPE MANUFACTURER TEKTRONIX VERTICAL SCALE 100mv

/ DIV.

MODEL NUMBER 2445B HORIZONTAL SCALE 1.0uSEC/DIV.

SERIAL NUMBER B011056 PERFORMED BY:

CALIBRATION VALID UNTIL 8-21-02 A

DATE

%-i 9-19-02

C (7

(t PLANT I UNIT OUTAGE:

W esDyne J.M. FARLEY 3-1-1 International TRANSDUCER I.D.

PROCEDURE:

REV.

REACTOR VESSEL U.T. EXAMINATION 160 FNP-ISI-54 0

TRANSDUCER RF WAVEFORM TRANSDUCER INFORMATION MANUFACTURER KBA CHANNEL NIA TARGET E

FREQUENCY 2.25 MHz ACTiVE ELEMENT DIMENSION 1.0" CONNECTOR TYPE BNC SERIAL NUMBER OODRRJ MONITOR OSCILLOSCOPE MANUFACTURER TEKTRONIX MODEL NUMBER 2445B SERIAL NUMBER B011056 CALIBRATION VALID UNTIL 8-21-03 VERTICAL SCALE 100mv I DIV.

HORIZONTAL SCALE 1.0uSEC/DIV.

PERFORMED BY' DATE 4

9-18-02 POST EXAM MONITOR OSCILLOSCOPE MANUFACTURER TEKTRONIX VERTICAL SCALE 100mv I DIV.

MODEL NUMBER 2445B HORIZONTAL SCALE 1.0uSEC/DIV.

SERIAL NUMBER B011056 PERFORMED BY.

CALIBRATION VALID UNTIL 8-21-02

(

I DATE 9-19-02 m.

A.

Farley Nuclear Plant Ultrasonic Instrument Qualification Record SHARED FNP-0-NDE-100.32 Southern Nuclear Operating Company nstrument Sheet No.

S02F2L007 Manufacturer Model Serial No.

Staveley SONIC 136 136-904K Transducer Manufacturer Size Frequency Serial No.

KBA

.50 2.25 MHZ 009TNR Reference Standard Type Serial No.

Mini Angle Beam 4846 Horizontal Linearity Back Refl.

Signal Position Back RefI.

Signal Position 1

1.0 6

6.0 2

2.0 7

7.0 3

3.0 8

80 4

4.0 9

90 5

50 10 10.0 Screen Height Linearity Amplitude Ha Amplitude Hb Amplitude Ha Amplitude Hb 100 FSH 50 50 FSH 25 90 FSH 45 40 FSH 20 80 FSH 40 30 FSH 15 70 FSH 35 20 FSH 9

60 FSH 29 10 FSH 4

Amplitude Control Linearity Indication Set at %

Indication Limits dB Control Change Instrument Indication of Full Screen

% of Full Screen

% of Full Screen 80%

32% to 48%

-6 dB 40 80%

16% to 24%

-12 dB 20 40%

64% to 96%

+6 dB 80 20%

64% to 96%

+12 dB 82 Instrument Qualification Results Horizontal Linearity Screen Height Linearity Amplitude Control Linearity Acceptable E

Acceptable W,

Acceptable Remarks FINAL Examiner Paul Valden Level Examiner N/ A Level Date Initials

.2/

II Initials N/A 9/20/2002

\\<.-NDE Level 111111 eview Level

-mri Date 0

i Revision 3.

p IJ L/

Farley Nuclear Plant Ultrasonic Instrument Qualification Record SHARED FNP-0-NDE-100.32 Southern Nuclear Operating Company nstrument Sheet No.

S02F2L008 Manufacturer Model Serial No.

Staveley SONIC 136 136-472F Transducer Manufacturer Size Frequency Serial No.

KBA

.50 2.25 MHZ 009TNR Reference Standard Type Serial No.

Mini Angle Beam 4846 Horizontal Linearity Back Refl.

Signal Position Back Refl.

Signal Position 1

10 6

60 2

20 7

70 3

30 8

80 4

40 9

90 5

50 10 100 Screen Height Linearity Amplitude Ha 100 FSH 90 FSH 80 FSH 70 FSH 60 FSH Amplitude Hb 50 46 40 35 30 Amplitude Ha 50 FSH 40 FSH 30 FSH 20 FSH 10 FSH Amplitude Hb 25 20 15 10 4

Amplitude Control Linearity Indication Set at %

Indication Limits dB Control Change Instrument Indication of Full Screen

% of Full Screen

% of Full Screen 80%

32% to 48%

-6 dB 38 80%

16% to 24%

-12 dB 18 40%

64% to 96%

+6 dB 82 20%

64% to 96%

+12 dB 88 Instrument Qualification Results Horizontal Linearity Screen Height Linearity Amplitude Control Linearity Acceptable L-Acceptable E

Acceptable E_

Remarks FINAL Examiner Paul Valden Level Examiner N/ A Level Date Initials VI Initials N/A 9120/2002

\\<.ADE Level I/Ill Review I `%-f-Level

-f E?

Date I

I I

I Revision 3.

S..

OI---

0 10--0/ij

Farley Nuclear Plant Ultrasonic Instrument Qualification Record SHARED FNP-0-NDE-100.32 Southern Nuclear Operating Company istrument Sheet No.

S02F2L009 Manufacturer Model Serial No.

Staveley SONIC 136 136-911K Transducer Manufacturer Size Frequency Serial No.

KBA

.50 2.25 MHZ 009TNR Reference Standard Type Serial No.

Mini Angle Beam 4846 Horizontal Linearity Back Refl.

Signal Position Back Refl.

Signal Position 1

10 6

60 2

20 7

70 3

30 8

80 4

40 9

90 5

50 10 100 Screen Height Linearity Amplitude Ha 100 FSH 90 FSH 80 FSH 70 FSH 60 FSH Amplitude Hb 50 45 40 35 31 Amplitude Ha 50 FSH 40 FSH 30 FSH 20 FSH 10 FSH Amplitude Hb 25 20 15 10 4

Amplitude Control Linearity Indication Set at %

Indication Limits dB Control Change Instrument Indication of Full Screen

% of Full Screen

% of Full Screen 80%

32% to 48%

-6 dB 39 80%

16% to 24%

-12 dB 20 40%

64% to 96%

+6 dB 81 20%

64% to 96%

+12 dB 80 Instrument Qualification Results Horizontal Linearity Screen Height Linearity Amplitude Control Linearity Acceptable E-/

Acceptable E-Acceptable, Remarks FINAL Examiner Paul Valden Level Examiner N/A Level Date Initials II Initials N/A 9/20/2002 I,K.NDE Level 11/111 Review an

ýfUL Level Date

-:L

Juy, I

I I I Revision 3.

EXAMINATION

SUMMARY

FOR UNIT 2 INTERVAL 3 PERIOD 1 OUTAGE 1 DRAWING APRI-il00B REACTOR VESSEL FLANGE LIGAMENTS ITEM NO VOLUMERIC SURFACE VISUAL REMARKS NI NMI RI NI NRI RIM NIT NRI T RI 4 thrug9 X

28 thru 37 X

44 thru 56 X

s i

m m

v i

9 1

i i

B 0

1 1

ff

I

WESI INGSHUUSE NUCLEAR SERVICES DIVISION THREADS IN FLANGE ULTRASONIC EXAMINATION PLANT SYST./COMP.

EXAMINER Farley Reactor Vessel Q t 4t,4j UNIT 2

SKETCH PROCEDURE DATE APR1-1100 FNP-ISI-55, Rev 0 9-19-02 STRAIGHT BEAM SCAN EQUIPMENT TRANSDUCER DIRECTION 0 CALIBRATION CHECK INST. SIN SIN G19804(SP)

INITIAL TIME STAVELEY SIZE 1.0" 0330, 9-19-02 136-897K FREQ.

2.25 MHz ANGLE 00 REP. RATE 1K CALIBRATION

__REF EC ORSIGNAL SWEEP AMPLITUDE POSITION REJECT OFF LOCATION A

80%

1.8 DAMPING 500 OHMS B

60%

3.8 C

40%

6 6 FILTER 1

FINAL TIME LIN. CHECK SAT 0550, 9-19-02 SU CABLE 6' RG-174 CAL. BLOCK ALA-RV-6 THICKNESS 15" COUPLANT DEMIN WATER THERMOMETER SIN 48881 CAL. GAIN 40.4 dB TEMP.

88u F THREAD IDENT.

TEMP.

SCAN EXAMINATION SURFACE RESULTS REMARKS (STUD HOLE NUMBER)

LIMITATIONS NI RI 4 thru 9 1020 F YES NONE SMOOTH X

28 thru 37 1020 F YES NONE SMOOTH X

44 thru 56 1020 F YES NONE SMOOTH X

,*A

_ _z_

61

EXAMINATION

SUMMARY

FOR UNIT 2 INTERVAL 3 PERIOD 1 OUTAGE 1 DRAWING APR1-1200 REACTOR VESSEL INTERNALS ITEM NO VOLUMERIC SURFACE VISUAL REMARKS NI NRI RI NI NRI RI NI NPJ RI

Upper Internals x

-

I REACTOR VESSEL INTERNALS O2BIIHOO1 UPPER INTERNALS

1.

THERMOCOUPLE CONDUIT.

CONNECTIONS AND SUPPORT BRACKETS'ASSOCIATED WITH "INSTRUMENT PENETRATIONS ABOVE THE UPPER SUPPORT PLATES

2.

INSTRUMENTATION COLUMNS

3.

UPPER SUPPORT PLATE KEYWAYS (FOR HEAD ALIGNMENT PINS)

4.

FLOW MIXER DEVICES AND FASTENERS

5.

SUPPORT COLUMNS AND FASTENERS

6.

GUIDE TUBES (EXTERIOR ONLY)

AND FASTENERS

7.

UPPER CORE PLATE FUEL ASSEMBLY GUIDE PINS S.

UPPER CORE PLATE ALIGNMENT KEYWAYS AND FASTENERS

9.

UPPER CORE PLATE

10.

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

23.

24.

25.

LOWER INTERNALS (INTERIOR)

UPPER CORE PLATE ALIGNMENT KEYWAYS AND FASTENERS CORE BARREL FLANGE FLOW NOZZLES CORE BARREL AND VESSEL HEAD ALIGNMENT PINS FLANGE TO UPPER BARREL WELD UPPER BARREL TO LOWER BARREL MID-PLATE WELD UPPER CORE PLATE ALIGNMENT KEY BAFFLE BOLTING AND LOCKING DEVICES LOWER CORE PLATE SUPPORT COLUMN BOLTING LOWER CORE PLATE INSTRUMENT GUIDE TUBE NUT LOWER CORE PLATE ACCESS COVER BOLTING LOWER CORE PLATE FUEL ASSEMBLY GUIDE PINS LOWER INTERNALS (EXTERIOR)

IRRADIATION SPECIMEN BASKET ATTACHMENT WELDS OUTLET NOZZLE TO VESSEL INTERFACE SURFACES CORE BARREL RADIAL SUPPORT KEYS SECONDARY CORE SUPPORT KEYWAYS THERMAL SHIELD ATTACHMENTS

'VENDOF MANUA-U-2>t, VESSEL INTERIOR

26.

CORE BARR*EL RADIAL SUPPORT KEYWAYS

27.

VESSEL INSTRUMENTATION PENETRATIONS 28.*.

R. V. OUTLET NOZZLE/CORE BARREL INTERFACE SURFACES AND INNER RADIUS

ý7-21-97 HSK TL REVISED P El, 2EA 7R-V.95 DEo S'u"*h-* h" ompa

" services. Inc'. "for "

.3 __L ALABAMA POWER COMPANY DRAWIZGMAWR

".ET R-v JOSEPH M. FARLEY NUCLEAR PLANT 6

UNIT 2 A-356454 6

"ILLUSTRATIVE ONLY" T

CD

<1 LJLJ >

T APRI*-i*20 0

Ci C

PLANT:

PROCEDURE:

J.M. FARLEY FNP-ISI-88, REV. 1 UNIT:

DATE:

2 9/23/2002 INTERVAL:

PERIOD:

1OUTAGE:

EXAMINER:

REFERENCE DWGS:APR1-1200 EXAMINER:

COMPONENT RI R

KS EXAMINER COMPONENT LOCATION TAPE LOCATION I NRII I

REMARKS INITIALS Resolution Check Initial Wire or banding noted on the refuel pool floor near 180 degree Upper Core Plate Keyway Upper Core Plate Fuel Assembly Guide Pins Upper Core Plate Alignment Keyways and Fasteners Upper Core Plate Guide Tubes Support Columns, Flow Mixer and Fasteners Resolution Check Thermocouple Conduit Connections and Support Brackets Associated with Instrument Penetrations above the Upper Support Plates Instrumentation Columns Upper Support Plate Keyways (for Head Alignment Pins)

Black Connector noted on refuel pool floor located by Core Barrel Support Ring Leg nearest Upper Internals Stand Resolution Check Final 0 to 360 Degrees 0 to 360 Degrees 0 to 360 Degrees 0 to 360 Degrees 0 to 360 Degrees 0 to 360 Degrees 0 to 360 Degrees 0 to 360 Degrees 0 to 360 Degrees 0 to 360 Degrees 0 to 360 Degrees 10:26 10:33 10:33 Thru 11:30 11:32 11:37 Thru 12:49 11:16 12:50

,AA1c

/2-0-1 x

x x

x X

Acceptable Not in examination area Examined accessible areas Examined accessible areas Examined accessible areas Examined accessible areas Examined accessible areas Acceptable Examined accessible areas Examined accessible areas Examined accessible areas Examined accessible areas Examined accessible areas Examined accessible areas Not in examination area Acceptable

(

ý?Izzni P fl f

ff I

APPENDIX D Setup and Checkout of Remote Underwater Examination Vehicle (Mini Rover, E-Roy, or Equivalent)

Setup

1.

Attach the system console, hand controller cable, power cable, and tether to the Mini Rover.

2.

Connect unit to a standard power source (104-120 or 208-240 VAC, 960 watts maximum).

3.

Attach applicable cables to TV camera, lights, video tape recorder, TV monitor and system console.

4.

Turn on TV System.

5.

Test camera focus.

6.

Test Video Tape Recorder.

7.

Test camera lights.

NOTE: LIGHTS MUST NOT BE TURNED ON FOR MORE THAN 10 SECONDS WHEN OUT OF WATER.

8.

Test camera movement in the vertical plane. Movement should be approximately 450 above and 550 below the horizontal plane. Verify that the direct-reading compass and depth gauge can be viewed with the camera.

9.

Place Mini Rover or E-ROV into water and verify controlled movement in the horizontal and vertical plane. Maneuver vehicle around the perimeter of the reactor vessel.

10.

Checkout Complete.

41 7LLa 4Z 9-g 23 9 Z3o*

'39 2 3 1-22, 9.2 02.*

9-23,Z 2 9E3 302-Initial Date

APPENDIX E Underwater Television System Resolution Checkout Data Sheet Level II:

Date:

Plant:

T.V. Camera:

T.V. Monitor:

T.V. Lights:

Video Tape Recorder:

Resolution Standard:

SCI"-M.

FA4-L.(:7 u m 2

E. b\\ 2-CAhAQQ-A SN PAiJ Ac~r tIL.

ST A&,I At.i*

Resolution Standard Approximate Depth 2-4 4 "

Z-4"1 Distance

.1

-'-2

-'4 14 Angle (Degrees) v.j~t 4sý "0

415

,*4S -

Resolution Acceptable IES lIEs Examiner(s):

C.taAr 1.

2.

3.

4.

JA cýTem

?/-20Z

EXAMINATION

SUMMARY

FOR UNIT 2 INTERVAL 3 PERIOD 1 OUTAGE 1 DRAWING APRI-1300 REACTOR VESSEL CLOSURE HEAD ITEM NO VOLUMERIC SURFACE VISUAL -

REMARKS NI NRI RI NI NRI RI NI NRI RI PEN58 X

REACTOR VESSEL CLOSURE HEAD 02BIlH001

-CRDM WELD (TYP. 69 PLACES)

APRI-1300A

.0O SHROUD OPENINGS (TYP. 3 PLACES)

CLOSURE HEAD WELDS WELD #

= 6.25" REACTOR VESSEL Scs DRAVM "lu A-356454 4.6, K>;

I I It ci L

FtN.- -z -- M-0t;7

(,

Farley Nuclear Plant Liquid Penetrant Examination Record Unit i-Component Number 2

i APR1-1300-58 Thermometer MfglSer. No.

PTC 1 48890 Cal. Due Date 2/5/2003 Surface Temp.

94 o F CS SHARED I Procedure/Rev./TCN FNP-0-NDE-100 5 FNP-0-.iE-100.5 PT-F-FORM 001 Southern Nuclear Operating Company 1 6.0 I N/A Penetrant Materials Manufacturer Magnaflux Cleaner I Remover Penetrant Developer Sheet No.

S02F2P006 Type SKC-S SKL-SP SKD-S2 Page I of f Batch 02E05K 96J02K 02G07K Component Configuration

% of Length Coverage 100 Date CRD HOUSING WELDS

% of Area Coverage 100 9/26/2002 Nd.No. Results Dwell Time Indication temark NA NI 10 NA NA Primary Examiner ASNT Level Initials Joseph D Funyak II SNC NDE Level II/111 Assistant Examiner N/A Date Percentage of Code

A 1.,1-,b2" Coverage

[0o ASNT Level Initials Non-Technical Review N/A ANII Review Date q-z7C-~

Date Revision 6.

EXAMINATION

SUMMARY

FOR UNIT 2 INTERVAL 3 PERIOD 1 OUTAGE 1 DRAWING APR1-1300B REACTOR VESSEL STUDS, NUTS and WASHERS ITEM NO VOLUMERIC SURFACE VISUAL REMARKS NI NRI RI NI NRI RI NI NRI RI Sol x________

S14 X

S15 X

S24 x

S25 x

S27 x

S28 X

S29 X

S30 x

S31 x

S32 x

S51 x

S52 X

S53 x

S54 x

S55 x

S56 X

S57 X

S58 X

N01 x

N14 x

N15 x

N24 x

N25 x

N27 X

N28 X

N29 x

N30 x

N31 x

N32 X

N51 x

N52 x

N53 N54 x

N55 x

EXAMINATION

SUMMARY

FOR UNIT 2 INTERVAL 3 PERIOD 1 OUTAGE 1 DRAWING APRI-1300B REACTOR VESSEL STUDS, NUTS and WASHERS ITEM NO VOLUMERIC SURFACE VISUAL REMARKS NI NRI RI NI NRI RI NI NRI RI N56 x

N57 x

N58 x

W0 1 X

W14 x

W15 x

W24 X

W25 x

W27 x

W28 x

W29 x

W30 X

X IER-00I W31 X

W32 X

W51 X

W52 X

W53 X

W54 X

W55 X

W56 X

W57 X

W58 X

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Southern Nuclear Operating Company Sheet No.

S02F2U025 Paqe I of I NA Notes:

Examination/Limitation Remarks:

RPV Studs examined from the top No limitations Total Length Crown Width I Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) of Weld NA NA 5 (L)

NA 2 (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Primary Examiner Level T;*tials Assistant Examiner Level Non-Technical Review Date Richard Money i 11 Andrew Mixon II

//a

- oe)

SNC NDE Level 11/ 11 Review Date Percentage of ANII RevewDate q 2-

) a-Code Coverage u

/

/Revision 4 0

(7 Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Southern Nuclear Operating Company Unit Sketch/Component Number Date Sheet No.

2 APR1-1300-S14 9/2112002 S02F2U026 Page J f

of__

Procedure/Rev./TCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 40 N/A Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone I Calibration Zone 2 Calibration Make/Model Panametrics I Epoch II Transducer Mfg.

Panametrics Cal. BIk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep NoModel No.

A S

Cal. Temp 80 F

Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Zone I Zone 2

5 80 38 NA

3 80 80 NA SizeINo. 50 Shape I Round Cal. In 11:1500AM Reference 61 66 Scanning 67 Frequency/Mode 10.0 / Long Cal. Chk.

1130 "Puser HIGH A" Dimension NA Cal. Out 1 00 00 PM Frequency 6 Rep Rate FIX Nom Angle 0

° Meas Angle NA ° Ref. Bk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54.25 and #5 at 7 6" are OD Notches Mode P/E Filter ON Cable Type /No. Conn. RG 174 / 0 Reflector/dB NA

/ NA Damping 400 Reject OFF Cable Length 6'

AmplSweep NA

% NA Comp Temp.

84 Configuration -

REACTOR VESSEL STUDS __Wo Loc.

NA LoLoc NA Scan Results

.d Length Ref. Measurements ThicknessC/L__

Notes:

Dir.

-A LI Lmax

,2 Wmax Smax NI

~

R L-

-m

__C2-_

0.

NA Examination/Limitation Remarks:

RPV Studs examined from the top. No limitations Total Lennth CrownWn,4.ith of...

Wel N.....

Length or weld Examinea Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) of Weld NA _

NA 5 (L)

NA 2 (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Primary Examiner Level a

Assistant Examiner Level i

Non-Technical Review Date Richard Money

,l Andrew Mixon I,

P ý q-L-Oa SNC NDE Le 1l/Ill Date Percentage of ANII Review Date T

4.-

?-277-c Code Coverage

-7

-/

n'/Z 7/, 7_

Revision 4 0

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Southern Nuclear Operating Company Unit SketchlComponent Number Date Sheet No.

2 APR1-1300-S15 9/21/2002 S02F2U027 Page t of (

ProcedurelRev./TCN CouplantiBatch No.

I ThermometerSNlCal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 4 0 N/A Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone I Calibration Zone 2 Calbration Make/Model Panametrics / Epoch II Transducer Mfg.

Panametrics Cal. Blk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep No.

max Wmax Model No.

A111S Cal. Temp 80 OF Refl.

Amp.

Div.

Refl.

Amp.

Div.

5 80 38 NA

3 80 80 NA SizelNo. 50 Shape I Round Cal. In 11.1500AM.......

Reference 61 66 Frequency/Mode 10 0 / Long.

Cal. Chk.

1130 Scanning 67 73___

Pulser HIGH "A" Dimension NA Cal. Out 1 00 00 PM Frequency 6 Rep Rate FIX Nom Angle 0 Meas Angle NA Ref. 13k. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54.25 and #5 at 7 6" are OD Notches Mode P/E Filter ON Cable Type /No. Conn.

RG 174 / 0 Reflector/dB NA

/NA Damping 400 Reject OFF Cable Length 6'

AmplSweep NA

% NA Comp Temp.

84 Configuration -

REACTOR VESSEL STUDS We Loc.

NA LoLoc.

NA Scan Results 11 nd -

Length Ref. Measurements ]

Thickness L

Notes:

-rDir.

NI_l NRI

[

RI INO.DCL LI Lmax L2 Wmax Smax I"<-

CL

->1" 0E NA Examination/Limitation Remarks:

RPV Studs examined from the top No limitations.

I Oral Length of Weld NA Primary Examiner Richard Money SNC NDE Level I/111 Crown widtn Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L)

NA 5 (L)

NA 2 (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Level s-AndewMlsoAssistant Examiner Level la Non-Technical Review Date II ~Andrew Mixon 11Y~

~AA~?L q-)..q-o.

eview Date Percentage of ANII Review Date

'ev

ewr, v-"

CodeCoverage

"*%v o/Z7/-4 L

7 Revision 4 0

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-1 00.39 Southern Nuclear Operatingi Company Unit Sketch/Component Number Date ISheet No.

2 APR1-1300-S24 9/21/2002 JS02F2U028 Page _L of

_Procedure/Rev./TCN Couplant/Batch No.

FThermometerSNlCal Due Date Linearity Sheet No.

FNP-0-NDJE-100 39 4.0 N/A Ultragel 11 1

01125 48881 2/5/2003 S02F2L-0110 Instrument Search Unit

Calibration Block Zone I Calibration Zn airto Make/Model Panametrics I Epo ch 11 Transducer Mfg.

Panametrics Cal. Bik. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal ISweep Cal.

Signal Sweep N..Model No.

AlliS Cal. Temp 80 'F Refi.

Amp.

Div.

Wmax Refl.

Amp.

Div. P Wmax Zone I Zone 2

5 80 38 NA

3 80 8 0 NA_

Size/INo..50 Shape I Round Cal. In 11:1500 AM Reference 61 66 Freuecy/od 100 LngCa.

hk 13 Scanning 67 Frqec/oe173Ln a.Ch.

13 Pulser HIGH "A" Dimension NA Cal. Out 1.00 00 PM Frequency 6 Rep Rate FIX Nom Angle 0 Meas Angle NA *Ref.

B1k. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7 6" are OD Notches.

Mode P/E Filter ON Cable Type /No. Conn.

RG 174 / 0 Reflector/dB NA I' NA Damping 400 Reject OFF ICable Length 6'

Amp/Sweep NA

% NA CopTm.

84 Cniuaon-REACTOR VESSEL STUDS WLo.NA Loo.NA Scan Results Ind Length_

Ref. Measurements Thickne~ss Notes:

Dir.j N]

_NRI R,

NO.

DAC LI Lmax L2 Wmax Smax I"-.

CIL

->I,.

0.

.i I

NA Exam ination/Lim itation Remarks:

RPV Studs examined from the top No limitations T,~~I~,G

I......Ir 11 611

~~~~

Crow M*~*

'IUI VUM Total Length of Weld Examir of Weld NA NA 5 (L)

NA 2 (L)

NA Primary Examiner Level Richard Money 11 SNC NDE Level il/11ll ie ied Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Assistant Examiner Level Non-Technical Review Date Andrew Mixon 11 (kL 44_t..

Q~ y Date Percentage of ANll1v Fie w 0Date ajý

- ?Code Coverage /06

-7/z 1-z Revision 4 0

C Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Southern N uclear eratin Cnnn Unit Sketch/Component Number Date Sheet No.

2 APR1-1300-S25 9/21/2002 S02F2U029 Page_

of /

Procedure/Rev./TCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100.39 40 N/A Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone 1 Calibration Zone 2 Calbration Make/Model Panametrics / Epoch II Transducer Mfg.

Panametrics Cal. Blk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep NModel No.

F Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Moe N.

A111S Cal. Temp 80 Zonel Zone 2

5 80 3.8 NA

3 80 80 NA SizelNo. 50 Shape I Round Cal. In 11:15.OOAM Reference 61 66 Scanning 67 Frequency/Mode 10 0 /Long Cal. Chk.

1130 Pulser HIGH "A" Dimension NA Cal. Out 1:00 00 PM

.[........

Frequency 6 Rep Rate FIX Nom Angle 0 Meas Angle NA ° Ref. BIk. No.

N/A Calibration Remarks:

Calhbration reflectors #3 at 54 25 and #5 at 7.6" are OD Notches Mode P/E Filter ON Cable Type /No. Conn. RG 174 / 0 ReflectorldB NA

/ NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA Comp Temp.

84

°l Configuration -

REACTOR VESSEL STUDS Wo Loc.

NA NA i-d

-- - Lo Loc.---

NA___-

Scan Results" nd-%

Length Ref. Measurements Thickness Notes:

Dir.

NI NRI R,

NO-DAC LI Lmax L2 Wmax Smax C>ý"

00 NA ExaminationlLimitatlon Remarks:

RPV Studs examined from the top No limitations.

Total Lenath tiCrnwnW*Netth

.i ow; =

L~~I 0....

xet fPreniua Sas(W xen fPaallScn L T o a L e g t....

W d t 1

........ O d L e n g t h o r Wo.

e l d Ex am in e d E x t en t o f P er p en d i cu la r S c an s ( W E x t en t o f P a ra lle l S c an s ( L) of Weld NA NA 5 (L)

NA 2 (L)

NA 7and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Primary Examiner Level Assistant Examiner Level Non-Technical Review-Date Richard Money II Andrew Mixon II Akah V.

SNC NDE Level Il/Il1 7vew ~Date Percentage of ANII ReviewDate V

Code Coverage (o00

/7 Revision 4 0

C Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Southern Nuclear Operating Company Unit Sketch/Component Number Date Sheet No.

2 APR1-1300-S27 9/21/2002 S02F2U030 PageL of

-L Procedure/Rev./TCN CouplantlBatch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100.39 4.0 N/A Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone I Calibration Zone 2 Calibration Make/Model Panametrcs / Epoch II Transducer Mfg.

Panametncs Cal. Bik. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep No.

Wmax e'.

Wmax Model No.

A11S Cal. Temp 80 °F Refl.

Amp.

Div.

Refl.

Amp.

Div.

Zone I Zone 2

5 80 38 NA

3 80 80 NA Size / No..50 Shape I Round Cal. In 11.15 00 AM Reference 61 66 Frequency/Mode 10.0/ Long.

Cal. Chk.

1130 Scanning 67 73 Pulser HIGH "A" Dimension NA Cal. Out 1 00 00 PM Frequency 6 Rep Rate FIX Nora Angle 0 Meas Angle NA Ref. BIk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54.25 and #5 at 7 6" are OD Notches.

Mode PIE Filter ON Cable Type /No. Conn. RG 174 / 0 Reflector/dB NA

/ NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA Camp Temp.

84 Configuration -

REACTOR VESSEL STUDS We Loc.

NA Lo Loc.

NA Scanr Reults..

Length Ref. Measurements Thickness Notes:

i 1

DAC

... -L;x L2..

Wmax Smax CIL 0.,

NA Examination/Limitation Remarks:

RPV Studs examined from the top. No limitations

,uta e-ng" CL.rown Width T

of Weld NA I NA Primary Examiner Richard Money SNC NDE Level1ll/l1l Rie

otal Length of Weld Examin (L)

NA 2 (L)

NA Level ed Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Assistant Examiner Level lNon-Technical Review Date Andrew Mixon 0I L~

yA~~

Date Percentage of ANII Review Date v

Code Coverage I7 L,

/Z7/-Z Revision 4 0

C Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED

(

FNP-0-NDE-100.39 Southern Nuclear Operatina Company Unit Sketch/Component Number Date Sheet No.

2 APR1-1300-S28 9/21/2002 S02F2U031 Page _

of /

Procedure/Rev./TCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100.39 40 N/A Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone I Calibration Zone 2 Calbration Make/Model Panametncs / Epoch II Transducer Mfg.

Panametrics Cal. BIk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep No.

I i

Model No.

A111S Cal. Temp 80 'F Refl.

Amp.

DIV.

Wmax Refl.

AMP.

Div.

Wmax Zonel Zone 2

5 80 38 NA

3 80 80 NA Size/No. 50 Shape / Round Cal. In 11:15.OOAM Reference 61 66 Scanning 67 Frequency/Mode 10 0 / Long Cal. Chk.

1130 Pulser HIGH "A" Dimension NA Cal. Out 1"00:00 PM Frequency 6 Rep Rate FIX Nom Angle 0 Meas Angle NA ° Ref. BIk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54.25 and #5 at 7 6" are OD Notches Mode P/E Filter ON Cable Type /No. Conn.

RG 174 / 0 Reflector/dB NA

/ NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA Comp Temp.

84

°11 Configuration -

REACTOR VESSEL STUDS Wo Loc.

NA LoLoc.NA Scan~

Results md

%Lnt

~Ref.

Measurements jThickness

]Nts Dir.J l

NRI RI No. IDAC LI Lmax L2 Wmax Smax I.."<-

CIL

-1

0.

NA Examination/Limitation Remarks:

RPV Studs examined from the top No limitations.

Tnotl I n th f,

rI*.,A#-*

I U I....

- I..

..... Total Length o of Weld NA NA 5 (L)

NA Primary Examiner Level Richard Money II SNC NDE Level Il/111 Review fWeld 2 (L) I Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA

ale Assistant Examiner Level Non-Technical Review Date SAndrew Mixon II q-,aq-oi Date Percentage of ANII Date q/.7*.ý*

Code Coverage

._0 Revision 4 0

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Southern Nuclear Oneratina Comnoanv Unit Sketch/Component Number Date Sheet No.

2 APR1-1300-S29 9/21/2002 S02F2U032 Page __

of Procedure/Rev.ITCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 40 NIA Ultragel II I

01125 48881 2/512003 S02F2L010 Instrument Search Unit Calibration Block I

Zone I Calibration Zone 2 Calibration Make/Model Panametrics I Epoch II Transducer Mfg.

Panametrics Cal. BIk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55.75" Cal.

Signal Sweep Cal.

Signal Sweep N.Model No.

AlS Cal. Temp 80 F

Refl.

Amp.

Div.

Wmax Reft.

Amp.

Div.

Wmax Zone 1 Zone 2

5 80 38 NA

3 80 8 0 NA Size/No. 50 Shape I Round Cal. ln 11.1500AM Reference 61 66 Frequency/Mode 10 01 Long.

Cal. Chk.

1130 Scanning 67

73.

Pulser HIGH "A" Dimension NA Cal. Out 1 00 00 PM Frequency 6 Rep Rate FIX Nom Angle 0

° Meas Angle NA Ref. BIk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54.25 and #5 at 7 6" are OD Notches Mode PIE Filter ON Cable Type/No. Conn. RG 174 / 0 Reflector/dB NA I NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA Comp Temp.

84

°If Configuration-REACTOR VESSEL STUDS We Loc.

NA LoLoc.

NA Scan Results TInd Length Ref. Measurements Thickness ___-

Notes:

Dir.

NI NR, RI J

N DAC LI Lmax L2 Wmax Smax I"<-

C/L

>I.

0.

NA Examination/Limitation Remarks:

RPV Studs examined from the top No limitations.

Total Length Crown Width 1 Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) of Weld NA NA 5 (L)

NA 2 (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Primary Examiner Level

I*tials Assistant Examiner Level Non-Technical Review Date Richard Money 1l Andrew Mixon 1,

q

-A(

-o.

02.

SNC NDE Level il/Ill Review Date Percentage of ANII Review Date Code Coverage

/

Revision 4 0

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Unit Sketch/Component Number Date Sheet No.

2 APR1-1300-S30 9/21/2002 S02F2U033 Page_ L of (

Procedure/Rev.iTCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 40 N/A Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit I

Calibration Block Zone I Calibration Zone 2 Calibration Make/Model Panametrics / Epoch 11 Transducer Mfg.

Panametrics Cal. B6k. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep N°Model No.

AlS Cal. Temp 80 *F Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Zone I Zone 2

5 80 3.8 NA

3 80 8 0 NA SizeINo. 50 Shape I Round Cal. In 11:1500AM -

Reference 61 66 1__

Frequency/Mode 10 0 / Long Cal. Chk.

1130 Scanning 67 73

\\_---

Pulser HIGH "A" Dimension NA Cal. Out 1:00.00 PM Frequency 6 Rep Rate FIX Nom Angle 0 Meas Angle NA ° Ref. B6k. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7.6" are OD Notches.

Mode P/E Filter ON Cable Type/No. Conn. RG 174 I 0 ReflectorldB NA

/ NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA 84 ot.U,,,uraidUU REACTOR VESSEL STUDS w° Loc.

NA Lo Loc.

NA Scani Results

]Ind Length Ref. Measurements Thickness Notes:

_Dir.

NI

-R

-I No.

DAC Li Lmax L2 I

Wmax Smax 0"

NA Examination/Limitation Remarks:

RPV Studs examined from the top No limitations Total Length Crown Width Total Length of Weld Examined Extent of Perpendicular Scans (W) j Extent of Parallel Scans (L) of Weld NA NA 5(L)

NA 2(L)

NA 7and8(W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Primary Examiner Level ts Assistant Examiner Level ia Non--Technical Review Date Richard Money II Andrew Mixon II q"

tl-Vc-D_

SNC NDE Level Il/111 Review Date Percentage of ANII Review Date ot.1-0 Z_ Code Coverage fOL) 7K i-,

Revision 4 0

C Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Southern Nuclear Operating Company Unit Sketch/Component Number Date Sheet No.

2 APRI-1300-S31 9/21/2002 S02F2U034 Page 1 of _

Procedure/Rev./TCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 40 NIA Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit I

Calibration Block Zone I Calibration Zone 2 Calibration Make/Model Panametrics / Epoch I1 Transducer Mfg.

Panametrics; Cal. Blk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep No.

Model No.

A111S Cal. Temp 80 'F Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Zonel Zone 2

5 80 38 NA

3 80 80 NA SizeINo. 50 Shape / Round Cal. In 11:1500AM..............

Reference 61 66 Scanning 67 Frequency/Mode 10.0 / Long.

Cal. Chk.

1130 Pulser HIGH "A" Dimension NA Cal. Out 10000 PM Frequency 6 Rep Rate FIX Nom Angle 0

° Meas Angle NA Ref. Bk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7.6" are OD Notches Mode P/E Filter ON Cable Type /No. Conn. RG 174 / 0 Reflector/dB NA

/NA Damping 400 Reject OFF Cable Length 6'

AmplSweep NA

% NA C;omp Temp.

84 C

Configuration -

REACTOR VESSEL STUDS IW Loc.

NA Lo Loc.

NA Scan Results nd o

Length J

Ref. Measurements Thicess

]...Notes:

DDA NI LINo.

Lmax L2 Wmax Smax I"<-

C/L

->1",

0" NA Examination/Limitation Remarks:

RPV Studs examined from the top No limitations Total Length Crown Width Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) of Weld NA NA 5(L)

NA 2(L)

NA 7 and 8(W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Primary Examiner Level -'I-nitials Assistant Examiner Level Non-Technical Review Date Richard Money I11 Andrew Mixon II ku.

J q-q-oL.

SNC NDE Level 11 Review Date Percentage of ANII iew Date "Iq20* "

Code Coverage

(

?vsft/"7/-4 7

ILI Revision 4 0

C Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Southern Nuclear ODeratina ComDanv Unit Sketch/Component Number Date Sheet No.

2 APR1-1300.S32 9/21/2002 S02F2U035 Page I of Procedure/Rev./TCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 40 N/A Ultragel II I

01125 48881 2/5/2003 S02F2LO10 Instrument Search Unit Calibration Block Zone 1 Calibration Zone 2 Calibration MakelModel Panametrics I Epoch II Transducer Mfg.

Panametrics Cal. Bk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep No.

N.Model No.

A1S Cal. Temp Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Zonel Zone 2

5 80 38 NA

3 80 80 NA SizelNo. 50 Shape I Round Cal. In 11:1500 AM Reference 61 66 Scanning 67 FrequencylMode 10 01Long.

Cal. Chk.

1130 Pulser HIGH "A" Dimension NA Cal. Out 1 00 00 PM Frequency 6 Rep Rate FIX Nom Angle 0 Meas Angle NA Ref. Bk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7.6" are OD Notches.

Mode PIE Filter ON Cable Type /No. Conn.

RG 174 / 0 Reflector/dB NA

/ NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA 84

°1 onU REACTOR VESSEL STUDS Wo Loc.

NA Lo LOC.

Di'r.J N, NR, RI RL _No.DA*C L

L Lma& x...-

L2-Wmax Smax I"<-

C/k

->1"

~_

0° K, NA Exam ination/Limitatio n Remarks:

RPV Studs examined from the top. No limitations Total Length Crown Width Total Length of Weld Examin of Weld NA NA 5(L)

NA 2(L)

NA Primary Examiner Level Initials Richard Money II SNC NDE.Le 11/1,, Ivi ý9 ied I Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) 7 and 8 (W) NA j5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Assistant Examiner Level Non-Technical Revmew Date Andrew Mixon IIA Date Percentage of ANII Review Date q.""*-7 Z-Code Coverage(

0 7/

Revision 4 0

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Unit SketchSComponent Number Date Sheet No.

2 Ak1300hp51 9/21/2002 S02F2UN36 PageDt ofS 2cAeRe1.rrcN S

Cou9/21/20 0

DuLFte "LnePagehetof Procedure-Re0TCN Coup3ant/Batch No.

ThermometerSNICal Due Date FLnearity Sheet N0.

FNP-0-NDE-100 39 40 N/A Ultragel 11 I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone I Calibration Zone 2 Calibration MakelModel Panametrics / Epoch II Transducer Mfg.

Panametrics Cal. BIk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep N.Model No.

AIS Cal. Temp 80 Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Zone I Zone 2

5 80 38 NA

3 80 80 NA SizelNo. 50 Shape ! Round Cal. In 11:1500AM Reference 61 66 Scanning 67 Frequency/Mode 10 0 / Long Cal. Chk.

1130 Pulser HIGH "A" Dimension NA Cal. Out 1:00 00 PM Frequency 6 Rep Rate FIX Nom Angle 0 Meas Angle NA Ref. B6k. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7 6" are OD Notches Mode PIE Filter ON Cable Type /No. Conn. RG 174 1 0 Reflector/dB NA

/NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA Comp Temp.

84

°d Configuration -

REACTOR VESSEL STUDS

__We

Loc, NA Lo LocNA scaRe

__-d...

n1%

-Le-ngth Ref. Measurements Thickness Notes:

Scaq F

-i I--

IS Dir.. _10R DAC LI Lmax L2 Wmax Smax CI"<

C/L......

0-NA Examination/Limitation Remarks:

RPV Studs examined from the top. No limitations Total Length 1Crown Width Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) of Weld NA NA 5(L)

NA 2(L)

NA 7and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Primary Examiner Level n

Assistant Examiner Level Non-Technical Review Date Richard Money "I

Andrew Mixon 11

-v evrw q;a Noa RteL(0o SNC NDE Level Il/ II Rve Date Percentage of ANII Re Date "W

Revs-0' 21 Code Coverage 7/Z 7/*o27 Revision 4 0

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED

(..

3 FNP-0-NDE-1 00.39 Southern Nuclear Ooeratina Comnanv Unit Sketch/Component Number Date Sheet No.

2 APRI-1300-S52 9/21/2002 S02F2U037 Page_

of L

Procedure/Rev.rTCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 40 N/A Ultragel 1I 01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone 1 Calibration Zone 2 Calibration Make/Model Panametrics / Epoch I1 Transducer Mfg.

Panametrics Cal. Bik. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep el N°F Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Model No.

Al1iS Cal. Temp 80

___+/-___

___+/-

Zonel Zone2

5 80 38 NA

3 80 80 NA Zone 6 66 Size / No..50 Shape I Round Cal. In 11 15 00 AM...

R e fe re n c e 6 1 6 6.

Scanning 67 Frequency/Mode 10 0 / Long Cal. Chk.

1130 "Pulser HIGH "A" Dimension NA Cal. Out 1 00 00 PM Frequency 6 Rep Rate FIX Nom Angle 0

° Meas Angle NA Ref. BIk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7 6" are OD Notches Mode PIE Filter ON Cable Type /No. Conn.

RG 174 / 0 Reflector/dB NA

/ NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA Comp Temp.

84 CFonfiguratlon -

REACTOR VESSEL STUDS Wo Loc.

NA LoLoc.NA can ResuLts I.d

,,Length Ref. Measurements Thickness

.Notes:

S NI NRI R,

NO. DAC LI Lmax L2 Wmax Smax

>r 0

NA Examination/Limitation Remarks:

RPV Studs examined from the top No limitations Totltenal lLenathk

-r--wn W*i-I..................

___,O

_erenicuarScns W)j Etet f.....e.Scns(.

Toa

- Crw Iota, Length or Weld E-xamined Extent of Perpendicular Scans (W) iExtent of Parallel Scans (L) of Weld NA i

NA 5 (L)

NA 2 (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Primary Examiner Level t

Assistant Examiner Level Non-Technical Review Date Richard Money

,1 Andrew Mixon 1,

U" O IJu, q-aq-) 7z SNC NDE Level Il/1l RDate Percentage of ANII ReviewDate

'3 J

Code Coverage i-0

-'/Z.--/eso, Revision 4 0

C Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Southern Nuclear Operating Company Unit SketchlComponent Number Date Sheet No.

2 APR1-1300-S53 9/21/2002 S02F2U038 Pagej_

of L Procedure/Rev./TCN Couplant/Batch No.

ThermometerSNICal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 4 0 N/A Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone I Calibration Zone 2 Calibration Make/Model Panametrics / Epoch II Transducer Mfg.

Panametrics Cal. BIk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55.75" Cal.

Signal Sweep Cal.

Signal Sweep No.

mxWa Model No.

All1S Cal. Temp 80 OF Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Zonel Zone 2

5 80 3.8 NA

3 80 80 NA Size I No..50 Shape I Round Cal. In 11:15 00 AM Reference 61 66 Frequency/Mode 10 0 / Long Cal. Chk.

1130 Scanning 67 73 "HIGH "A" Dimension NA Cal. Out 1 00 00 PM Pulser HIGH Frequency 6 Rep Rate FIX Nom Angle 0 o Meas Angle NA Ref. Bk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7 6" are OD Notches Mode P/E Filter ON Cable Type/No. Conn. RG 174 / 0 ReflectorldB NA

/ NA Damping 400 Reject OFF Cable Length 6'

AmplSweep NA

% NA Comp Temp.

84

[1 Configuration -

REACTOR VESSEL STUDS We Loc.

NA Lo Loc.

NA Scan Results _

Lengtmh Ref. Measurementsma Thlcke__

Notes:

Dir.

Ni NR, RI R

No.lDAC I

Lmax L2 Wmax Smax C/L

>I"

0.

NA Examination/Limitation Remarks:

RPV Studs examined from the top. No limitations.

I Ulda LenILI of Weld NA Primary Examiner Richard Money SNC NDE Level IlI1 Grown Widt Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L)

NA 5 (L)

NA 2 (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Level Assistant Examiner Level Non-Technical Revmw Date II

\\...

Andrew Mixon II UTq" Date Percentage of ANII Review Date

--[/b

-"2. Code Coverage (00

-71, Z Revision 4 0

C Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED FNP-0-NDE-100.39 Southern Nuclear Operating Company Unit Sketch/Component Number Date Sheet No.

2 APRI-1300-S54 9/21/2002 S02F2U03g Page 1 of Procedure/Rev./TCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 40 N/A Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone I Calibration Zone 2 Calibration Make/Model Panametrics / Epoch II Transducer Mfg.

Panametrics Cal. BIk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55.75" Cal.

Signal Sweep Cal.

Signal Sweep No.I IoModel No.

AlS Cal. Temp 80 F Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Zonel Zone2

5 80 38 NA

3 80 8 0 NA SizelNo..50 Shape I Round Cal. In 11 1500 AM Reference 61 66 Frequency/Mode 10 0 / Long Cal. Chk.

1130 Scanning 67 73..

Pulser HIGH "A" Dimension NA Cal. Out 1 00 00 PM Frequency 6 Rep Rate FIX Nom Angle 0 o Meas Angle NA Ref. BIk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7 6" are OD Notches Mode P/E Filter ON Cable Type /No. Conn. RG174 / 0 Reflector/dB NA

/ NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA Comp Temp.

84 Configuration -

REACTOR VESSEL STUDS Wo Loc.

NA LoLoc.

CofN NA Sca Re ut I

d I%__

Le gh oL c

Scan' Results i I

-n Length

] Ref. Measurementsi Thickness Notes:

Dir.

NI J NRI RI N.. DAC LI Lmax L2 Wmax Smax 1<-

CIL

->1" 0° NA Examination/Limitation Remarks:

RPV Studs examined from the top No limitations Total Length Crown Width Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) of Weld NA NA 5 (L)

NA 2 (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA rrimary -xamminer Level

\\lfiEuals l

ASSistant Examiner Level Richard Money II l Andrew Mixon 11 SN DE Level-If/1 RebDate Percentage of q,'1-c.-_

I Code Coverage (o v Non-Technical Review ANII Review Date q.-,7q-o~

Date Revision 4 0

Farley Nuclear Plant Ultrasonic Calibration and Examination Record C

SHARED C

FNP-0-NDE-100.39 Southern Nuclear Operatinq Company Unit SketchlComponent Number Date Sheet No.

2 APRI-1300-S55 9/21/2002 S02F2U040 Page I of /

Procedure/Rev./TCN CouplantiBatch No.

ThermometerSN/Cal Due Date Linearlty Sheet No.

FNP-0-NDE-100 39 40 N/A Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone I Calibration Zone 2 Calbration Make/Model Panametrics I Epoch II Transducer Mfg.

Panametrics Cal. BIk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep No.

No.Model No.

A S

Cal. Temp 80 F

Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Zonel Zone 2

5 80 38 NA

3 80 80 NA Size I No..50 Shape I Round Cal. in 11:15 00 AM Reference 61 66 Scanning 67 Frequency/Mode 10 0 / Long Cal. Chk.

1130 Pulser HIGH "A" Dimension NA Cal. Out 1 00 00 PM Frequency 6 Rep Rate FIX Nom Angle 0 Meas Angle NA Ref. BIk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7 6" are OD Notches Mode PIE Filter ON Cable Type /No. Conn. RG 174 / 0 Reflector/dB NA

/ NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA CompTemp.

84 Configuration-REACTOR VESSEL STUDS Wo Loc.

NA NA Sca Results

~n Thickness___

Scan Results T

-nd -_D.

Lengtih

-. Ref. Measurements

--No-T-hicness N

Dir.

NI NRI

[ RI 1

No.

DAC LI Lmax L2 Wmax Smax l 1-<-

CIL-_

_o 0° NA Examination/Limitation Remarks:

RPV Studs examined from the top No limitations Total Length I Crown Width i Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) of Weld NA NA 5 (L)

NA 2 (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA I

l.....

M

,SiS*

a n: Examiner Level Richard Money II Andrew Mixon II SNC NDE Level 11/11 Review Date Percentage of

...- '1 -"61 Code Coverage Non-Technical Review Date ANII Review Date Revision 4 0

K Farley Nuclear Plant Ultrasonic Calibration and Examination Record SA, SHARED C

FNP-0-NDE-1 00.39 South.rn.Nuclear...ratrna Com

-an Unit Sketch/Component Number Date Sheet No.

2 APR1-1300-S56 9/21/2002 S02F2U041 Page (

of I Procedure/Rev./TCN CouplantlBatch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 40 N/A Ultragel II 01125 48881 215/2003 S02F2L010 Instrument Search Unit

-Calibration Block Zone I Calibration Zone 2 Calibration Make/Model Panametrics / Epoch II Transducer Mfg.

Panametrics Cal. Bk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep No.Model No.

A S

Cal. Temp 80 F

Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Zone I Zone 2

5 80 38 NA

3 80 80 NA Size / No..50 Shape I Round Cal. In 11:15 00 AM Reference 61 66 Scanning 67 Frequency/Mode 10 0 / Long Cal. Chk.

1130 Pulser HIGH "A" Dimension NA Cal. Out 1'00.00 PM Frequency 6 Rep Rate FIX Nom Angle 0 Meas Angle NA Ref. BIk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7 6" are OD Notches.

Mode P/E Filter ON Cable Type /No. Conn. RG 174 / 0 Reflector/dB NA

/ NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA C~mp Tmp" 84

C~nlgurat~n" IWo, Loc.

ooN Comp Temp.

84 Configuration-REACTOR VESSEL STUDS NA Lo Lo.

NA Scan Results In-d Length Ref. Measurementsj Thickness

........:Notes:

Dir.

NI NRI IR, No-DAC LI Lmax L2 Wmax Smax il<-

C/L....

0,

NA Examination/Limitation Remarks:

RPV Studs examined from the top. No limitations Total Length Crown Width Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) of Weld NA NA 5 (L)

NA 2 (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Exam,,,r Level A

-ssistant Examiner Level iFal.

Non-Technical Review Richard Money II Andrew Mixon 11_

SNC NDE Level 111111 Rev Date

--P of-4*

-L Iat o

Percen tag e of A N 1 1 R e w

Date S......__-_4 -O

Date Revision 4 0

Farley Nuclear Plant Ultrasonic Calibration and Examination Record S

SHARED C

FNP-0-NDE-100.39 Southern Nuclear Operating Company Unit Sketch/Component Number Date Sheet No.

2 APR1-1300-S57 9/21/2002 S02F2U042 Page l_ of Procedure/Rev.ITCN Couplant/Batch No.

ThermometerSNICal Due Date Linearity Sheet No.

FNP-0-NDE-100.39 40 N/A Ultragel II I

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block Zone I Calibration Zone 2 Calibration Make/Model Panametrics / Epoch II Transducer Mfg.

Panametrics Cal. Blk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55.75" Cal.

Signal Sweep Cal.

Signal Sweep No.

F Refl.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Model No.

A111S Cal. Temp 80 1FRf

_Ap Div.

Rf Ami Zone I Zone 2

5 80 38 NA

3 80 8 0 NA SizelNo..50 Shape I Round Cal. In 11"500AM Reference 61 66 Scanning 67 73 Frequency/Mode 10.0/Long.

Cal. Chk.

1130 "Pulser HIGH "A" Dimension NA Cal. Out 1 00 00 PM....

Frequency 6 Rep Rate FIX Nom Angle 0 Meas Angle NA ° Ref. Blk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54.25 and #5 at 7 6" are OD Notches Mode P/E Filter ON Cable Type /No. Conn. RG174 / 0 Reflector/dB NA

/NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA Comp Temp.

84 Configuration -

REACTOR VESSEL STUDS w° Loc.

NA L

NA Scan Results

_.In -

Length hRef" Measurements hickness Notes:

Dir.

NI NRI RI I j DAC L1__

Lmax-L2-Wmax Smax I--<

C/L 0o

-NA Examination/Limitation Remarks:

RPV Studs examined from the top No limitations Total Length crown Width Total Length of Weld Examined of Weld NA NA 5(L)

NA 2(L)

NA 7and 8 (W) NA Extent of Perpendicular Scans (W) 1 Extent of Parallel Scans (L) 5-From NA to NA 2-From NA to NA From (5) NA to (2) NA Primary Examiner Level Richard Money II SNCNDE Level 111111 Review Assistant Examiner Level

\\

-. ia.. Andrew Mixon II Date Percentage of

~ ~

~47~

Code Coverage P

) 1 Non-Technical Review ANII Review Date Date Revision 4.0 I

C Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHARED C

FNP-0-NDE-100.39 Southern Nuclear Operating Company Unit Sketch/Component Number Date Sheet No.

2 APR1-1300-S58 9/21/2002 S02F2U043 Page _

of Procedure/Rev/TCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 39 40 N/A Ultragel II

/

01125 48881 2/5/2003 S02F2L010 Instrument Search Unit Calibration Block-Zone 1 Calibration Zone 2 Calibration Make/Model Panametrics / Epoch II Transducer Mfg.

Panametrics Cal. BIk. No ALA-36 Serial 91043406 Serial No.

239864 Thickness 55 75" Cal.

Signal Sweep Cal.

Signal Sweep No.Model No.

A1S Cal. Temp 80 °F Refi.

Amp.

Div.

Wmax Refl.

Amp.

Div.

Wmax Zone I Zone2

5 80 38 NA

3 80 8 0 NA SizeINo..50 Shape I Round Cal. In 11.1500AM......

Reference 61 66 Frequency/Mode 10 0 / Long Cal. Chk.

1130 Scanning 67 73 Pulser HIGH "A" Dimension NA Cal. Out 1 00 00 PM Frequency 6 Rep Rate FIX Nomn Angle 0

°Meas Angle NA ° Ref. Blk. No.

N/A Calibration Remarks:

Calibration reflectors #3 at 54 25 and #5 at 7.6" are OD Notches Mode PIE Filter ON Cable Type /No. Conn. RG 174 / 0 ReflectorldB NA

/ NA Damping 400 Reject OFF Cable Length 6'

Amp/Sweep NA

% NA Comp Temp.

Configuration-Wo LocN Lo Loc.N 84 01REACTOR VESSEL STUDS

____NA JNA Scan Results

]Ind Length 1

Ref. Measurements Thickness Notes:

Dir.

NI NRI R

RDAc LI Lmax L2 i

Wmax Smax 1"<-

C/L

->1" 0-NA Examination/Limitation Remarks:

RPV Studs examined from the top No limitations Total Length Crown Width Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) of Weld NA NA 5 (L)

NA 2 (L)

NA 7 and 8 (W) NA 5-From NA to NA 2-From NA_

to NA From (5) NA to (2) NA i'rimary Examiner Richard Money SNC NDE Level i1/1Il Level II i

.il s ita tE a i e evel i No

-ec nca eview Andrew Mixon II Date Percentage of ANiI Review-S4.OJ7,0-1*

Code Coverage (0-Date Date Revision 4 0

Farley N(

Nlant Visual Examination Record VT-1 SHAR -Li)

Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-NO1 APRI-1300 S02F2V096 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA I_ Yes

-_BANW I-Yes Wj 1/32" Division (Scale)

[] Direct

[

Video Procedure No.

FNP-0-NDE-100 21 F-] No F] Color W No 1/32" Line (Gray Card) 1 Remote Revision No.

1 0

/

N/A Equipment Lighting Tools Examinertinitial John W Bell

'5 W

Level I Mirror

]-JN/A

, Ambient Vl Scale

[D Depth Gauge

[

Level SQg'

(

a*,

,j,.

Mgi micrometer F

Comparator L]

Examinerllnitial NIA Level V!]

Magnifier lI Flashlight Maicmer ld C

ator Sig N/A F-CCTV FI Droplight Li Caliper I.] Weld Gauge Date (Month-Day-Year)

________________________________9/20/2002

"*UN-

UN

-] WELDS AND BASE MATERIAL VT-1 SAT N/A S6 BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material 1_ F

-[

Loose Members

[0 F]-1 I7 Undercut

[i

[-1 FI Cracks I--

n-LI Corrosion Build-up

[-F I F Iv Corrosion F[ I Gouges

[7 rl Gouges

]

-i Evidence of Leakage Fi U]

W/i Thread Damage L/

[--]

[-1 Arc Strikes

[L_

1 P/

Deformation L]

[7 Cracks Li

[

[]

Protective Coating LE 0_

Other-

[

[7 ]

Evidence of Leakage

[]F]

[-

Other-*

Li L;

ID Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments NA FNP-O-*!

100.21 b

Farley NuC lent Visual Examination Record VT-1 SHARED)

FNP-0-i 100.21 Southern Nuclear ODerating Companv Plant / Unit Line Number/Examination Area/Weld No.

Drawing Numiber Sheet Number Farley

/

APR1-1300-N14 APR1-1300 S02F2V069 REACTOR VESSEL NUTS.

Photos Sketch Resolution Technique WO / WA NA I Yes L B/W L7 Yes 1/32 Division (Scale)

V Direct 0 Video Procedure No.

FNP-0-NDE-100 21 SNo O Color

[] No L7-7 1/32' Line (Gray Card)

-i Remote Revision No.

1.0

/

N/A Equipment Lighting Tools Examanerfnlt0-l DiValerfo Level R Mirror [I N/A Li Ambient 7V Scale El Depth Gauge Li Level Sig.

Examiner/Initial N/A Level SMagnifier Flashlight E Micrometer E-Comparator D_

Sig.

N/A l CCTV Li Droplight L-D Calper L Weld Gauge Date (Month-Day-Year) 9/19/2002

UN-

UN Li WELDS AND BASE MATERIAL VT-I SAT SAT N/A

[I BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material 0

W, Loose Members Undercut

[]

L]

Cracks Li M

Corrosion Build-up S/ 7]

1 Corrosion 11 Fi Gouges Oi Li 0

Gouges 1:

Li Evidence of Leakage El 0i Thread Damage 0i Li Arc Strikes Li

[]

Deformation Li Li Cracks Lij F-1 Protective Coating El Li Other-Ej 0

/

Evidence of Leakage El

[l Other L"i[

Li

Provide details on unsat areas by use of supplemental data sheet.

- Provide details on other areas examined Comments NA

Farley Nur Jant Visual Examination Record VT-1 SHAR[LD FNP-0-.

100.21 Plant I Unit Line Number/Examination Area/Weld. No, Drawing Number Sheet Number Farley I

2 APR1-1300-N1S APR1-1300 S02F2V070 I *REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO / WA NA Lj Yes ZB/W I

Yes Wj 1/32' Division (Scale)

__ Direct Video Procedure No.

FNP-0-NDE-100.21

[]No Color 9 No L_

1/32" Line (Gray Card)

Revision No.

1.0 N/A Equipment Lighting Tools Examiner/Initial/P5ul Di aleno Level VSig.

/

Mirror i] N/A El Ambient j Scale El Depth Gauge Li Level S-g.

Examiner/InItial N/A Level L. Magnifier 1

Flashlight Micrometer El Comparator Si Sg.

N/A Li CCTV ID Droplight Z Caliper

'Z Weld Gauge Date (Month-Day-Year) 9/19/2002 "UN-

UN

[] WELDS AND BASE MATERIAL VT-1 SAT SAT N/A R BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material 7,

El 7

Loose Members 1: Li Undercut El S/1 Cracks El Li Li Corrosion Build-up 0i

-i Corrosion Li El Gouges L1

'V Gouges Li Li Evidence of Leakage Di

[

]

Thread Damage Li]

Li Arc Strikes Li 5i 1 Deformation

[i Li Cracks L

]

Li V

Protective Coating Irv ]

Other-El Evidence of Leakage El L[

Other El El Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined uomments NA Revision 1.0

r Farley Nu..

'ant Visual Examination Record VT-1 C

SHARE,_)

FNP-O-100.21 Southern Nuclear Operating Comoanv Plant / Unit Linb Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-N24 APR1-1300 S02F2V071 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA L Yes El B/W 2 Yes ki 1/32" Division (Scale)

] Direct Video Procedure No.

FNP--NDE-100.21 S No

- Color 7V No 2 1/32' Line (Gray Card) 2 Remote Revision No.

1 0 I N/A Equipment Lighting Tools Examlner/IntiRayI DiValeno Level Sig.

SMirror N/A Ambient

-Scale

[Depth Gauge D Level Examiner/initial N/A Level Magnifier R Flashlight S

Micrometer 2 Comparator 2

sIg.

N/A S CCTV 2 Droplight

[

Caliper E2 Weld Gauge 2

Date (Month-Day-Year) 9/19/2002

UN-

UN 2 WELDS AND BASE MATERIAL VT-1 SAT SAT N/A R

BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material 2]

V]

Loose Members 2

El 2l Undercut 2

2 1

Cracks 27 2l Corrosion Build-up 2

2 Corrosion 2l 2

Gouges 2]

2]

7 Gouges D

2 Evidence of Leakage 2

2 Thread Damage 2

2 Arc Strikes

]

2

[

Deformation 2

2 Cracks 2

l 2

Protective Coating 2

2 Other**

0 2

Evidence of Leakage 2

2 Other 2*[

2]

Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments NA

Farley Nu(&

lant Visual Examination Record VT-.1.

C SHARED).

FNP-0(

100.21 Southena N-1 e%%.

no

'pa VVVLn ithi I. IU,,

n g*I.Il I

m Iny Plant / Unit Line Number/Eiamination ArealWeld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-N25 APRI-1300" 02F2V072 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA S Yes 7i B/W 0- Yes 1/32' Division (Scale)

Re Direct Li Video Procedure No.

FNP-0-NDE-100 21

No Li Color

[

No Li 1/32" Line (Gray Card)

[] Remote Revision No.

1.0

/ N/A Equipment Lighting Tools Examiner/initla iauValeno Level

_kMirror Li N/A El Ambient

[

Scale L_ Depth Gauge LI Level Examiner/initial N/A Level Magnifier RP Flashlight Li Micrometer Li Comparator Si Sg.

N/A mK CCTV Li Droplight Li Caliper

[] Weld Gauge 0i

, Date (Month-Day-Year)

____________9/19/2002

UN-

UN Li WELDS AND BASE MATERIAL VT-1 SAT SAT N/A

[

BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material El Li

[

Loose Members IV]

L i]

Undercut w]

51

/

Cracks 7W 0i Corrosion Build-up E]

Li 7

Corrosion LZ Li Gouges i

L 17-Gouges L]

Ei Li Evidence of Leakage Li Li

[

Thread Damage Li Li Arc Strikes Li Li

[

Deformation Li Li Cracks Li Li

[

Protective Coating Li Li Other-*

Ei Li Evidence of Leakage EL EL i

]

Other~ *i[

Li

[

Provide details on unsat areas by use of supplemental data sheet.

- Provide details on other areas examined Comments NA

Farley NuE Plant Visual Examination Record VT-1 SHARED FNP-0ucea 100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley 2

APR1-1300-N27 APR1-1300 S02F2V097 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA 0 Yes E] BNv E] Yes SI 1/32" Division (Scale)

Fi Direct Video Procedure No.

FNP-0-NDE-100 21 SNo

[1 Color n No I

1/32" Line (Gray Card)

[1-Remote Revision No.

1 0 I N/A Equipment Lighting Tools Examiner/inltial JohnW Belli Level SMirror Li N/A

[W Ambient S/1 Scale Fi Depth Gauge Li Level I,Magnifier 1 Flashlght LI Micrometer Li Comparator L]ImIg N/A I j CCTV Li Droplight

.- Caliper L-Weld Gauge Date (Month-Day-Year)

____________________9/20/2002

UN-

UN

]WELDS AND BASE MATERIAL VT-1 SAT A7' N/A I-I BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material I. I Loose Members E]

[i Undercut

[-I Cracks Li E]

Corrosion Build-up I_-

[L 9

Corrosion 1]

Li L]

Gouges

[-1 Li

[v Gouges

[I

-I Evidence of Leakage

[-1

-]

S/1 Thread Damage Li Li Arc Strikes F-]

E_

[I ]

Deformation

[]

Li Cracks 0

Li W

Protective Coating

[]i L

Other**

[i Li ]

Evidence of Leakage Li L-

[1I Other *-

Li

-i Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

Farley NuC Plant Visual Examination Record VT-I SHARED

(

FNP-O-(F 100.21 Southern Nuclear Operating Company Plant I Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APRI-1300-N28 APRI-1300 S02F2V098 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO / WA NA 0B Yes

[ 1]Yes FJ] 1/32" Division (Scale)

[

Direct

[ Video Procedure No.

FNP-0-NDE-100.21

j No i_"]

Color No VJ 1/32" Line (Gray Card)

-] Remote Revision No.

1 0

/ N/A Equipment Lighting Tools Examiner/Initlal John W Bell

&'-'3 8

Level F mirror [I N/A

/* Ambient

] Scale

[1 Depth Gauge F] Level SIg.

I Examinertinitial N/A Level F] Magnifier 7-] Flashlight

] Micrometer 1 - Comparator Si

]

Slg.

N/A L-C CTV

[ -D roplfight L Caliper

-W eld G auge I

-]

Date (M onth-Day-Year) 9/20/2002

UN-

UN F] WELDS AND BASE MATERIAL VT-1 SAT SA, N/A F-BOLTS, STUDS, AND WASHERS VT-I SAT SAT N/A Ground Blend Material E-F!

Loose Members F]

Li Undercut

[]

L]

[

Cracks 0]

[

Corrosion Build-up I __

L-I Corrosion 1]

[-]

Gouges F]

El WJ Gouges VL-I-]

Evidence of Leakage E]

E]

F]

Thread Damage F-1 F]

Arc Strikes F]

L-I

[]

Deformation

-I

[1 Cracks LI F]

E W

Protective Coating F] 1]

D]

Other-F[]

F]

[]

Evidence of Leakage

]

L1 Other-

[7 F]

[]I Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments NA

Farley Nu(

'lant Visual Examination Record VT-1 C

SHARED FNP-04 100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley I

2 APRI-1300-N29 APR1-1300 S02F2V099 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA Li Yes L-BNW Li Yes W1 1/32" Division (Scale)

[] Direct EH Video Procedure No.

FNP-0-NDE-100 21 F-/ No F] Color No ri 1/32" Line (Gray Card)

-] Remote Revision No.

1 0

/ N/A Equipment Lighting Tools Examinerlinltlal John W Bell Level L] Mirror w N/A

[ Ambient

[ Scale Li Depth Gauge F] Level Sag_,,,ý III Examlner/lnitlal N/A Level SMagnifier Flashlight

/

Micrometer LI Comparator F_]

SIg.

N/A Li CCTV L-j Droplight r i Caliper Li Weld Gauge Li Date (Month-Day-Year)

__________________________9/20/

/20200

"*UN-

UN El WELDS AND BASE MATERIAL VT-I SAT 54-r N/A

[] BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material LI F]

Loose Members Li Li W

Undercut

-]

Li

[]

Cracks 0i Li Corrosion Build-up F]

Li Corrosion Li I]

Gouges

[ I LI

-i Gouges

[]

Li

[i Evidence of Leakage U

]

We l Thread Damage Li F]

Arc Strikes r i L_

J Deformation

[l EL F-]

Cracks L-Li Protective Coating

[i F]

Other-F F]

Evidence of Leakage Li H

f-l Other-L0 rJ

]

Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

Farley Ni1 1ant Visual Examination Record VT-1 C

SHARED FNP-O(V 100.21 Southern Nuclear Operating Company Plant I Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley I

2 APRI-1300-N30 APRI-1300 S02F2V100 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WOIWA NA Yes

- BNVF1 Yes W 1/32" Division (Scale)

Direct Procedure No.

FNP-0-NDE-100 21 Vj No

[71-Color

[] No

-- 1/32" Line (Gray Card) 7 Remote Revision No.

1 0

/ N/A Equipment Lighting Tools Examiner/Initlal John W Bell

.V.G Level Vý

-1 mbientSig.'G2 W (IMAJE

- Mirror [I N/A l

Ambient Scale L - Depth Gauge Li Level Examiner/Initial N/A Level Magnifier F,7 Flashlight Li Micrometer I 1 Comparator Li-_.

Sig.

N/A i-] CC'I'V

[-i Droplight LI Caliper L_ Weld Gauge

_-]_

Date (Month-Day.Year) 0_Dat____9/20/2002

UN-

UN V-WELDS AND BASE MATERIAL VT-1 SAT

-r N/A

[F BOLTS, STUDS, AND WASHERS VT-I SAT SAT N/A Ground Blend Material

[-- JI 0

/

Loose Members H1 ri Undercut

[]

-]

Cracks

-]

Corrosion Build-up P F i

[*

Corrosion

[.]

]

Gouges

[]

7 Gouges

[]

L))

H Evidence of Leakage El F]

[%

Thread Damage Arc Strikes

-]

]

Deformation

[f J.

Cracks

[71

]

[

Protective Coating Li F

Other** "

F]

[-;

Evidence of Leakage H

LI Other **

[--

[.LI

[*F Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments NA

Farley Nl(,I

'lant Visual Examination Record VT-I SHARED FNP-0.1 100.21 Southern Nuclear Operatingl Company Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APRI-1300-N31 APR1-1300 S02F2V101 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA LYes

[]BAN LI Yes

[

1/32" Division (Scale)

[% Direct L] Video Procedure No.

FNP-0-NDE-100 21

[] No LI Color

ý-/ No

[% 1/32" Line (Gray Card)

El Remote Revision No.

1 0

/ N/A Equipment Lighting Tools Examiner/Initial John W Bell

iA~'3 Level Fr* Mirror LI N/A S

Ambient

/

Scale Ij Depth Gauge Li Level lg0_9L III ExamLner/lnltlal N A Level

,-M agnifier

[ ] Flashlight

-_] M icrometer LI Comparator

_ SIg.

N/A

-. CCTV Li Droplight L

Caliper L-Weld Gauge I

Date (Month-Day-Year)

______________________________________________9/20/2002

"*UN-

UN LI WELDS AND BASE MATERIAL VT-1 SAT N/A

{-i BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material E]

LI V

Loose Members LI LI Undercut E]

EL W-Cracks

[.-LI Corrosion Build-up El Li W 1 Corrosion W[

[]

Gouges LI El L]

Gouges

[R

[-]

L Evidence of Leakage LI El W

Thread Damage RI EL Arc Strikes

-I

[0

]

Deformation

[]

0-LI Cracks

[3 LI V

Protective Coating MI LI Other**

EL EI

[]

Evidence of Leakage El LI Other LI

[

Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

Farley Nu(, ?ant Visual Examination Record VT-1 SHARED FNP-0-h' 100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley I

2 APR1-1300-N32 APR1-1300 S02F2V102 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA L-Yes

[I BAN F] Yes F1 1/32" Division (Scale)

Direct F] Video Procedure No.

FNP-0-NDE-100 21 S.'j No Li Color r/ No W1 1/32" Line (Gray Card)

-71 Remote Revision No.

1 0 I N/A Equipment Lighting Tools Examlner/initial John W Bell

?

Level Sigcj3

~

n

[5/ Mirror [I N/A LW Ambient F] Scale E] Depth Gauge E] Level V

Examiner/Inltlal N/A Level

-*] Magnifier Flashlight iMicrometer Comparator

[-]

Sig.

N/A F] CCTV

_] Droplight Li Caliper

-] Weld Gauge L-Date (Month-Day-Year) 9/20/2002

UN-

UN E] WELDS AND BASE MATERIAL VT-1 SAT SA' N/A E] BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material F-I

-j

[

Loose Members Undercut r]

[

W

[

Cracks W[

F_-]

Corrosion Build-up F-

[I W]

Corrosion FR D]

Gouges F]

Fj

[

Gouges

[]i E]

Evidence of Leakage F-]

FI J

W Thread Damage 0]

F]

-]

Arc Strikes L-F]

[

Deformation F-LI

-]

Cracks

[]

[--]

[]

Protective Coating ri F]

Other**

Li

.]

[V Evidence of Leakage 0]

[J Other **

_]

I,/-]

Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments NA

Farley NuC 3lant Visual Examination Record VT-I SHARED FNP0"-04 100.21 Plant I Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300.N51 APR1-1300 S02F2V103 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO IWA NA LE Yes El BAI

[] Yes St] 1/32" Division (Scale)

[] Direct w Video Procedure No.

FNP-0-NDE-100 21 rV No Ln Color F-] No FI 1/32" Line (Gray Card)

H Remote Revision No.

1 0

/ N/A Equipment Lighting Tools Examinerllnltial John W Bell 8 )w Level I] Mirror EH N/A I] Ambient

[ Scale L] Depth Gauge Li Level SWgi

Il Examlnerflnitial NIA Level 1Magnifier

[

Flashlight Sig Micrometer Comparator Sg.

NIA LI CCTV El Droplight Li Caliper L__]Weld Gauge Li Date (Month-Day-Year)

__________________________9120/9/20200

UN-

UN EL WELDS AND BASE MATERIAL VT-1 SAT A'A N/A

[] BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material

[0 H

[]

Loose Members Li 1__

FV Undercut Li H--

[7 Cracks HI/[

i Corrosion Build-up L]

[-]

F]

Corrosion L[

[_

Gouges 1]

l w-i Gouges

[]

F]

LI Evidence of Leakage EL EL

[]

Thread Damage LI E]

Arc Strikes LI Li-

[]

Deformation D

U.I Cracks Li Li R

Protective Coating D

Li Other-

[]

L

[

Evidence of Leakage I

-L[

Other --

Li Provide details on unsat areas by use of supplemental data sheet

- Provide details on other areas examined Comments NA

Farley Nu[

-lant Visual Examination Record VT-i C

SHARED)

C_

FNP-O*h 100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley 2

APR1-1300-N52 APR1-1300 S02F2V104 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA Li Yes L-BAN Li Yes v 1/32" Division (Scale)

Direct LI Video Procedure No.

FNP-0-NDE-100 21

- No Li Color

[*_I No

[] 1/32" Line (Gray Card)

El Remote Revision No.

1 0

/ N/A Equipment Lighting Tools Examiner/Initial John W Bell 6W 1 Level S Mirror [I N/A F Ambient S/] Scale Li Depth Gauge L_ Level SIg-*.*c

,-W (:a

.ý III Examiner/Initial N/A Level F-]Magnifier F! Flashlight L] Micrometer Si Comparator Sig.

NIA LCCTV Li Droplight Li Caliper 0i Weld Gauge Li Date (Month-Day-Year)

____________________________9/20/2002

UN-

UN L-WELDS AND BASE MATERIAL VT-1 SAT

,-r1 N/A

[57 BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material

[

El F

Loose Members Li w1

/_

Undercut F-

[F-1 Cracks R1 F-LI Corrosion Build-up f']

[1 R-1 Corrosion

[I I-]

Gouges 1-1 0-W]

Gouges El P]

Evidence of Leakage F1 El Thread Damage El EL Arc Strikes Fi]

[71

[

Deformation 17 Li Li Cracks EL EL 5

Protective Coating Li El Other-El Li W

Evidence of Leakage Li Li Other "i

[L'

Provide details on unsat areas by use of supplemental data sheet

- Provide details on other areas examined Comments NA

Farley Nu-

,[ lant Visual Examination Record VT-i SHARED FNP-0-1*

100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley 2

APR1-1300-N53 APRI-1300 S02F2V105 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA LI Yes E-] BNW LI Yes 7/ 1/32" Division (Scale) i Direct Video Procedure No.

FNP-0-NDE-100 21 SNo F] Color F-/ No 1/32" Line (Gray Card)

F] Remote Revision No.

1 0 I N/A Equipment Lighting Tools Examinerlinitial JohnW Bell 46W Level V- -M irror O ]N/A

Ambient W1 Scale I _ Depth Gauge

-_ Level S l g.

III FIMcoeeCoprtrExaminer/Initial NIA Level I Magnifier fV-Flashlight

[-l Micrometer

[g Comparator

]A L.-CCTV Li Droplight Fl Caliper Ii Weld Gauge LI Date (Month-Day-Year)

__________________________9/20/2/20200

UN-

UN E_] WELDS AND BASE MATERIAL VT-1 SAT

.Ar N/A FV BOLTS, STUDS, AND WASHERS VT-SAT SAT N/A Ground Blend Material W]

Loose Members F

R Undercut 7V

[]

Cracks I*

Li l

Corrosion Build-up F]

[1 7

Corrosion UI]

[]

Gouges L]

[__

]

Gouges

-]

LI Evidence of Leakage

[]

F]

Thread Damage F

[]

Arc Strikes El LiJ F

Deformation

I

{

I_

Cracks

-i W]

Protective Coating

[

I.]

Li Other*"

F]

1]

Evidence of Leakage L-LF Other "]

i Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

Farley NI(

Nlant Visual Examination Record VT-1 SHARED FNP-0 7

100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APRI-1300-N54 APR1-1300 S02F2V106 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO / WA NA L* Yes LI BAN F] Yes

[

1/32" Division (Scale)

L] Direct Video Procedure No.

FNP-O-NDE-100.21 V No E] Color

[ -- No

[ 1/32" Line (Gray Card)

-Remote Revision No.

1 0 I N/A Equipment Lighting Tools Examineriinitlal JohnW Bell 8

,is Level

,- Mirror Li N/A Ambient

[

Scale EL Depth Gauge

[] Level GgMAJ

(

.9.

Examinerfinitial N/A Level F. Magnifier W1 Flashlight i

Mgcrometer

[II Comparator Sig.

N/A Li CCTV L Droplight Li Caliper F] Weld Gauge El Date (Month-Day-Year) 9/

___________________9/20/2002

"*UN-

UN

_J WELDS AND BASE MATERIAL VT-1 SAT

-AT N/A

[

BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Matenal L-]

Li

[]

Loose Members EL Li Undercut El W

Cracks W

E]

Corrosion Build-up

[i L

[

Corrosion

[

LI Gouges

[]

Li

[]

Gouges

[

Li LI Evidence of Leakage

[7

] Li Thread Damage El L-]

Arc Strikes EL Li W

Deformation W]

L-Li Cracks Li Li W]

Protective Coating S/1 El Other-*

EL EL V

Evidence of Leakage EL H

Other-*

Li

Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

Farley Nu(

-lant Visual Examination Record VT-1 SHAREDL Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-N55 APRl-1300 S02F2V107 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO / WA NA Li Yes 13 BNV

[] Yes

[1 1/32" Division (Scale)

[I Direct

-J Video Procedure No.

FNP-0-NDE-100 21 INo E Color No

[-] 1/32" Line (Gray Card)

F] Remote Revision No.

1.0 I N/A Equipment Lighting Tools Examinerflnitial John W. Bell Level r Mirror D] N/A

Ambient W-] Scale Li Depth Gauge

0. Level

slgiA04, W

Examiner/initial N/A Level I.-Magnifier Flashlght

] Micrometer

[] Comparator

]ig

[]CCTV Li Droplight L] Caliper F] Weld Gauge L_]_Date (Month-Day-Year)

_______________________________________________________________________________________9/2__1/20200

"*UN-

UN

[] WELDS AND BASE MATERIAL VT-I SAT SAT N/A I]

BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material rF]

f Loose Members

[]

[-]

Undercut 7V Cracks El E

Corrosion Build-up Li

[1 L

Corrosion E -]

Gouges 0

F]-

Pe Gouges FI Evidence of Leakage

[

D_

F Thread Damage FLi E]

Arc Strikes o-03 F

Deformation

[I

[1_]

0 Cracks Li 1:

[

Protective Coating 0]

F Other-Li F]

[

Evidence of Leakage

[-

Li Other-0

[1

[

Provide details on unsat areas by use of supplemental data sheet,

- Provide details on other areas examined Comments NA FNP-0-1t 100.21 Revision 1.0

Farley Nu(-

'lant Visual Examination Record VT-1

(

SHARED)

FNPC0 N o0.21 Southern Nuclear Operating Company Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

APR1-1300-N56 APRI-1300 S02F2V108 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA L

e Yes BAN Yes 1/32" Division (Scale)

L Direct w Video Procedure No.

FNP-0-NDE-100 21 W-No N]

Color

[V] No 1/32" Line (Gray Card) 1 Remote Revision No.

1 0

/ N/A Equipment Lighting Tools Examinerfinitial John W Bell Level SIg.

,3 S/ Mirror LI N/A r

Ambient

Scale El Depth Gauge El Level W

(.110 Examinerflnitial N/A Level Magnifier

[] Flashlight Fl Micrometer el Comparator F-]

Sig.

N/A Li Ccv EL Droplight

-] Calper

[] Weld Gauge F]

Date (Month-Day-Year) 1 1_

9/20/2002

UN-

UN

[] WELDS AND BASE MATERIAL VT-1 SAT M7r N/A

[l BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material

[]

L Loose Members 0I F

Undercut

-]

Li Cracks

-]

LI Corrosion Build-up

[-

Li Corrosion

--]

[i Gouges

[]

[i Gouges

-I LI Evidence of Leakage F-] LI Thread Damage

[E II

-J Arc Strikes Li-I fv Deformation L]

Li Cracks Li LI v

Protective Coating E]

LI Other**

LI LI Evidence of Leakage LI LI F*

Other**

[_-]

7]

Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

Farley NuC -

ant Visual Examination Record VT-1 C

SHAREL)

FNP(0-K 00.21 SouternNuclarFnPr-0-nn

.00.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-N57 APRI-1300 S02F2V109 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA 0] Yes Li B/W 0i Yes

[

1/32" Division (Scale)

[] Direct El] Video Procedure No.

FNP-0-NDE-100 21 F] No El Color F-i No 1/32" Line (Gray Card)

F]1 Remote Revision No.

1 0

/ N/A Equipment Lighting Tools Examiner/Initial John W Bell (Ue Level 51g.

t..Nf&

Mirror L N/A

-S Ambient cale EL Depth Gauge El Level Examiner/Initial N/A Level J-]Magnifier Flashlight D_ Micrometer

[] Comparator F]

SIg.

NIA LI CCTV Li Droplight F] Caliper L] Weld Gauge LI Date (Month-Day-Year)

________________________________9/20/2002

".UN-

UN El WELDS AND BASE MATERIAL VT-I SAT SAr N/A tIl BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material

[

D W]

Loose Members Li

[]

Undercut L-F F]

7V Cracks F]

[

Corrosion Build-up F]

i Corrosion

[_

Gouges L[ 1

]

Gouges I-/

-]

F]

Evidence of Leakage

[]

Li Thread Damage LI1 LF.IL Arc Strikes LD L

[]

J Deformation

[W

[1 Li Cracks LI Li Protective Coating W]

E]

Other-

[]

Li

[

Evidence of Leakage 0i El Other~ **

i Li

Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments NA

Farley Nu(

'lant Visual Examination Record VT-1 C

SHARED FNP-0-'(

.100.21 Plant / Unit Line NumberlExamination Area/Weld No.

Drawing Number Sheet Number Farley

/

APRI-1300-N58 APRI-1300 S02F2V110 REACTOR VESSEL NUTS Photos Sketch Resolution Technique WO I WA NA F-] Yes 1BNV Yes 1/32" Division (Scale)

FJ Direct Video Procedure No.

FNP-0-NDE-100 21

!%1 No N]

Color Dy No 1/32" Line (Gray Card)

F] Remote Revision No.

1 0

/ N/A Equipment Lighting Tools ExaminerlInitlal JohnW Bell

'inwG Level F Mirror Fi] N/A SJ Ambient Scale LI Depth Gauge Li Level

,] Magnifier Flashlight LI Micrometer L-Comparator Exam inerliitia NIAA Ii CCTV Li Droplight L[ Caliper LJ Weld Gauge Li Date (Month-Day-Year) 9/20/2002

UN-

UN L] WELDS AND BASE MATERIAL VT-1 SAT N/A L] BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material r_

LJ Loose Members Ei F]

Undercut i -

]

Cracks F]

Li Corrosion Build-up W

i

[

Corrosion 0i U

Gouges W[.

3 J

Gouges

[]I E-1 l

Evidence of Leakage

((

L -

Thread Damage

[]1

[E.

Arc Strikes

[11

-J F/

Deformation E[]

[-1

[-1 Cracks

[]

EL W

Protective Coating F))

E E

Other*

[] El W]

Evidence of Leakage El 0

W Other **

W-L[

Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

Farley N[_

?lant Visual Examination Record VT-I SHARED C

Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APRI-1300-WO1 APRl-1300 S02F2V077 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA LI Yes 13 LNVi Yes t

1/32" Division (Scale)

LI Direct EL Video Procedure No.

FNP-0-NDE-100 21 V] No F" Color r

No ij 1/32" Line (Gray Card)

F] Remote Revision No.

1.0

/ N/A Equipment Lighting Tools Examinernlnltial JohnW Bell

'*3 3

Level Sig.

tO.

J Mirror [-_i N/A 1

Ambient I1 Scale L Depth Gauge El Level I

'I Examine-Initial N/A Level

,- Magnifier P Flashlght K] Micrometer LI Comparator F]

Sg.

N/A Li CCTV Li Droplight Li Caliper 1 Weld Gauge E]

Date (Month-Day-Year)

_______________9/20/2002

UN-

UN L] WELDS AND BASE MATERIAL VT-1 SAT SAA N/A

,*1 BOLTS, STUDS, AND WASHERS VT.1 SAT SAT N/A Ground Blend Material Ei F]

Loose Members E I Undercut

[-]

[

Cracks W-1 Corrosion Build-up F]

[ j Corrosion LIe L I F1 Gouges E]

D]

[_/1 Gouges I-I Evidence of Leakage I-]

L j Thread Damage L]

Arc Strikes EI L

I F,

Deformation Fi L_]

Cracks F]

[j F.j Protective Coating

[Ei L

Other" El 1-1 i

H Evidence of Leakage hi Other *

!I Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

Farley Nuc(.

lent Visual Examination Record VT-1 SHARED FNP-O-,-100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farlyy

/

2 APR1-1300-W14 APR1-100""

S02F2V073 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO / WA NA 7 Yes 7

A/W Li Yes 1/32" Division (Scale)

Direct Di Video Procedure No.

FNP-0-NDE-100 21 S No

- Color

[

No 1/32" Line (Gray Card)

I Remote Revision No.

1.0

/ N/A Equipment Lighting Tools Examiner/lnltlal ul Valerio Level

'Mirror Di N/A Li Ambient 7

Scale L7 Depth Gauge

[

Level S,-..

r-,

Examiner/Initial N/A Level L-4 Magnifier 7] Flashlight

[_i Micrometer Li Comparator E--tSig.

N/A Li CCTV L Droplight 7

Caliper i Weld Gauge Date (Month-Day-Year)

__________________9/19/2002

UN-

UN Li WELDS AND BASE MATERIAL VT-1 SAT SAT N/A i BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material E!

r-S Loose Members Li[

E]

Undercut 1i 7

r Cracks Li Li Corrosion Build-up Li L]

[]

Corrosion Li Li Gouges L]

Li S6 Gouges Ri Li Evidence of Leakage Li Li L

Thread Damage Li Li Arc Strikes EL Li W

Deformation

'7V L

Cracks Li Li

[

Protective Coating Li Li Other-Li Li

[]

Evidence of Leakage i

Li]

Other El Li

[

Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments NA

Farley Nucc lant Visual Examination Record VT-1 SHARED C

FNP-O-1N.,.--1 00.21 Souher Nule r

.....t..

C n-Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley 2/

APR1-1300.W15 APR1-1300 S02F2V074 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO/WA NA S--*'1/32" Division (Scale)

VJ Direct Yes El B/W I Yes 1

D Si Video Procedure No.

FNP-0-NDE-100.21 VW No EI Color

[] No iJ 1/32" Line (Gray Card)

Li Remote Revision No.

1.0

/ N/A Equipment Lighting Tools Examiner/Initial P6Zi'DiValerio Level Sig.

S Mirror [I N/A L-i Ambient 7} Scale LI Depth Gauge LEI Level

-4..

-I Examiner/initial N/A Level Magnifier Flashlight EL Micrometer Li Comparator ID Sig.

N/A Li CCTV Droplight El Caliper Li Weld Gauge

[]

Date (Month-Day-Year) 9/19/2002

UN-

UN Li WELDS AND BASE MATERIAL VT-1 SAT SAT N/A 9

BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material

[]

[i R

Loose Members R

[]

Undercut Li 0]

_jf Cracks ii 0i Corrosion Build-up R1

[

Corrosion Fl Li L

Gouges Li Li Gouges Li Li Evidence of Leakage Li Li r

Thread Damage Li]

E L Arc Strikes Li Li

[

Deformation Li L]

Cracks li i

V_

Protective Coating li Li Other*

Li EL R

Evidence of Leakage Li Li Other**

Li Li-

Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined uomments NA

Farley Nu C

,ant Visual Examination Record VT-1 SHARED)

Plant / Unit Line Number/Examination Area/Weld No.

Farley I

2 APR1-1300-W24 REACTOR VESSEL WASHERS Drawing Number APR1-1300 FNP-0-I 100.21 Southern Nuclear Operating Company Sheet Number S02F2V075 Photos Sketch Resolution Technique WO I WA NA E] Yes Li B/W D Yes 1/32" Division (Scale)

[' Direct

[] Video Procedure No.

FNP-0-NDE-100.21 SNo D Color

'1 Na EN 1/32" Une (Gray Card)

Li Remote Revision No.

1.0 I N/A Equipment Lighting Tools Examiner/initlal Pal.

aleno Level Sig.

If Mirror ' N/A L Ambient

_Scale

[Depth Gauge

[Level Examiner/initial NI A Level

[ Magnifier Vi Flashlight Ei-Micrometer D Comparator Si Sig.

N/A ID CCTV

[]Droplight

[l Caliper EJ Weld Gauge Date (Month-Day-Year)

Droplight__________

Date___

9/19/2002

UN-

UN LiJ WELDS AND BASE MATERIAL VT-1 SAT SAT N/A L] BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material I

Loose Members E

F-1 Undercut ED

r. 1 Cracks El Li Corrosion Build-up

[]

i Corrosion Li El F

Gouges

[ E j

Gouges 0i Li Evidence of Leakage

[]

El S/

Thread Damage El Li Arc Strikes E-l 0

7-/

Deformation

[I El Cracks ED

[]

R Protective Coating

[R Li Other**

Evidence of Leakage Ei LI Other **

Li Li Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments NA

Farley Nu (cC, 'lant Visual Examination Record VT-1 SHARED FNP-O-N. S-100.21 Plant / Unit Line Number/Examlnatlon Area/Weld No.

brawing Noihber Slieet Number.o Farley

/

2 APR1-1300-W25 APRI-1300 S02F2V076 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA El Yes El B/W

[] Yes 1/32' Division (Scale)

Direct El Video Procedure No.

FNP-0-NDE-100.21 SNo D Color

[] No LI 1/32" Line (Gray Card)

L Remote Revision No.

1.0 I N/A Equipment Lighting Tools Examiner/Initial Paul IV5 erio Level

Mirror LI N/A L Ambient

[] Scale 17 Depth Gauge LI Level SiI.

Examiner/initial N/A Level LI Magnifier

[

Flashlight El Micrometer El Comparator El SIg.

N/A LICCTV LI Droplight El Caliper LI Weld Gauge MI Date (Month-Day-Year)

_________________9/19/2002

UN-

UN L. WELDS AND BASE MATERIAL VT-1 SAT SAT N/A

[

BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material w

ii Loose Members Re El El Undercut El

[]

Cracks RI

[]

Corrosion Build-up L0 E

7 Corrosion FV1 11 Gouges j

EI Rj Gouges

[]

-I Evidence of Leakage LI L

I R

Thread Damage EI ]I Arc Strikes El LI

[]

Deformation

[I

[]

Cracks El 9I j Protective Coating RI MI Other** "I LI Evidence of Leakage EI lI Other R-1I

Provide details on unsat areas by use of supplemental data sheet.

"Provide details on other areas examined Comments NA

Farley NC

)lant Visual Examination Record VT-1 SHARED C I FNP-0-K 100.21 Southern Nuclear Operating Company Plant I Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley I

2 APR1-1300-W27 APR1-1300 S02F2V078 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA F] Yes L BNV Fl Yes R

1/32" Division (Scale)

] Direct e Video Procedure No.

FNP-0-NDE-100.21 1,A No F] Color I No L

1/32" Line (Gray Card)

F-Remote Revision No.

1 0

/ N/A Equipment Lighting Tools Examinerf*nitial JohnW Bell Level

, Mirror 1 N/A W Ambient

[] Scale Li Depth Gauge 1] Level Sig. Cý W (11M,0*

III Examlner/lnitlal NIA Level Magnifier W] Flashlight F] Micrometer Fl Comparator Si Sg.

N/A LJ CCTV Ei Droplight i

Caliper L] Weld Gauge Li Date (Month-Day-Year)

___________________________________9/20/2002

UN-

UN

[] WELDS AND BASE MATERIAL VT-1 SAT

$Ar N/A

[F BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material n

IJ F

Loose Members

[]

E]

Undercut L-]

El

[P/

Cracks

[ -1

]

Li Corrosion Build-up F]

FJ]

]

Corrosion Fi F1 i]

Gouges W[]

]

Gouges F%-_))

LI Evidence of Leakage

[1 F]

[

Thread Damage L.

I Arc Strikes

-]

Li

[

Deformation F]

]

Cracks 1]

Li

[J Protective Coating

[]

E]

C]

Other**

El Di W

Evidence of Leakage EL El

[

Other Li F]

Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments NA Revision 1 0

Farley Nk.

lant Visual Examination Record VT-1 SHARED FNP-04K 100.21 Southern Nuclear Operating Company Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-W28 APRI-1300 S02F2V079 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO /WA NA 1-Yes 0] BNw El Yes

[

1132" Division (Scale)

[

Direct El Video Procedure No.

FNP-0-NDE-100 21 SNo Li Color No

[*]

1/32" Line (Gray Card)

Li Remote Revision No.

1.0 I N/A Equipment Lighting Tools Examiner/Initial John W. Bell 19 Level SM irror LI N /A

[ A m bient

S cale LI D epth G auge L I Level Siga n rI. n, N/

Level Examlner/Inltlal NIA Level

[lMagnifier

[] Flashlight

-] Micrometer L-Comparator E]

Sig.

N/A h]CCTV EL Droplight L

Caliper

_- Weld Gauge Li Date (Month-Day-Year)

___________________________________9/20/2002

UN-

UN Li WELDS AND BASE MATERIAL VT-1 SAT SAT N/A W1 BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material

[]1 R

[

Loose Members 0

[1 W

Undercut F]

[- ]

Cracks R-Li Corrosion Build-up F[ I L

Corrosion WL F-F]

Gouges D]

1 W-]

Gouges PF1]

L-E Evidence of Leakage i

Ei

[]

Thread Damage E]

E]

Arc Strikes

[

0 L_

[]

Deformation El]

Li Cracks Li Li

[]

Protective Coating E[]

[i L[

Other-R, L-Evidence of Leakage W-Li

--]

Other**]

[

Provide details on unsat areas by use of supplemental data sheet

- Provide details on other areas examined Comments NA

Farley Nu("

'lant Visual Examination Record VT-1 SHARED)

C,I FNP-O-N 100.21 Southern Nuclear Operating Company Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley I

2 APR1-1300-W29 APR1-1300 S02F2V081 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO IWA NA E1 Yes Li B/W El Yes

-1 1/32" Division (Scale)

Direct ni Video Procedure No.

FNP-0-NDE-100.21

-No F] Color

[

No

[] 1/32" Line (Gray Card)

F] Remote Revision No.

10 IN/A Equipment Lighting Tools Examlner/Inltlal John W Bell

,w Level FV M irror [ i N/A

[ Am bient Scale

[] Depth G auge F ] Level S ig ne/nta NL v

Examiner/Initial N/A Level 1,1] Magnifier Flashlight F

Micrometer F Comparator F]

sfg.

N/A ii CCTV El Droplight LI Caliper V-1 Weld Gauge 1]

Date (Month-Day-Year)

______________________________________________9/20/2002

"*UN-

UN

-_ WELDS AND BASE MATERIAL VT-I SAT

'Ar N/A Rl BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material

-i

[

Loose Members 11 F]

Undercut U-Li Fv Cracks

[

[]

LI Corrosion Build-up

_]

El V]

Corrosion

[i

[I Gouges L0 L.

F' Gouges

[]

Evidence of Leakage L1 F-]

7 Thread Damage

-]

Li Arc Strikes F-.-]

F%1[

Deformation Ii FJ]

0I Cracks El EL F

Protective Coating W

F-Lij Other-L.

Li Evidence of Leakage

[7-]

[-]

Provide details on unsat areas by use of Other 0

supplemental data sheet Provide details on other areas examined Comments NA

Farley Nu(

. Plant Visual Examination Record VT-1 C

SHARED FNP-O.

-100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-W30 APRI-1300 S02F2V082 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA 11 Yes 13N BVW L Yes m

1/32" Division (Scale)

Direct Video Procedure No.

FNP-0-NDE-100 21 DI No

[ Color F/ No

ýr 1/32" Line (Gray Card)

F. Remote Revision No.

1 0 I N/A Equipment Lighting Tools Examiner/Initial John W Bell Level

[ Mirror E] N/A I] Ambient

[] Scale E] Depth Gauge El Level Slgog'c' III Examlner/lnitial NIA Level I.] Magnifier

[] Flashlight i

Micrometer L_

Comparator

[]

sig.

N/A I

CCTV

[] Droplight

[_ Caliper L_ Weld Gauge LD Date (Month-Day-Year) 1 9/20/2002

UN-

UN EH WELDS AND BASE MATERIAL VT-1 SAT 7/AT N/A

[

BOLTS, STUDS, AND WASHERS VT-I SAT SAT N/A Ground Blend Material L.

L-W Loose Members 11 ID Undercut ri El

[]

Cracks Fvi EI]

Corrosion Build-up Li i

I[]

Corrosion F]

[]

Gouges S/1 L

[

Gouges

[]

f]

Li Evidence of Leakage H

D L r []

Thread Damage

[i Li Arc Strikes Li 1-1 W

Deformation H

L_

Cracks El W

Protective Coating Ei l_

Other-F%

L i

[

Evidence of Leakage EL L[

Other **i[

Li Provide details on unsat areas by use of supplemental data sheet.

- Provide details on other areas examined Comments Washer 30 UNSAT due to ding/metal role back of small T Washer for -3" on flat outer side edge, photos taken

C Farley Nuclear Plant Liquid Penetrant Examination Record SHARED FNP-,-NDE-100.5 PT-F-FORM 001 Unit Component No.

Procedure/Rev./TCN

,,*h et No.

Werm er 3

-C)-MrnG-Ic, S

Page/

of ThermometerI l-Mfg/Ser. No.

Frc_.

I 4B8881 Cal. Due Date

?-"ZS -0:3 Manufacturer MACK)A "LL..,

Penetrant Materials Cleaner / Remover Penetrant Surface Temp.

83 0 F Developer Component Configuration Vn Ae a

s E _

Ind. No. I Results FDwell Time F Indication Desc. / Exam Limitations I etc.

N/A NI "q t Type S kD. -S SP.L-S?

S kD -S2 Batch 6 3TOI Bk C 6:.1o Bk.

% of Length Coverage oo(

0 Date

% of Area Coverage oo 010 q-Z3-02 Remarks Se aIF 2o-

\\

9 o

_8Z A P.EA Ad_

_]7-tez Primary Examiner ASNT Level Initials Assistant Examiner ASNT Level Initials Non-Technical Review C NDE Level 1I/111 Review Date Percentage of Code ANII Review i.

9 "Z7-Coverage Date Date Date Revision 6.

FL u.s L' i

Farley Nu.

lant Visual Examination Record VT-1 SHARED)

FNP-0-N

.00.21 Southern Nuclear Operating Company Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-W31 APR1-1300 S02F2V083 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA El Yes L B/W

[

Yes Sel 1/32" Division (Scale) 1] Direct El Video Procedure No.

FNP-0-NDE-100 21 F-No Ni Color F

No

[v' 1/32" Line (Gray Card)

F] Remote Revision No.

1 0 I

N/A Equipment Lighting Tools Examiner/initial John W Bell Level SMirror FI N/A I

Ambient F

Scale F-Depth Gauge F] Level Sig. A*"9-t c

III Examiner/lnitial N/A Level r.]Magnifier Flashlight F-Micrometer

-1e Comparator

]-_

sig.

N/A F-CCTV

_ Droplight Li Caliper

[71 Weld Gauge

{ -J_

Date (Month-Day-Year)

__________________________9/20/9/20200

UN-

UN L-WELDS AND BASE MATERIAL VT-1 SAT SAh N/A D] BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material E]

1 -1

,Y Loose Members Li F-]

Undercut Li

[-_1 V!

Cracks

((

Li Corrosion Build-up Li

[P Fvi Corrosion H

Li Gouges Li I I W]

Gouges LIj F-1 II Evidence of Leakage

[-1 L

"j Thread Damage

-][-

L]

Arc Strikes i

V

[]

Deformation

[J 1-]

I_

Cracks EL 0-

[

Protective Coating

[I Ji Li Other-*

0

[1

[]

Evidence of Leakage Ui

[_-

Other

[I Fl fl Provide details on unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments NA

Farley Ni(

11lant Visual Examination Record VT-1 SHARED

(

Plant / Unit Line NumberlExamination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-W32 APRI-1300 S02F2V084 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA

[Yes BI BAW LI Yes 17 1/32" Division (Scale)

[

Direct LI Video Procedure No.

FNP-0-NDE-100 21 F No

[] Color 7 No

- 1/32" Line (Gray Card)

L -Remote Revision No.

1 0

/ N/A Equipment Lighting Tools ExamInerflnitlal John W Bell t

. 6 Level 51g.

ý W Mirror [] N/A s

Ambient

{

Scale L-Depth Gauge LI Level SIn.r/Initia NAel Amin lLvlExamýiner/lnltial NIA Level

,Magnifier F-] Flashlight 1 Micrometer L] Comparator

[Si Slg N/A ICCTV EL Droplight L. Caliper Li Weld Gauge L-_]_Date (Month-Day-Year)

_______________________________9/20/2002

UN-

UN Li WELDS AND BASE MATERIAL VT-1 SAT Mr N/A I BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material r_

Loose Members

((]

Undercut

[I]

H 1%ý"

Cracks

.1]

L Corrosion Build-up

[

[7 1*[

Corrosion Li Li Gouges LiF e-1 Gouges

[]l Li I

Evidence of Leakage 1_

0 7n Thread Damage 0]

L Arc Strikes Li F-

[]

Deformation I-i F]

Li Cracks Li IE

[S/

Protective Coating

[l Li Li O ther -

L-

[

[ -j Evidence of Leakage F

O ther **

F --

L _I Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

Farley Nifj

'lant Visual Examination Record VT-1 SHARLo FNP-O-100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-W51 APR1-1300 S02F2V085 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA Yes B]/W L] Yes V1/32" Divison (Scale)

Direct

[

Video Procedure No.

FNP-0-NDE-100 21

/

No F-1 Color NV o

No 1/32" Line (Gray Card)

L Remote Revision No.

1 0

/

N/A Equipment Lighting Tools Examiner/Initial John W Bell Level V Mirror FI N/A

Ambient i Scale

[] Depth Gauge LI Level SCg.

.3,,.

Examinerllnitial NIA Level Magnifier Flashlight I Micrometer Comparator Sig.

N/A

! CCTV L1A Droplight

[ I Caliper I I Weld Gauge

[-_

Date (Month-Day-Year)

L I

Droplight

[___e_(_onh___yYa___9/20/2002

"*UN-

UN I

WELDS AND BASE MATERIAL VT-1 SAT fAr N/A BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material L-w Loose Members Undercut

[1 F]

W Cracks

[-

[

Corrosion Build-up L

I-I- -,

Corrosion F-]

F]

[_

Gouges L

Li Gouges

[

[-

LI Evidence of Leakage I

D LI r,

Thread Damage L-I Arc Strikes 0]

Li-vI Deformation F- /- ]I Cracks

[]

S]

Protective Coating F]

-]

I_]

Other-F]

L Rj Evidence of Leakage 0

Li_ý.

I Other **

LI LIJ

,/

Provide details on unsat areas by use of supplemental data sheet

- Provide details on other areas examined Comments NA

Farley N(

1lant Visual Examination Record VT-1 C

SHARED C.

FNP-0-K 100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APRI-1300-W52 APRI-1300 S02F2V086 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA EI Yes 1 3/N Vl Yes 1/32" Division (Scale)

[

Direct Video Procedure No.

FNP-0-NDE-100 21 7% No

[.] Color No 1/32" Line (Gray Card)

LI Remote Revision No.

1 0

/ N/A Equipment Lighting Tools Examiner/Initial John W Bell Level

-Mirror D] N/A

[] Ambient Sil Scale 1i Depth Gauge E] Level

'a' C3enPi...

(jo.

Examlnerllnitlal N/A Level r, 1 Magnifier

[- Flashlight Li Micrometer F1-Comparator El_

Sig.

N/A LJ CCTV EL Droplight I]

Calper F] Weld Gauge Date (Month-Day-Year)

______________________________9/20/2002

UN-

UN

[I WELDS AND BASE MATERIAL VT-1 SAT S$r N/A

[1 BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material F-I}

F]

/

Loose Members F]

M Pi Undercut 7

-j

-v Cracks 7%i i0 Corrosion Build-up Wi F]

[]

Corrosion H]

[-

1_1 Gouges 0-L.

[]J Gouges E-]

L Evidence of Leakage L

0

[3

[

Thread Damage

[]

LU Arc Strikes

[I]

J

[

Deformation F-1 LI Ii Cracks F.]

Li

[

Protective Coating E]

El Other" E_*1 i

[

Evidence of Leakage 0

F]

Other **

Li

[]

[

Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

Farley Nuc,-

'lant Visual Examination Record VT-1 SHARED FNP K" 100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-W53 APRi-1300 S02F2V088 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA F] Yes F-1 B/W I] Yes 1/32" Division (Scale) r-- Direct LJ Video Procedure No.

FNP-0-NDE-100 21 7V No I I Color FhI No i

1/32" Line (Gray Card)

Fl Remote Revision No.

10

/ N/A Equipment Lighting Tools Examlner/lnitial John W. Bell 4%

Level V Mirror F] N/A

,9 Ambient F

Scale i

Depth Gauge

-J Level sg AoJ I Iw Fl Magnifier 1l Flashlight 1i Micrometer

[1 Comparator t

Examiner/Initial NIA Level IV1Fahih F]ClprWlGag Sig.

N/A 17 CCTV F I Droplight i]

Calper Li Weld Gauge

[I ]_Date (Month-Day-Year) 9/20/2002

UN-

UN EL WELDS AND BASE MATERIAL VT-1 SAT M*r N/A 1 BOLTS, STUDS, AND WASHERS VT-I SAT SAT N/A Ground Blend Material

[-1

[--i Loose Members E7 W-Li]

Undercut F 1

]

FI Cracks

[

F F]

Corrosion Build-up i

F 1i F"

Corrosion

[- I 1]

Gouges Li Li

[i Gouges rI F1 Evidence of Leakage D-

[

W

[]

Thread Damage

((J D

Arc Strikes

[_-

V1 -

Deformation

[1

[1 Cracks

[E E]

1--/

Protective Coating L:I F_]

Other-l3 []

Evidence of Leakage

]

Li--

Other **

LI LI

[']

Provide details on unsat areas by use of supplemental data sheet

Provide details on other areas examined Southern Nuclear 0 eratin Con Comments NA

Farley NJ(,

?lant Visual Examination Record VT-1 C.

SHARED C

FNP-0-N 100.21 Southern Nuclear Operating Company Plant / Unit Line Number/Examination AreaSWeld No.

Drawing Number Sheet Number Farley I

2 APRt-1300-W54 APR1-1300 S02F2V089 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WOIWA NA F] Yes Li BNV El Yes W 1/32" Division (Scale)

] Direct Video Procedure No.

FNP-0-NDE-100.21 I, No L-Color Vj No F-/ 1/32" Line (Gray Card) i Remote Revision No.

1 0 I N/A Equipment Lighting Tools Examinerllnltlal John W Bell Level

[mirror DN/A F-1 Ambient

[% Scale L]Depth Gauge LiLevel Sig. A*

W 1

III Examiner/Initial NIA Level

. 'Magnifier P Flashlight U-Micrometer L. Comparator Sig Sig.

N/A L C CCTV Droplight

] Caliper LI Weld Gauge

[.1 Date (Month-Day-Year)

__________________________________912012002

UN-

UN F] WELDS AND BASE MATERIAL VT-I SAT SAT N/A V

BOLTS, STUDS, AND WASHERS VT-I SAT SAT N/A Ground Blend Material r I Li Loose Members F-I

[-W_

Undercut F]

[]

[J Cracks

[1 F]-

L]

Corrosion Build-up F]

[ I

[1 Corrosion F./I I-]

F]

Gouges I

_i Gouges I-_

[]

Evidence of Leakage H

Li-L%

Thread Damage

[]

Arc Strikes Li H

]

Deformation F]

H Cracks n

F]

/

Protective Coating W

F-L-]

Other*"

D_

i Li F*i Evidence of Leakage E]

Li Other

F.

Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA Revision 1.0

Farley NL.

'lant Visual Examination Record VT-1 C

SHAREdrL FNP.0.N 100.21 Southern Nuclear Operating Company Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APRI-1300-W55 APRI-1300 S02F2V090 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA F] Yes L B3N IV Yes 1/32" Division (Scale)

Direct L Video Procedure No.

FNP-0-NDE-100 21 1'j No F I Color i No r

1/32" Line (Gray Card) 1i Remote Revision No.

1 0

/

N/A Equipment Lighting Tools Examlner/lnltlal JohnW Bell 6

W l

Level W1 Mirror FN/A W1 Ambient W Scale 1 Depth Gauge LJ Level Slg't,1._

M Examlnerllnitlal N/A Level 1,1Magnifier W1,i Flashlight

-] Micrometer I Comparator L-.

Sig.

NIA

! CCTV L0- Droplight L] Caliper I - Weld Gauge

[.i Date (Month.Day.Year) 9/20/2002

UN-

UN F] WELDS AND BASE MATERIAL VT-1 SAT

..NT N/A 1 BOLTS, STUDS, AND WASHERS VT-I SAT SAT N/A Ground Blend Material El

[

7 Loose Members E]

F-i Undercut

[71 El 7V Cracks W[1

[

Corrosion Build-up

[-1 L

1_

1}

Corrosion ri E]

Gouges LI E

L, J Gouges UL L1 Evidence of Leakage F.

F]

Thread Damage I

F-]

Arc Strikes 17-Li

[

Deformation

[J I_

Cracks F]

FJ Protective Coating

[]

E]

Other-*

F]

E]

W Evidence of Leakage

[F]

]_

Other **

L i

Provide details on unsat areas by use of supplemental data sheet.

- Provide details on other areas examined Comments NA

Farley NL*

lant Visual Examination Record VT-I SHARED FNP-0-K 100.21 Plant / Unit Line Number/Examination Area/Weld No.

Drawing Number Sheet Number Farley I

2 APRI-1300-W56 APR1-1300 S02F2V091 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA 11 Yes ED BNtv El Yes 1/32" Division (Scale)

[1 Direct Video Procedure No.

FNP-0-NDE-100 21

,V No Color No F*

1/32" Line (Gray Card)

H Remote Revision No.

1.0

/

N/A Equipment Lighting Tools Examiner/Initial John W Bell 6%j s Level

""Mirror El N/A J

Ambient L

Scale

[]

Depth Gauge F] Level 51g I

Examiner/Initial N/A Level r-]Magnifier Flashlight El Micrometer F-H Comparator Sig.

N/A

-] CCTV

[-] Droplight El Caliper L] Weld Gauge E]

Date (Month-Day-Year)

____________________9/20/2002

UN-

UN i_ WELDS AND BASE MATERIAL VT-I SAT MT-N/A

[F BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material Li

[_J W

Loose Members n_

[-]

Undercut I-j El y

V Cracks L-L Corrosion Build-up Vr 1 Corrosion Gouges LI-

[2 ]

J Gouges H

Evidence of Leakage L]

F-Thread Damage

[0

[

Arc Strikes

[1 Li 1

Deformation

[r

[-1 i-1 Cracks

-]

H Protective Coating F-]

[i Other-*

[]

F]

[

Evidence of Leakage

-i L_]

Provide details on unsat areas by use of Other Ei f

supplemental data sheet.

- Provide details on other areas examined Comments NA

Farley NC*.

?lant Visual Examination Record VT-1 SHARED C

FNP-0-r\\

100.21 Souher Nu~nr("

-*r**ln rnmJn Plant / Unit Line Number/Examination ArealWeld No.

Drawing Number Sheet Number Farley 2

APRI-1300-W57 APR1-1300 S02F2V092 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO / WA NA F] Yes Fl BNV L] Yes 1/32" Division (Scale)

[

Direct L] Video Procedure No.

FNP-0-NDE-100 21 F-1 No

[-] Color V] No

([ 1/32" Line (Gray Card)

F] Remote Revision No.

1.0

/ N/A Equipment Lighting Tools Examinertinitial John W. Bell tw Level SMirror [I N/A WJ Ambient 7

Scale

[I] Depth Gauge F] Level sigl 0

W Q Ill Examiner/initial N/A Level Magnifier VJ Flashlight F] Micrometer F Comparator F]

Sig.

N/A

[]CCTV F] Droplight F] Caliper F] Weld Gauge Li Date (Month-Day-Year)

________________________________9/20/2002

"*UN-

UN F] WELDS AND BASE MATERIAL VT-1 SAT N/A P

BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material D]

F]

R Loose Members W]

-]I Undercut 0]

L 7%

Cracks

[1 F

Corrosion Build-up F-]

El We Corrosion L.

-]

Gouges W]

F]

Gouges 11

[]

LI Evidence of Leakage 1]

[

7 V

Thread Damage

'I --

Arc Strikes 7]

F]

Deformation

-J

[1 F-]

Cracks E-F]

1 Protective Coating Li E]

Other-F]

F]

W Evidence of Leakage F]

W]

Other*

F]

[-]

Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Cnmment*

MA VVHHIDHD*IIL*

I!*

Farley NuC,.

lant Visual Examination Record VT-1 SHARED FNP-0-"

100.21 Plant / Unit Line Number/Examination ArealWeld No.

Drawing Number Sheet Number Farley

/

APR1-1300-W58 APRI-1300 S02F2V093 REACTOR VESSEL WASHERS Photos Sketch Resolution Technique WO I WA NA F] Yes Di BANV L Yes 1/32" Division (Scale)

[

Direct Video Procedure No.

FNP-0-NDE-100 21 F No

[E_-

Color F-/ No 1/32" Line (Gray Card)

L] Remote Revision No.

1 0 I

N/A Equipment Lighting Tools Examiner/initial John W Bell V.j Level 7v Mirror E] N/A

[I Ambient R

Scale Li Depth Gauge EL Level S

III Examiner/lnitial N/A Level f

Magnifier

[r] Flashlight

[i Micrometer

[1 Comparator L-SIg.

N/A I-.i CCTFV L] Droplight L

Caliper

[-L Weld Gauge 0-_

Date (Month-Day-Year)

CCT El Doplght ate(Moth-D9/20/2002

UN-

UN F[ WELDS AND BASE MATERIAL VT-I SAT

.7 N/A R

BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material S

Loose Members L]

[-i Undercut

-]

L-

[]

Cracks

[]11

[F Corrosion Build-up i

iF

[4J Corrosion W,

[

Gouges EJ F-;

[_j Gouges F

i*

EI Evidence of Leakage LI L_

[J Thread Damage 1%7-

-]

D1 Arc Strikes t]

[-

Deformation fi]

11 LI Cracks

[]

[

Protective Coating LI Li Other" F]

Evidence of Leakage LI

]I Other Pi

-i Provide details on unsat areas by use of supplemental data sheet Provide details on other areas examined Comments NA

EXAMINATION

SUMMARY

FOR UNIT 2 INTERVAL 3 PERIOD 1 OUTAGE 1 DRAWING APR1-1300C REACTOR VESSEL CLOSURE HEAD CONOSEAL BOLTING ITEM NO VOLUMERIC SURFACE VISUAL REMARKS NI NRI RI NI NRI RI NI NPI RI PEN 51 X

i fi w

I i

0 m

ff m

i i

0 i

i i -

m

Nlii r

Farley Nuc Plant Visual Examination Record VT-1 SHARE SH A

REuDe OpertM FNP-l V

-ing 0ompany Plant I Unit Line NumbertExamination Area/Weld No.

Drawing Number Sheet Number Farley

/

2 APR1-1300-PEN 51 APR1-1300 S02F2V165 CRD HOUSING BOLTING I

Photos Sketch Resolution Technique WOIWA N/A El Yes

[2B/W El Yes F

1/32* Division (Scale)

Li Direct Procedure No.

FNP-0-NDE-100 21 rj No LIColor r No El 1/32" Line (Gray Card)

DRemote Revision No.

1.0

/ N/A Equipment Lighting Tools ExamInerlinltlal TM.. Carrahe Level LIMirror J

N/A i Ambient

_i Scale

[]

Depth Gauge

[] Level II C

Examiner/inltlal N/A Level

[2 Magnifier

[2 Flashlight

[2 Micrometer

[2 Comparator

[2 _Sig.

N/A

[E CCTV El Droplight

[2 Caliper LI Weld Gauge

[]

Date (Month-Day-Year)

_____________________________10/7/2002 "UN-

UN

[2 WELDS AND BASE MATERIAL VT-1 SAT SAT N/A

[I BOLTS, STUDS, AND WASHERS VT-1 SAT SAT N/A Ground Blend Material EJ 0

R]

Loose Members

[E

[2 Undercut

[2

[D r]

Cracks

/[1

[

Corrosion Build-up,

[2

[-

Corrosion Gouges

[2

[

Gouges 0[

[2 Evidence of Leakage

[2

[

S R

Thread Damage

[2

[2 Arc Strikes

[]

[2 R]

Deformation 0[

[2 Cracks

[2

[2 7j Protective Coating

[]

[2

[2 Other-"

[2

[

V

[

Evidence of Leakage

[2

[R Other"**

[2

Provide details 0 unsat areas by use of supplemental data sheet.

Provide details on other areas examined Comments Bolting was removed for examination.

Revision 1.0

.r j

FNP

"" :-100.21

1.2

EXAMINATION

SUMMARY

FOR UNIT 2 INTERVAL 3 PERIOD 1 OUTAGE 1 DRAWING APR1-2100A PRESSURIZER NOZZLE TO VESSEL WELDS ITEM NO VOLUMERIC SURFACE VISUAL REMARKS NI NRI RI NI NRI RI NI NRI RI 9

X X

9IR X

10 X

X 10IR X 4-4-I 4-4-I i

i i

m i

i 0

i i

5 m

i i

w 9

v w

i 1

0

I

WELD EXAMINATION

SUMMARY

SHEET Sheet No S02F2S079 Weld Number:

APR1-2100-9 Examination Area:

PRZ UPPER HD. TO NOZZLE WELD Fgmure No.

Procedure Cal Block Exam Requirements APR1 -2100 FNP-0-NDE-100.11 APR-7 B-D/B3.1 10/

FNP-0-NDE-100.34 The following data sheets are included in this package Data Sheet No.

Angle Results Remarks S02F2M001 NI S02F2U012 45 NI S02F2U013 60 NI S02F2U015 70 NI Comments:

SUPPLEMENTAL SURFACE EXAMINATION. RR-6 75% ASME CODE COVERAGE.

(Describe limitation In comments)

Percent on required area examined - Surface Percent of required volume examIned - Volumetric Relief Request Number/Required?

Code Case used (if applicable)

IER Number (if applicable)N ITS Review:-

Date:______

100 75 RR-6 NA NA

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SH.. ED FNP-0-NDE-100.34 So..the.....

r-....... ( v*,

Y Unit Sketch/Component Number Date Sheet No.

2 APR1-2100-9 9/20/2002 S02F2U012 Page _(

of ProcedurelRev./TCN Couplant/Batch No.

ThermometerSNICal Due Date Linearity Sheet No.

FNP-0-NDE-100 34 60 N/A Ultragel II 01125 48890 2/5/2003 S02F2L005 Instrument Search Unit Calibration Block Axial Scan Calibration Circ Scan Calibration Instrument Staveley / SONIC 136-Transducer Mfg.

Panametrics Cal. BIk. No APR-7 Cal.

Signal Sweep Wmax Cal.

Signal Sweep Wmax Serial No. 136-905K Serial Number 267694 Thickness 35 Refl.

Amp.

Div.

Refl.

Amp.

DIv.

1/4 80 20

.88 1/4 80 2 0 88 Axial dB Circ dB Model No.

ANGLE Cal. Temp 94 OF 1/2

.60 o 4 0 1 80 1/2 60 4 0 1 80 3/14 45 60

-265 3/4 45 6 0 265 Reference 40 40 Size I No.

5"X1" Shape Rect Cal. In 8"15 10 80 35 5 T

10 80 350 1T 10 8 0 3 50-1T 10 8 0 3 50 Scanning 52 52 FrequencylMode 2.25/Shear Cal. Chk.

1305 5/4 26 100 N/A 5/4 26 100 N/A "A" Dimension

.75 Calibration Remarks:

Reject OFF Cal. Out 15 30 Nom Angle 45° N/A Frequency 225 45*

Ref. BIk. No.

A01146 Mode P/E Cable Type I No. Conn. RG174/0 Reflector/dB SDH / 40 Damping 500 OHMS Cable Length 12' Amp/Sweep 40 % / 2.0 Comp Temp.

94

°1 Configuration -

PRZ UPPER HD TO NOZZLE WELD Wo Loc.

Lo Loc.

C Weld C/L TDC Scan Results Ind Length Reference Measurement Sweep Positlon Thickness Dir.

NI NRI I

NO. DAC Ll Lmax L2 WI Wmax W2 S1 Smax S2 I"<-

C/L

>1,,

Notes:

8 5

2 0I 0

6

NA NA NA NA Examination/Limitation Remarks:

Nozzle Limits 2 Scan Tota ength Crown Width Total Length of Weld ined 1int of Perpendlcula cans (W) of Weld 47"1" 5 (L)

NL 2 (L)

NL-7 and 8 (W)

NL 5-From NL to NL 2-From

u.

Extent of Parallel Scans (L 3,4 to NL From (5)

NL to (2)

NL V!*'-rb*,*J,"t Level,,

11 4

Joseph 0 Funyak als Assistant Examiner Level Initials Non-Technical Review

"Paul valden

,1 G.ku4A*,hoIo 9o Date Percentage of &4 ANII Review Date Cý.esode Coverage 6.0 Revision 6.0 Vvv

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SH( -RED FNP-0-NDE-100.34 Southern Nuclear Operating Company Unit Sketch/Component Number Date Sheet No.

2 APR1-2100-9 9/20/2002 S02F2U013 Page f of ProcedurelRev./TCN CouplantlBatch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 34 6.0 N/A Ultragel II I

01225 48890 2/5/2003 S02F2L005 Instrument Search Unit Calibration Block Axial Scan Calibration Circ Scan Calibration Instrument Staveley / SONIC 136 Transducer Mfg.

Panametrics Cal. Bk. No APR-7 Cal.

Signal Sweep Wmax Cal.

Signal Sweep Wmax Serial No. 136-905K Serial Number 276054 Thickness 35 Refl.

Amp.

Div.

Refl.

Amp.

Div.

1/4 80 20 1 67 114 80 20 1.67 Axial dB Circ dB Model No.

A403S Cal. Temp 94 °F 112 50 4 0 3.22 1/2 50 450 3O22 3/4 35 6 0 482 3/4 35 60 4 82 Reference 47.2 472 Size I No.

5"Xl" Shape Rect Cal. In 820 1

80 6

12 80 641 IT 12 8 0 641 1T 12 80 641 Scanning 592 592 Frequency/Mode 2.251 Shear Cal. Chk.

1315 5/4 16 100 N/A 5/4 16 100 N/A "A" Dimension

.75 Calibration Remarks:

Reject OFF Cal. Out 15'32 Nom Angle 600 NA Frequency 2 25 Ref. B~k. No.

A01146 Meas Angie 58 ° e.Bk o

~

4 Mode P/E Cable Type I No. Conn. RG174 /0 ReflectorldB SDH / 47 2 Damping 500 OHMS Cable Length 12' Amp/Sweep 55 % I 1 8 1t94 V44 IU1dUonI PRZUPPER HD TO NOZZLE WELD Scan....

Results Fd Length Dir.

NI I NRIt RI No. DAC LI Lmax L2 8

7 NA 7

.NA 5

NA 2

NA Reference Measurement WI Wmax W2 I Wo Loc.

Weld C/L Sweep Position SI Smax S2 1"<

Lo Loc.

TDC Thickness C/L

"-'>1" Notes:

ExaminationlLimitation Remarks:

Nozzle Limits 2 Scan Total Length Crown Width of Weld 47" 1"

Total Length of Weld Examined Extent of Perpendiculal Scans (W)

Extent of Parallel Scans (L) 5 (L)

NL 2 (L)

NL 7 and 8 (W)

NL 5-From NL to NL 2-From 34"_to NL From (5)

NL to (2)

NL Primary Examiner Joseph D Funyak SNC NDE Level.l Assistant Examiner Level Initials Non-Technical Review Paul Vaiden 11Gq i,~4I Date Percentage of I I Review

_ C o d e C o v e r a g e Date Date 7/Revii z6 Revision 6 0 IN 5 0/1) C

.JP Qotx I ^,r^l I--l1:*1.

l

Farley Nuclear Plant Ultrasonic Calibration and Examination Record S

_,RED FNP-0-NDE-100.34 Southern Nuclear (nirFNi-n 0nmn3n Unit SketchlComponent Number Date Sheet No.

2 APR1-2100-9 9/20/2002 S02F2UO15 Page_1-of ProcedurelRev./TCN couplantlBatch No.

[ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 34 60 N/A Ultragel II I

01225 48890 2/5/2003 S02F2L005 Instrument Search Unit Calibration Block Axial Scan Calibration Circ Scan Calibration Instrument Staveley /SONIC 136 Transducer Mfg.

Panametrics Cal. BIk. No APR-7 Cal.

Signal Sweep Wmax Cal.

Signal Sweep Wmax Serial No. 136-905K Refl.

Amp.

Div.

Refl.

Amp Div.

Serial Number 267701 Thickness 3 5 1/4 80 40 247 1/4 80 4 0 2.47 Axial dB Circ dB Model No.

ANGLE Cal. Temp 94 "F 1/2 45 80 4 72 1/2 45 8 0 4.72 Reference 504 504 Size I No.

.5"X1" Shape Rect.

Cal. In 8 25 Scanning 62.4 62 4 FrequencylMode 2 25 / Shear Cal. Chk.

1330 "A" Dimension 90 Calibration Remarks:

Reject OFF Cal. Out 15"34 Nom Angle 70

NA Frequency 225 70 Ref. BIk. No.

A01146 Mode P/E Cable Type / No. Conn. RG174 / 0 Reflector/dB SDH /50 4 Damping 500 OHMS Cable Length 12' Amp/Sweep 55 % I 1 9 Co'mn Termn 1-rf,',,'*~

H

____,l 94 4

0 IVII

'.II'/-

PRZ UPPER HD TO NOZZLE WELD Scan Results Ind Length Reference Measurement Dir.

I NRI I

N o. DAC LI Lmax L2 Vl WI max W2 8

r*_

NA 7

NA 5

NA 2

NA Wo Loc.

W Lo Loc.

___Weld O/L

__TDC Sweep Position Thickness S1 Smax S2 I"<-

C/L

->1" Notes:

ExamlnationlLimitation Remarks:

Nozzle Limits 2 Scan qhCl.L

ofl Lengtn Crown Width Total Length of Weld Examined Extent of PelpendlcularScan (W) of Weld 4"

5 (L)

NL 2 (L)

NL 7 and 8 (W)

NL 5-From NL to NL 2-From Extent of Parallel Scans (L) 3.4" to NL From (5)

NL -- to (2)

NL Primary Examiner Level Joseph D Funyak 11 SNC NDE Level I/111 Review

-A II kin J

Assistant Examiner Level Initial c

Paul Valden II 6ýW

. Dae.

Percentage of N-- -Revic Code Coverage s I Non-Technical evi w Date IVY Date Re visio 6

Z Revision 6 0 WL, r -C(. C,. o-1

C Farley Nuclear Plant Magnetic Particle Examination Record S

SHARED FNP-O-NDi:-100.11 MT-F-FORM 002

-Southern Nuclear Operating Company Unit Weld Number 2

APR' Thermometer Mfg /Ser. No.

PTC

/

Cal. Due Date 2/5/2003 Surface Temp.

1-2100-9 48890 98 0 F

Component Configuration PRZ UPPER HD. TO NOZZLE WELD Ind. No.

Results NA NI NA Procedure/Rev./TCN FNP-0-NDE-100.11 Magnetizing Yoke Mfg.:

Magnaflux to Serial No.:

A999638 Pole Spacing:

8 "r Field Indicator SIN:

MFI-02 Power AC

~40 N/A 02F2001 Page I of I Sheet No.

S02F2M001 Mfg.:

Batch Num Color:

Field Indicator Acceptable [YIN]

Yes j

pe:

% of Length Coverage

% of Area Coverage Indication Desc. / Exam Limitations I etc.

MT Materials Magnaflux ber:

95H062 Red N/A 100 Date 100 9/17/2002 Remarks NA Remarks: NA 45C.U S

(_

Primary Examiner ASNT Level Initials Assistant Examiner ASNT Level -I Initials Non-Technical Review Date John W. Bell If j

(., J Joseph D Funyak

_II AAA__C &

(.

q SNC NDE Leyel II/111 Review _

Date Coverage aANtiRevew Dat

-Revi*.nN Revision 4.

/ 40

/ N/A

WELD EXAMINATION

SUMMARY

SHEET Sheet N.

S02F2S077 Weld Number:

APR1-2100-91R Examination Area:

PRZ NOZ-INSIDE RADIUS Fiure Na Procedure Cal Block Exam Reauirements APR1-2100 FNP-0-NDE-100.38 ALA-38 B-D/B3.120/

The following data sheets are included in this package Data Sheet No.

Angle Results Remarks S02F2U006 20 NI Comments:

(Descnrbe limitation In comments)

Percent on required area examined - Surface NA Percent of required volume examined - Volumetric 100 Relief Request Number/Required?

NA Code Case used (if applicable)

NA IER Number (if applicable)

NA ITS Review.---

I MI&=

7 Date:___________

V

Farley Nuclear Plant Ultrasonic Calibration and Examination Record S(

-EED FNP-0-NCE-100.38 SouthernNuclear O

-erainaCompany Unit SketchlComponent Number Date Sheet No.

2 APR1-2100-91R 9/17/2002 S02F2U006 Page 1 of Procedure/Rev.[TCN CouplantlBatch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 38 20 N/A Ultragel II I

01125 48890 2/5/2003 S02F2L001 Instrument Search Unit Calibration Block Axial Scan Calibration Circ Scan Calibration Instrument Staveley/SONIC 136 Transducer Mfg.

KBA Cal. Bik. No ALA-38 Cal.

Signal Sweep Wmax Cal.

Signal Sweep Wmax Serial No. 136-905K Serial Number L30469 Thickness 601 Refl.

Amp.

Div.

Refl.

Amp.

Div.

NA A

80 30 265 Axial dB Clrc dB Model No.

SWS Cal. Temp 79 °F B

5-.0 2-C 60 570 3 24 Reference NA 638 Size/ No.

5' Shape Round Cal. In 1445 C

40 70 399 Scanning NA 69,8 Frequency/Mode 2 25/Long Cal. Chk.

1545 "A" Dimension 7

Calibration Remarks:

Reject OFF Cal. Out 17.55 Nom Angle 20 0 Wmax from end of block Frequency 225 Ref. Blk. No.

A01146 Meas Angie 20 ° e.Bk N.

A14 Mode P/E Cable Type / No. Conn. RG174 / 0 Reflector/dB 2"Rad/53 8 Damping 200 OHMS Cable Length 12' Amp/Sweep 80 % I 8 I.-

Comp,emp.

98

°1

.onmiguriuon -

PRZ NOZ-INSIDE RADIUS Scan Results Ind T%-

engt Dirj NI NRI L-RI No.:DACJ LI Lmax 8

NA 7

NA L2 Wo Loc.

L Lo Loc.

NA NA Reference Measurement Sweep Position Thickness W1 Wmax W2 S1 Smax S2 I"<--

C/L

->1" I

Notes:

Examination/Limitation Remarks: tb 1; A*,

.;&.. S A6J Total Leng of Weld gth Crown Width TTotal Length of Weld Examined I Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L)

NA NA 5(L)

NA 2 (L)

NA 7 and 8 (W)

NA 5-From NA to NA 2-From NA to NA From (5)

.NL__to (2)

NL Primary Examiner Level Injials I Assistant Examiner Level Initials Joseph D Funyak II W_'o Bell___

A11*(

SNC NDE Level 111111 Revi*w

-Date Percenta of 1

Review

,CodeCoverage, S.

e---g-j-

.i..

Non-Technical Review Date q.....

.q_

_-_ o Date Revision 2 0 f -V, *To

Farley Nuclear Plant SHARED

Itrasonic Performance Record for Inner Radius Examinations FNP-0-NDE-100.38 Southern Nuclear Operating Company

\\'.-'

Plant/Unit 1~~.~~.

I Farley 2

U.UUut rage -1 U

Instrument Manufacturer iModel Serial No.

Staveley SONIC 136 136-905K Search Unit Type/Manufacturer Size Frequenc Angle iSra o

.5" 2.25 MHz 20 o L30469 Search Unit Cable Type Length I Number Connectors Calibration Block Serial No. And Thickness RG 174 12' I

0 ALA-38 1

6.01 Couplant Batch Number Demonstration of Flaw Detectability Acceptable Ultragel I1

/ 01125 BEAM SPREAD MEASUREME Notch A Maximum Near Far Notch B Maximum Near Far Notch C Maximum Near Far ENTS 100%

2.56 Surface Distance 50%

N/A 20%

N/A 100%

3 07 Metal Path 50%

N/A 20%

N/A N/A 236 22 N/A 303 I

2.99 N/A 283 311 NIA 317 326 324 N/A N/A 402 N/A N/A N/A 304 2.82 N/A 396 394 N/A 348 367 N/A 408 415 J1 [

399 NIA N/A 495 { N/A N/A N/A 364 348 N/A 487 483 N/A 432 443 N/A j

504 510 I ______________0 Remarks:

Examiner I SNT Level Examiner SNT Level Date Joseph D. Funyak I

II Paul Valden II 9/17/2002 NDE Level I/llR view 771

/..*

Date Revision 2.0 I 1 Sheet NoJ O/'V" E-"1)I'

WELD EXAMINATION

SUMMARY

SHEET Sheet No. S02F2S078 Weld Number APR1-2100-10 Examination Area:

PRZ UPPER HD. TO NOZZLE WELD Figure No.

Procedure Cal Block Exam Requirements APRI1-2100 FNP-0-NDE-100.11 APR-7 B-D/B3.110/

FNP-0-NDE-100.34 The following data sheets are included in this package Data Sheet No.

Angle Results Remarks S02F2M002 NI S02F2U016 45 NI S02F2U017 60 NI S02F2U018 70 NI Comments:

SUPPLEMENTAL SURFACE EXAMINATION. RR-6 75% ASME CODE COVERAGE.

(Describe limitation In comments)

Percent on required area examined-Surface 100 Percent of required volume examined - Volumetric 75 Relief Request Number/Required?

RR-6 Code Case used (if applicable)

NA IER Number (if applicable)

NA ITS Rve-CDate:______

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SH-.,

7 ED

(

FNP-0-NDE-100.34 Southern Nuclear Operating Company Unit SketchlComponent Number Date Sheet No.

2 APR1-2100-10 9/20/2002 S02F2U016 Page L of 1 Procedure/Rev./TCN Couplant/Batch No.

ThermometerSNICal Due Date ILinearity Sheet No.

FNP-0-NDE-100 34 60 N/A Ultragel II I

01125 48890 2/5/2003 S02F2L005 Instrument Search Unit Calibration Block Axial Scan Calibration Circ Scan Calibration Instrument Staveiey / SONIC 136 Transducer Mfg.

Panametrics Cal. Bk. No APR-7 Cal.

Signal Sweep Wmax Cal.

Signal Sweep Wmax Serial No. 136-905K Refl.

Amp.

Div.

Refl.

Amp.

Div.

Serial Number 267694 Thickness 3 5 1/4 80 20 88 1/4 80 20

.88 Axial dB Circ dB Model No.

ANGLE Cal. Temp 94 OF 1/2 60 40 1 80 1/2 60 4 0 1 80 3/4 45 6.0 2 65 3/4 45 6"0 2 65 Reference 40 40 Size / No.

5"X1" Shape Rect.

Cal. In 8:15 3..-

0 8.0 6.- 3.50 4T 1

0 650 1T 10 8 0 3.50 1T 10 8 0 3 50 Scanning 52 52 Frequency/Mode 2 25/ Shear Cal. Chk.

1340 5/4 26 100 N/A 5/4 26 10 0 N/A "A" Dimension

.75 Calibration Remarks:

Reject OFF Cal. Out 15 30 Nom Angle 450 NA Frequency 225 45*

Ref. Bk. No.

A01146' Mode P/E Cable Type/ No. Conn. RG174/0 Reflector/dB SDH / 40 Damping 500 OHMS Cable Length 12' Amp/Sweep 40 % / 2.0 comp Temp.

94 Configuration -

PRZ UPPER HD. TO NOZZLE WELD Scanf Results id Length Dir.

Nil NRI RI No. DAC LI Lmax L2 I

Reterence Measurement WI Wmax W2 I Wo Loc.

S1 La Loc.

Weld C/L Sweep Position Smax Thickness 1"<-

C/L S2 TDC

->I" INotes:

I_,

NA NA NA NA Examination/Limitation Remarks:

Nozzle Limits 2 Scan I77O~

r....

Crown

\\ r.% -

.F~

it Tu*--

Total Length Crown Width Total Length of Weld Examined Extent of Perpendicular Scas (W)

,l Extent of Parallel Scans (L) of Weld 47 1"

5 (L)

NL 2 (L)

NL 7 and 8 (W)

NL 5-From NL to NL 2-From 3 4" to NL From (5)

NL to (2)

NL Primary Examiner Level In Lals I Assistant Examiner Level Initials I Non-Technical Review I Datar Joseph D Funyak SNC NDE Level I1111 F II

(* yo Paul Valden II 6?V Date Percentage of ANII Review a

L 1-2.1-01, Code Coverage 7r 1%ILOCO4OiŽIZC

R ite 6 Revision 6 0 I.,

8 7

5 2

Farley Nucle Plant Ultrasonic Calibration and Examination Record SH'. "ED FNP-0-NDE-100.34 Southern Nuclear Operating Company Unit Sketch/Component Number Date Sheet No.

2 APR1-2100-10 9/2012002 S02F2U017 Page 1 of J Procedure/Rev./TCN Couplant/Batch No.

ThermometerSNlCal Due Date Linearity Sheet No.

FNP-0-NDE-100 34 60 N/A Ultragel II I

01125 48890 2/5/2003 S02F2L005 Instrument Search Unit Calibration Block Axial Scan Calibration Circ Scan Calibration Instrument Staveley /SONIC 136 Transducer Mfg.

Panametrics Cal. BIk. No APR-7 Cal.

Signal Sweep Wmax Cal.

Signal Sweep Wmax Serial No. 136-905K Refl.

Amp.

Div.

Refl.

Amp.

Div.

Serial Number 276054 Thickness 3 5 1/4 80 20 167 1/4 80 20 167 Axial dB Circ dB Model No.

A403S Cal. Temp 94 °F 12 50 4 0 3 22 1/2 50 4 0 3 22 1/4 35 60 4.82 3/4 35 60 482 Reference 47.2 472 Size I No.

.5"X1" Shape Rect Cal. In 8:20 3/

12 6 0 64182 3T 3 180 641 IT 12 80 641 1T 12 80 641 Scanning 59.2 592 Frequency/Mode 2.25 / Shear Cal. Chk.

1355 5/4 16 100 N/A,-

5/4 16 100 N/A "A" Dimension

.75 Calibration Remarks:

Reject OFF Cal. Out 15 32 Nom Angle 600 N/A Frequency 225 58 Ref. Bk. No.

A01146 Mode P/E Cable Type I No. Conn. RG174 / 0 Reflector/dB SDH /472 Damping 500 OHMS Cable Length 12' Amp/Sweep 55 % / 1.8 Comp Temp.

94 Configuration -

PRZ UPPER HD TO NOZZLE WE ScanI Results

,nd-%

Length Dir.

NI NRI RI INo.DAC LI Lmax L2 8

NA 7

NA 5-NA 2

NA Reference Measurement WI Wmax W2 Wo Loc.

Weld C/L Sweep Position SI Smax S2 Lo Loc.

I "<-

CDC I"- CL

->I" Notes:

Examination/Limitation Remarks:

Nozzle Limits 2 Scan Total Length Crown Width Total Length of Weld Examined Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) of Weld 47" 1"

5(L)

NL 2 (L)

NL 7and 8 (W)

NL 5-From NL to NL 2-From 34" to NL From (5)

NL to (2)

NL Primary Examiner Level Joseph D. Funyak SNC NDE Level il/1l1

,qlnitials Assistant Examiner Level Paul Valden II Date Percentage of

.A,,11 ?-Z(-oz. Code Coverage Oal ANII Revie s

Non-Technical Review w

Date Date Revision 6 0

'X75' ife, pqph a

Farley Nuclear Plant Ultrasonic Calibration and Examination Record SHý "ED FNP-0-NUE-100.34 Southern Nuclear Operating Company Unit Sketch/Component Number Date Sheet No.

2 APR1-2100-10 9/20/2002 S02F2U018 Page of Procedure/Rev.rTCN Couplant/Batch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 34 60 NIA Ultragel II I

01225 48890 2/5/2003 S02F2L005 Instrument Search Unit Calibration Block Axial Scan Calibration CIrc Scan Calibration Instrument Staveley/SONIC 136 Transducer Mfg.

Panametrics Cal. Bik. No APR-7 Cal.

Signal Sweep Wmax Cal.

Signal Sweep Wmax Serial No. 136-905K Refl.

Amp.

Div.

Refl.

Amp.

Div.

Serial Number 267701 Thlckness 3 5 1/4 80 40 2.47 1/4 80 4.0 2 47 Axial dB Circ dB Model No.

ANGLE Cal. Temp 94 °F 1/2 45 80 472 1/2 45 8 80 _

4 72 Reference 504 50 4 Size I No.

5X1" Shape Rect Cal. In 8 25 Scanning 624 62 4 Frequency/Mode 2.25/ Shear Cal. Chk.

1405 "A" Dimension

.90 Calibration Remarks:

Reject OFF Cal. Out 15.34 Nom Angle 70

NA Frequency 2Angle 70 Ref. Blk. No.

A0o 146 Mode P/E Cable Type I No. Conn. RG17410 Reflector/dB SDH/504 Damping 500 OHMS Cable Length 12' AmplSweep 55 % I 1 9

,ump I ernp.

94

%,oniiguration PRZ UPPER HD TO NOZZLE W Scan Results 1_-d Length Dir.

Ni NRI jNRI DAC LI Lmax L2 8

9 NA 7

NA 5

NA 2

NA Reference Measurement WI Wmax W2 I Wa Loc.

SI$

Weld C/L Sweep Position Smax S2 Lo Loc.

_________TDC Thickness I"<-

C/L

->1" Notes:

ExaminatlonlLimitation Remarks:

Nozzle Limits 2 Scan Total Length Crown Width Total Length of Weld Examined Extent of Perpenhnicular Scans (W)

Extent of Parallel Scans (L) of Weld 47" 1

5 (L)

NL 2 (L)

NL 7 and 8 (W)

NL 5-From NL to NL 2-From 34" to NL From (5)

NL to (2)

NL Primary Examiner Level I,-

ni inas Assistant Examiner Level Initials

' Non-Technical Review Date Joseph D Funyak 11 SNC NDE Level il/I1 7 view

, 7 n Paul Valden Date Per I

i P q-.-6 z,

C o d II centage of oeCoverage 75-ANII Review VC&td?L

Date Revision 6 0 I

I S1 9,1.{L

"7¢

-,.J

,-A

Farley Nuclear Plant Ultrasonic Performance Record SHARED FNP-0-NDE-100.34 Southern Nuclear Operating Company I

Farley I

2 Sheet No.

S02F2U009 Page __

Instrument Manufacturer Model Serial No.

Staveley SONIC 136 136-905K Search Unit Type/Manufacturer Beam Size Frequency Angle Serial No.

Panametrics 1

.5"X1" 2.25 MHz 70 ° 267701 Searcn unit LCale Type RG174 Couplant Batch Number Ultragel 1 /01125 Length I Number Connectors SI?.-./

Demonstration of Flaw Detectability of I Calibration Block Serial No. And Thickness APR-7

/

3.5 I

Acceptable BEAM SPREAD MEASUREMENT 114 T Hole Minimum (20% DAC Near)

Minimum (50% DAC Near)

Maximum Signal Minimum (50% DAC Far)

Minimum (20% DAC Far) 112 T Hole Minimum (20% DAC Near)

Minimum (50% DAC Near)

Maximum Signal linimum (50% DAC Far)

'ý-Minimum (20% DAC Far) 314 T Hole Minimum (20% DAC Near)

Minimum (50% DAC Near)

Maximum Signal Minimum (50% DAC Far)

Minimum (20% DAC Far)

Surface Distance Metal Path 157 173 232 243 2.90 1

2.92 327 330 322 358 367 3.99 441 1

469 580 610 695 715 NA NA NA NA NA NA NA NA NA NA Remarks:

NA

/o I ft" *.0

' r lal I1* *;lllk

Farley Nuclear Plant Ultrasonic Performance Record SHARED FNP-0-NDE-100.34 Southern Nuclear Operating Company Plant/Unit Farley 1

2 1

0.

0U/-1iUU1U Page __

Instrument Manufacturer Model Serial No.

Staveley SONIC 136 136-905K Search Unit Type/Manufacturer Beam Size Frequency Angle Serial No.

Panametrics

.5"XI" 2.25 MHz NA I

276054 Search Unit Cable Type RG174 Length I Number Connectors Calibration Block Serial No. And Thickness APR-6

/

5.5 Couplant Batch Number Demonstation of Flaw Detectability Acceptable Ultragel 11

/ 01125 BEAM SPREAD MEASUREMENT 114 T Hole Minimum (20% DAC Near)

Minimum (50% DAC Near)

Maximum Signal Minimum (50% DAC Far)

Minimum (20% DAC Far) 1/2 T Hole Minimum (20% DAC Near)

Minimum (50% DAC Near)

Maximum Signal linimum (50% DAC Far)

\\-JMinimum (20% DAC Far) 3/4 T Hole Minimum (20% DAC Near)

Minimum (50% DAC Near)

Maximum Signal Minimum (50% DAC Far)

Minimum (20% DAC Far)

Surface Distance 1 23 143 1.35 1.52 1.67 1.80 205 2.14 225 232 255 30 272 319 3.22 3.59 3.96 4 23 432 460 3 91 4 62 417 488 4 82 5 42 5 85 6 37 6 25 6 71 Remarks:

NA Examiner ASNT Level Joseph D. Funyak

'1

1 i1 NDE Level 11/11 Rev ' F1 Examiner N/A ASNT Level

-al ASNT Level N/A I.

/

I Date 9/18/2002 Date Revision 6.

of I Metal Path I ck

& %J

Farley Nuclear Plant Ultrasonic Performance Record SHARED FNP-0-NDE-100.34 Southern Nuclear Operating Company rlanuunit Farley

/

2 Sheet No.

S02F2U011 Page I

of Instrument Manufacturer Model Serial No.

Staveley SONIC 136 136-905K Search Unit Type/Manufacturer Beam Size Frequency Angle I Serial No.

Panametncs i

.5"X1" 2.25 MHz 45° 267694 Searcn unit Cable Type Length I Number Connectors I Calibration Block Serial No. And Thickness KulI/

12 I

1 APR-7 I

3.5 Couplant Batch Number Demonstration of Flaw Detectability Ultragel 11 101125 7W Acceptable BEAM SPREAD MEASUREMENT 1/4 T Hole Minimum (20% DAC Near)

Minimum (50% DAC Near)

Maximum Signal Minimum (50% DAC Far)

Minimum (20% DAC Far) 1/2 T Hole Minimum (20% DAC Near)

Minimum (50% DAC Near)

Maximum Signal linimum (50% DAC Far)

K._.-inimum (20% DAC Far) 314 T Hole Minimum (20% DAC Near)

Minimum (50% DAC Near)

Maximum Signal Minimum (50% DAC Far)

Minimum (20% DAC Far)

Surface Distance

.57 Metal Path 1.05 70 1.10 87 1 18 1 05 1.40 1 15 1.45 140 225 1 55 2.35 1 80 243 200 266 213 2.80 2.18 335 230 342 261 361 305 402 378 412 Remarks:

NA i

f"

Farley Lclear Plant Magnetic Particle Examination Record SHARED FNP-0-ND,-100.11 MT-F-FORM 002 Southern Nuclear Operating Company Unit Weld Number 2

APR1-2100-10 Thermometer Mfg /Ser. No.

PTC Cal. Due Date 2/5/2003 Surface Temp.

1 48890 98 0 F

.Component Configuration PRZ UPPER HD TO NOZZLE WELD Ind. No.

Results NA NI NA Procedure/Rev./TCN FNP-0-NDE-100 11 Magnetizing Yoke Mfg.:

Magnaflux yr Serial No.:

A999638 Pole Spacing:

8 Al Field Indicator SIN:

MFI-02 Field Indicator Acceptable [Y/N]

Yes Indication Desc. / Exam Limitations I etc.

Power AC 14.0 1N/A

[

Mfg.:

Batch Number:

Color:

Type:

% of Length Coverage

% of Area Coverage NA Sheet No.

S02F2M002 MT Materials Magnaflux 95H062 Red N/A 100 Date 100 Remarks Remarks: NA Primary Examiner John W Bell SNC NDE Level Il/111 Review A1 4ý ASN T Level Initials Assistant Examiner II

,tL2.

(

Joseph D Funyak Date Percentage o r

7 -7,/--6e7-Coverage ASNT Level Initials ANII Review f Code Non-Technical Review "OL, 07aJJ 4(06 Date q-iq.. 0 Date Revision 4.

Page I of I 9/17/2002

WELD EXAMINATION

SUMMARY

SHEET Sheet No S02F2S076 Weld Number.

APR1-2100-10IR Examination Area:

PRZ NOZ-INSIDE RADIUS Fiure No.

Procedur Cal Block Eam Requirements APR11-2100 FNP-0-NDE-100.38 ALA-38 B-D/B3.120/

The following data sheets are included in this package Data Sheet No.

Angle Results Remarks S02F2U008 20 NI Comments:

(Describe limitation In comments)

Percent on required area examined - Surface Percent of required volume examined-Volumetric Relief Requektt NumberdRequired?

Code Case used (if applicable)

IER Number (if applicable)

NA 100 NA NA NA

/

ITS Review:.

( *o L

Date: fPz/-oz-I

Farley Nuclear Plant Ultrasonic Calibration and Examination Record Si-,

-ED FNP-0-NDE-100.38

nllh~r IMIP~k FNP-0-lN DE-1in 00~l,.38 Unit Sketch/Component Number Date Sheet No.

2 APR1-2100-IOIR 9/17/2002 S02F2UO08 Page of Procedure/Rev /TCN CouplantlBatch No.

ThermometerSN/Cal Due Date Linearity Sheet No.

FNP-0-NDE-100 38 2 0 N/A Ultragel II 1

01125 48890 2/5/2003 S02F2L001 Instrument _

Search Unit Calibration Block Axial Scan Calibration Circ Scan Calibration Instrument Staveley I SONIC 136 Transducer Mfg.

KBA Cal. BIk. No ALA-38 Cal.

Signal Sweep Wmax Cal.

Signal Sweep Wmax Serial No. 136-905K Refl.

Amp.

Div.

Refl..

Amp.

Div.

Serial Number L30469 Thickness 6 01 NA A

80 30 265 Axial dB Circ dB Model No.

SWS Cal. Temp 79 *F B

60 50-_

3.24 R eference N A 63 8 S ize I N o.

5" S hape R ound C al. In 14 "45 C

40 7 0 3 99 Scanning NA 69 8 Frequency/Mode 2 25 / Long Cal. Chk.

1600 "A" Dimension 7

Calibration Remarks:

Reject OFF Cal. Out 17 55 Nom Angle 20° Wmax from end of block Frequency 2Angle 20*

Ref. BIk. No.

A01146 Mode PIE Cable Type / No. Conn. RG174/0 Reflector/dB 2"RAD/53 8 Damping 200 OHMS Cable Length 12' Amp/Sweep 80 % 1 8 Cnmn TP~mn.

I Crnmfinr,,rf;......n-98 ScanL

-Results.

Ind Dir.

NI _[NR-RI No.

8 NA PRZ NOZ-INSIDE RADIU:

01o --

Length DAC LI Lmax S

Wo Loc.

Lo Loc.

I -

N A_

N A Reference Measurement Sweep Position I

Thickness.

1 L2 WI Wmax W2 S1 Smax S2 1"<-

C/L

->1",

Notes:

NA Examination/Limitation Remarks:

4,A,:

O¶5...

aJoV Total Length of Weld Examined 5 (L)

NA 2 (L)

NA 7 and 8 (W)

NA Level Ilnitials Assistant Examiner IIJohn W Bell Date Perc

/AL

-5

-oh e

Cod Extent of Perpendicular Scans (W)

Extent of Parallel Scans (L) 5-From NA to NA 2-From NA to NA From (5)

NL to (2)

NL Level Initials Non-Technical Review Date q-jq) ca entage of Review Date Coverage go

.0)

Revisron 2 0 7

0 Total Length

ý Crown Width of Weld NA NA Primary Examiner Joseph D Funyak SNC NDE Level I/I11l ReviE O

I

ML030300235

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

Navigation menu