ML20204D727
| ML20204D727 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/15/1999 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20204D694 | List: |
| References | |
| NUDOCS 9903240274 | |
| Download: ML20204D727 (250) | |
Text
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INSERVICE INSPECTION REPORT Date of Document Completion: February 1,1999 REFUELING 15 INTERVAL 2 PERIOD 3
. OUTAGE 3 J. M. FARLEY UNIT 1
- O 1
NUCLEAR GENERATING PLANT COLUMBIA, ALABAMA 36319 Commercial Service Date: December 1,1977 i
Southern Nuclear Jperating Company 40 inverness Parkway
_ . . . . . _ . . . _ _ _ _ . _ _ _ _ . . _ . - - . . . _ . . _ . _ . . . . ____.._m.. ._. _ . . . ..___ _ . .._....___m_
INDEX Cr SECTION TAB NIS-1 OWNERS REPORT A i
SUMMARY
B I l
EXAMINATION PROGRAM C EXAMINATION RESULTS D l l
ADDITIONAL EXAMINATIONS E INDICATIONS F PERSONNEL, EQUIPMENT, MATERIAL, & CALIBRATION BLOCK CERTiflCATIONS G EXAMINATION PROCEDURES H REACTOR VESSEL INSPECTION TOOL D/s P. AND RESULTS I ;
i NIS-2 FORM-OWNER'S REPORTS FOR REPAIRS AND REPLACEMENTS J
Page 1 of 4 FORM NIS-1 OWNER'S REPORT FOR INSERVICE INSPECTIONS l As required by the Provisions of the ASME Code Rules
/%
i Southern Nuclear Operating Co. 40 Inverness Center Parkway,
- l. Owner Birmingham Al 35242 (as agent for Alabama Power Co.)
(Name and Address of Owner) l 2. Plant J. M. Faley Nuclear Plant, Hwy 95 South. Columbia. Al. 36319 (Name and Address of Plant)
- 3. Plant Unitl 4. Owner Certificate of Authorization (if required) N/A
- 5. Commercial Service 12/01/77 6. National Board Number for Unit See Listed N. B.
for each component
- 7. Components Inspected Manufacturer Component or Manufacturer or Installer State or National Appurtenance or Installer Serial No. Province No. Board No.
Reactor Vessel Combustion 69204 N/A 21012 Closure Head Engineering Class I Piping Daniel N/A N/A N/A Construction Class 2 Piping Daniel N/A N/A N/A Construction i
A
\m, Note: Supplemental sheets in the form oflists, sketches or drawings may be used, provided (1) size is 81/2 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.
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Page 2 of 4 FORM NIS-1 t
- 8. Examination Dates 10/17/98 to 12/27/98
- 9. Inspection Period Identification: Third Period 8/01/94 to 12/01/97 I
- 10. Inspection Interval Identification: Second Interval 12/01/87 to 12/01/97
, 1 l l l 11. Applicable Edition of Section XI 1989 Addenda None i
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- 12. Date/ Revision ofInspection Plan: FNP-1-M-043; 02/10/97; Revision 5 ,
i
- 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 and C
- 14. Abstract of Results of Examinations and Tests. See Tab B
- 15. Abstract of Corrective Measures. See Tab B l
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 l conform to the rules of the ASME Code,Section XI.
Cenificate of Authorization No. (if applicable) N/A Expiration Date N/A Date U/[ 19 $ Signed Southern Nuclear Operating Co. ByMF [
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(Owner) l l CERTIFK ATE OF INSERVICE INSPECTION l
- I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel l Inspectors and the State or Province of A~ and employed by Arkwright Mutual Insurance Company of l Waltham, Massachusetts have inspected the coinponents described in this Owner's Report during the period pg/ c to ///Mr, ,and state that to the best of my knowledge and belief, the Owner has performed l
l exammations and tests arid taken corrective measures described in this Owner's Repon 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'< Report. Furthermore, neither
! the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
- _ Commissions A Y2:# YA/
Ins'pector'sqfiature National Board, State, Province, and Endorsements r
Date y//r 19 ff
Page 3 of 4 l l
OWNER'S REPORT O FOR V INSERVICE INSPECTION I DATE: 02/01/99 l l
OWNER NAME AND ADDRESS: Southern Nuclear Operating Co. l 40 Inverness Parkway !
Birmingham, Al35242 (as agent for Alabama Power Co.) j i
NAME AND ADDRESS OF j NUCLEAR GENERATING PLANT: Joseph M. Farley Nuclear Plant l Highway 95 South l Columbia, Alabama 36319 l NAME ASSIGNED TO NUCLEAR POWER UNIT: Joseph M. Farley Nuclear Plant ,
Unit 1 OWNER CERTIFICATE OF AUTHORIZATION: N/A COMMERCIAL SERVICE DATE: December 1,1977 i NATIONAL BOARD NUMBER: See listed NB's for each component l
NAME OF COMPONENTS OR PARTS OF COMPONENTS INVOLVED: Representative samples of the following components and systems were examined using nondestructive examination techniques.
CLASS 1 COMPONENT OR SYSTEM SYSTEM - APR SKETCH DESIGNATION Reactor Vessel Closure Head Bl3 1-1300B m
6 O
r Page 4 of 4 CLASS 2 COMPON ENT OR SYSTEM SYSTEM APR SKETCil
{gg g DESIGNATION 1
HYDROSTATIC TESTING: SEE TAB B NAME AND ADDRESS OF MANUFACTURER OR INSTALLER OF COMPONENTS:
REACTOR VESSEL CLOSURE HEAD CLASS I and 2 PIPING Combustion Engineering, Inc. Daniel Construction Co.
Chattanooga, Tennessee Greenville, South Carolina i
INSERVICE INSPECTION DATES: 10/17/98 TO 12/27/98 NAME OF AUTHORIZED NUCLEAR INSPECTOR: Charles G. Ward NAME AND MAILING ADDRESS OF INSPECTOR'S EMPLOYER: Arkwright Mutual Insurance Company 1 225 Wyman St.
V P. O. Box 9198 Waltham, Ma. 02454-9198 ABSTRACT: SEE TAB B il O
J. M. FARLEY NUCLEAR PLANT UNIT NO 1 o INTERVAL 2 PERIOD 3 OUTAGE 3 C BALANCE OF PLANT / REACTOR VESSEL EXAMINATION
SUMMARY
INTRODUCTION An Inservice examination of Class I components and piping systems was conducted at Farley Nuclear ;
Plant Unit I from October 1998 to December 1998. The examinations were performed in accordance with an approved Examination Program Plan located under Tab C of this report. The primary areas of examination included the Reactor Vessel Closure 11ead Nuts and RiiR/S1 Piping.
The program utilized visual nondestructive testing methods in accordance with the requirements of ASME Section XI 1983 Edition, up to and including Summer 1983 Addenda, and Technical Specifications 4.0.5 and 4.4.6.
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 Visual examination of thirty-eight (38) Reactor Vessel Closure ficad nuts were performed in !
accordance with the alternate examination requirements of Relief Request RR-55 of the 2"d Interval ISI Program. These examinations had been postponed from the previous refueling outage and the interval extension provisions of IWA 2400(c) were applied. Examinations resulted in no i recordable indications being noted. '
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SUMMARY
OF INDICATIONS CLASS 1 (A) VOLUMETRIC EXAMINATIONS None (B) SURFACE EXAMINATIONS None (C) VISUAL EXAMINATIONS None o
.A CLASS 2 (A) VOLUMETRIC EXAMINATIONS None
)
(II) . SURFACE EXAMINATIONS None (C). VISUAL EXAMINATIONS None AUGMENTED EXAMINATIONS No augmented examinations were performed.
ADDITIONAL EXAMINATIONS Results from additional examinations which were performed during this outage are as follows:
o Class 1 System Leakage Test In accordance with ASME Section XI 1989 Edition IWB-5210(a)(1), leak testing of the Class 1 Reactor Coolant System Pressure Boundary was performed prior to startup following the 15th V,G refueling outage. The testing was completed by plant personnel on 12/27/98 marking the end of the refueling outage, and results are included in the outage report documenting work performed to meet requirements of the 3"' Inspection Interval.
e Class I and 2 Hydrotesting A pressure test was performed on sections of the RilR and Safety injection systems, connecting to the RCS, which are not normally pressurized during normal operation. This piping is isolated by check valves or normally closed isolation valves. The testing was conducted, under the provisions of ASME Code Case N-498-1 and procedure IWP-1-STP-156.2, at normal operating pressure.
This testing had been postponed from the previous refueling outage and the interval extension provisions of IWA 2400(c) were applied. The testing was completed satisfactorily.
STATUS OF EXAMINATIONS REQUIRED FOR CURRENT INTERVAL This refueling was the 3rd outage,3rd period of the 2d Inspection Interval and completed all remaining examinations for the interval on Unit 1.
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O EXAMINATION PROGRAM PLAN UNIT 1 RF 15 INTERVAL 2 PERIOD 3 OUTAGE 3 1998 O
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O O O SOUTHERN NUCLEAR OPERATING COMPANY FNP-1-M-045 J.M. FARLEY NUCLEAR PLANT Unit 1 INSERVICE INSPECTION-Interval 2 Period 3 Outage 3 Code Component No. Type Exam Exam Cov. Cal. Plan '
Cat./ Item sketch / Item Mat./Sup. Type (FNP-Fig. ) Block No. Loc. Remarks 1 B-G-1/B6.10 -ALA1-1300-N01 (A) VT-1 RPV(M) 2 B-G-1/B6.10 ALAl-1300-N02 (A) VT-1 RPV(M) 3 B-G-1/B6.10 ALAl-1300-NO3 (A) VT-1 RPV(M) 4 B-G-1/B6.10 ALAl-1300-N04 (A) VT-1 RPV(M) 5 B-G-1/B6.10 ALA1-1300-N05 (A) VT-1 RPV(M) 6 B-G-1/B6.10 ALAl-1300-N06 (A) VT-1 RPV(M) 7 B-G-1/B6.10 ALAl-1300-N07 (A) VT-1 RPV(M)
B B-G-1/B6.10 ALAl-1300-N08 (A) VT-1 RPV(M) 9 B-G-1/B6.10 ALAl-1300-N09 (A) VT-1 RPV(M) 10 B-G-1/B6.10 AIAl-1300-N10 (A) VT-1 RPV(M) 11 B-G-1/B6.10 ALAl-1300-N11 (A) VT-1 RPV(M) 12 B-G-1/B6.10 ALAl-1300-N12 (A) VT-1 RPV(M) 13 B-G-1/B6.10 ALAl-1300-N13 (A) VT-1 RPV(M) 14 B-G-1/B6.10 ALAl-1300-N14 (A) VT-1 RPV(M) 15 B-G-1/B6.10 ALA1-1300-N15 (A) VT-1 RPV(M) r 16 B-G-1/B6.10 ALAl-1300-N16 (A) VT-1 RPV(M) ;
17 B-G-1/B6.10 ALAl-1300-N17 (A) VT-1 RPV(M) -*
1 Gen. Rev. 10
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SOUTHERN NUCLEAR OPERATING COMPANY FNP-1-N-045 J.M. FARLEY NUCLEAR PLAl*fT '
Unit 1 INSERVICE INSPECTION y Interval 2 Period 3 Outage 3 Code Component No. Type Exam Exam Cov. Cal. Plan Cat./ Item sketch / Item Mat./sup. Type (ENP-Fig. ) Block No. Loc. Remarks 10 B-G-1/B6.10 ALAl-1300-N18 (A) VT-1 RPV(M) 19 B-G-1/B6.10 ALAl-1300-N19 (A) VT-1 RPV(M) 20 B-G-1/B6.10 ALAl-1300-N20 (A) VT-1 RPV(M) 21 B-G-1/B6.10 ALAl-1300-N21 (A) VT-1 RPV(M) 22 B-G-1/B6.10 ALAl-1300-N22 (A) VT-1 RPV(M) 23 B-G-1/B6.10 ALAl-1300-N23 (A) VT-1 RPV(M) 7 24 B-G-1/B6.10 ALAl-1300-N24 (A) VT-1 RPV(M) 25 B-G-1/B6.10 ALA1-13DO-N25 (A) VT-1 RPV(M) 26 B-G-1/B6.10 ALAl-1300-N26 (A) VT-1 RPV(M) 27 B-G-1/B6.10 ALAl-1300-N27 (A) VT-1 RPV(M) t 28 B-G-1/B6.10 ALA1-1300-N28 (A) VT-1 RPV(M) 29 B-G-1/B6.10 ALAl-1300-N29 (A) VT-1 RPV(M) 30 B-G-1/B6.10 ALA1-1300-N30 (A) VT-1 RPV(M) ,
31 B-G-1/B6.10 ALAl-1300-N31 (A) VT-1 RPV(M) r 32 B-G-1/B6.10 ALAl-1300-N32 (A) VT-1 RPV(M) 33 B-G-1/B6.10 ALAl-1300-N33 (A) VT-1 RPV(M) i 34 B-G-1/B6.10 ALAl-1300-N34 (A) VT-1 RPV(M) -
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SOUTHERN NUCLEAR OPERATING COMPANY FNP-1-M-n45 I J.M. FARLEY NUCLEAR PIET Unit 1 INSERVICE INSPECTION !
Interval 2 Period 3 Outage 3 Code Component No. Type Exam Exam Cov. Cal. Plan Cat./ Item sketch / Item Mat. /Sup . Type (DIP-Fig. ) Block No. Loc. Remarks j 35 B-G-1/B6.10 ALAl-1300-N35 (A) VT-1 RPV(M) l l
! 36 B-G-1/B6.10 .ALAl-1300-N36 (A) VT-1 RPV(M) !
l 37 B-G-1/B6.10 ALAl-1300-H37 (A) VT-1 RF"J (M) 38 B-G-1/B6.10 ALAl-1300-N39 (A) VT-1 RPV(M) }
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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 VALVE BODIES / BOLTING EXAMS 1.5 REACTOR COOLANT PUMP EXAMS 1.6 PRESSURE RETAINING BOLTING / PRESSURE'iESTING EXAMS 1.7 CLASS 2 COMPONENT EXAMS 2.1 STEAM GENERATOR EXAMS 2.2 PIPING WELD EXAMS 2.3 I
O O
EXAMINATION
SUMMARY
FOR UNIT 1 4 INTERVAL 2 PERIOD 3 OUTAGE 3
'O DRAWING ALAl-1300B REACTOR VESSEL STUDS, NUTS and WASHERS ITEM NO YOLUMERIC SURFACE VISUAL REMARKS
! NI NRI R1 NI NRI RI NI NRI RI RV NUTS N01-N38 X
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FNP-I-M-097 AL Al-1300B REACTOR VESSEL STUDS, NUTS, AND VASHERS
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STUD NUT 58 STUDS AND
's- NUTS 58 VASHER u f ,____, x SETS (2)
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- STUDS 016 ALA-36 W , 1-58 1 3-26-98 RAV JAR REVISED PER REA 96-1295 REv. O LET R4.ns v X X 0 6-30-92 SDH JAR ISSUED PER PCN S-92-1-8162. CAB "% AH DML ncv. nATE sv cm n E SCRIPT 1DN APPft.1 APPR2 APPR.3 APPIL4
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Southern Company Services, Inc. e.r REACTOR VESSEL ALABAMA POVER COMPANY ses DRavns MJMKP swerT nov.
/ JOSEPH M. FARLEY NUCLEAR PLANT
( UNIT i A-351192 9 1
CN N I"% u l 1 v Q)
FARLEY NUCLEAR PLANT SHARED FNP-0-NDE-100.21 VISUAL EXAMINATION RECORD VT-1 RTYPE: L1.09 SOUTHERN NUCLEAR OPERATING COMPANY ,
Plant /Urut Line Number / Examination Area / Weld No. Drawtng Number Sheet No.
FARLEY / 1 ALA1-1300-N01 THRU N38 ALA1-1300 S98F1V016 Photos Sketch Resolution Technique WO/WA N/A O ves O Bm O ves O 1rr ossim (Scaie) @ Drect Procedure No- FNP-0-NDE-100.21
'Si No O coior + No I 1/32" Line (Gray Card) O Remote R h No. 1 Equipment Lighting Tools Examiner / Initial D. R. Cordes Level Sig~ III
@ Mirror O Ambient Scale O oepthcause ( ) tevei Examiner / Initial NYA Level O uagnrier t nasnn sht O uierometer O comparator uf, 3,, .
O ccTv O orop69ht O canper O weu cauoe cate (uonuvoay/vear>
10/26/98 O WELDS & BASE MATERIAL VT-1 Sat N/A @ BOLTS, STUoS, ANo WASHERS VT-1 N/A Sat Sat sa Ground Blend Materw O O + L=se uembers O O @
undercut O O + cracks @ O O corrosion Buiu-uP O O + c-rosion + 0 O ocuses O O @ couges t O O Evidence of Leakage O O + Thread o mage + 0 O Arc StrWes O O + oerormat.on + O O cracks O O + Protective Coating O O @ +
Other" O O + Evidence or teakage O O +
Other " O O + !
Provide details on unsat areas by use of supplemental data sheet.
" Provide details on other areas examined Comments
- VT-1 EXAMINATION FOR 2ND INTERVAL COMMITMENT PER RR-55.
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%.Y SHARED FARLEY NUCLEAR PLANT FNP4-NDE-100.22 VISUAL EXAMINATION RECORD - VT2 SOUTHERN NUCLEAR OPERATING COMPANY Plant / Unit Data Packa9e Drawing Number FARLEY / -1 Ref.160.22 D-351118 Sheet 1 Rev.6 WO/WA No- System BoWarns 606848 Procedure No-The 'A' Train RHR Loop Suction piping was examined under hydrostatic test conditions in FNP-0-NDE-100.22 accordance with FNP-1-STP-156.2, Appendix A requirements. See the attached sheet for the Revision No. 2 system boundaries. The examination included all vents, drains, instrument lines and test Examiner gg g'g Levet connections within the system boundaries.
Scott R. Erickson 11 Examiner Level AM4 N/A Date (Month / Day / Year) 11/16/98 SKETCH '
Examination (Per Para. 7.5)
- Sat t
- Unsat
- Provide details on unsat areas N/A Comments FARLEY NUCLEAR PLANT Figure 1 Revision 2 fa sE l *! E
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Plant /Unrt Data Package Drawing Number [
FARLEY / 1 Ref.160.23 D-351118 Sheet 1 Rev.6 WO/WA No. 8Y* " *"**
606848 Procedure No.
The 'B' Train RHR Loop Suction piping was examined under hydrostatic test conditions in FNP-0-NDE-100.22 accordance with FNP-1-STP-156.2, Appendix B requirements. See the attached sheet for the '
Revision No.. 2 system boundaries. The examination included all vents, drains, instrument lines and test Connections within the system boundaries.
Examinergg g, M Level Scott R. Erickson 11 Examiner Level 4/b N/A [
Date (Month / Day / Year) 11113/98 [
SKETCH '
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Examination (Per Para. 7.5) i
- Sat e
- Unsat .
- Provide details on unsat areas Q1E11V063A & B (Vent line) evidenced a leakby at the valve seat (through drain hose). The remainder of the system was sat. ,
Comments FARLEY NUCLEAR PLANT i i
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SUBJECT:
Unit 1 B Train RHR Loop Suction piping pressure test.
REFERENCES:
FNP-l-STP-156.2
} 1. PROBLEM DESCRIPTION: On 11/13/98 the B Train RHR Loop Suction piping was pressure tested at nomitial operating pressure under the provisions of ASME Code Case N-498-1. This testing was being performed to meet the remaining pressure testing requirements for Class I piping, for the 2" Inspection Interval. The VT-2 examination was noted as "unsat" due to vent valves, used to vent air from the system while filling with water, were leaking past their seat. The remainder of the system was noted as " sat",
- 2. EVALUATION PERFORMED / FINDING: The leakage past the valve seat on the %" vent valves is not considered a structural integrity problem which would cause the pressure test to be unsatisfactory.
Valve seat leakage is not addressed in the ASME Code Section IWA-5250 as a condition requiring corrective measures to be taken. The vent valves were capped after completion of the pressure testing.
- 3. CONCLUSION / RECOMMENDATION: The structural integrity of the piping system was verified intact by the performance of the pressure test. The pressure testing requirements of ASME Code Case N-498-1 has been satisfied and no further action is required.
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1013-Reactor Coolant systesa ISI Bdry Exasmination Period Relief j component Bydro Dwg No. Coord Loc Dwg First second Third Request Researks j WITH CLASS 1. (E21 ]
SYSTEM) 6" CCA-22 (LOOP 3) 160.1 D-351114-1 C-7 EG718 I/H to gvost4 ;
> 160.1 D-351115-1 C-1 EG718 u 160.1 D-351115-2 E-1 EG718 6" CCB-32 160.1 D-351115-2 E-2 EG718 I/H RR-23(J) CLASS 2 HYDRO TRSTED WITH CLASS 1. (Ell SYSTEM) 1 8" CCA-22 160.1 D-351115-1 C-3 EG718 I/H y 10" CCB-32 160.1 D-351115-2 F-2 EG718 I/H RR-23(J) CLASS 2 HYDRO TESTED j WITH CLASS 1, THRU f PENETRATION INO. 15) I TO QV023B (E11 k SYSTEM) f 6" CCA-28 (LOOP 3) 160.1 D-351114-1 D-7 EG715,EG687 I/H To evorrc. f
> 160.1 D-351115-1 G-1 EG715 }
2" CCA-28 150.1 D-351115-1 G-2 E934,E935,E9 I/H I 36 2" CCA-17 (LOOP 3) 160.1 D-351114-1 B-11 E1522 I/H 2" CCA-21 (LOOP 3) 160.1 D-351115-1 C-3 EG590 I/H [
2" CCA-26 (LOOP 3) 160.1 D-351115-1 C-3 E1352 I/H 2" CCA-29 (LOOP 3) 160.1 D-351115-1 G-3 E0936 I/H 160,1 D-351115-1 G-2 E0947 I/H b 2" CCA-30 (LOOP 3) o 1" CCA-4 (LOOP 3) 160.1 D-351114-1 B-11 E1522 I/H ,
> 160.1 D-351116-1 C-6 E1432 k 4
3/4" CC: 37 !!.a^? 3; 150.1 0-351111-1 D-10 E1521 I/:: ?" 23(C) Cm:0 2 ::YDnC T2;T50 ;
wrT= Cr.re 1. el?f; esrm ,
i-150.1 0-251107-1 C-2 E2531,52559, Ifit ER 2Me; CM3'HHfYDfte-TESTED r
~~ ' * ***
- 7
g ~
g !4 J.M. Farley Nuclear Plant - Unit 1, Class 2 Y
1E11-Residual Beat Retsoval
]
ISI Bdry Examination Period Relief Component Eydro Dwg No. Coord Loc Dwg First Second Third Request Researks ,
6" CCB-22 (LOOP 1) D-351115-2 G-2 EC718 I/H RR-23(J) CIASS 2 HYDRO TESTED ?
WITH CIASS 1 REQUIREMENTS (160.1) g 10" CCB-32 D-351115-2 G-2 EG718 I/H RR-23(J) CIASS 2 HYDRO TESTED WITH CIASS 1, THRU f
PENETRATION (NO. 17)
TO QV023A (160,1) 6" CCB-22 (LOOP 2) D-351115-2 F-2 EG718 I/H RR-23(J) CIASS 2 HYDRO TESTED WITH CIASS 1 REQUIREMENTS (160.1) 10" CCB-22 D-351115-2 F-2 EG718 I/H RR-23(J) CIASS 2 HYDRO TESTED WITH CIASS 1 REQUIREMENTS (160.1) 6" CCB-29 D-351115-1 F-4 EG518',EG715 I/H RR-23(I) CIASS 2 HYDRO TES WITH CIA 35 1 j REQUIREMENTS (160.1) j 10" CCB-29 D-351115-2 E-1 EG518 I/H RR-23(I) CIASS 2 HYDRO TESTED f WITH CIASS 1, THRU !
PENETRATION (NO. !
TO QV044 (160.1) 101)
> D-351115-1 F-4 EG518 I/H RR-23(I) CIASS 2 HYDR TESTED !
WITH CIASS 1i '
REQUIREMENTS (160.1) 6" CCB-32 (LOOP 3) D-351115-2 E-2 EG718 I/H RR-23(J) CIASS 2 HYDRO TESTED WITH CIASS 1 REQUIREMENTS (160.1) 10" CCB-32 D-351115-2 F-2 EG718 I/H RR-23(J) CIASS 2 HYDRO TESTED j WITH CIASS 1, THRU ,- ! '
PENETRATION (NO. 15) l TO QV023B (160.1) I b
. ~, ...
.~. o,..
oo i , . ,. , . , , .,a l
/, i, !m) j j 'w %.
I J.M. Farley Nuclear Plant - Unit 1, Class 2 ;
t.
1E21-Safety Injection ISI Bdry Examination Period Relief Couponent Hydro Dwg No. Coord Loc Dwg First Second Third Request F*am rk s en-eC4-24-fi OC;' 1; 0-351115-2 D-3 EC715 I/:: ""-- 2 3 ("; CIASS 2 "Y0nc TEST =0-T O C L*.S S 1 REQUIBEMENTS (150.1)-
3/t" CCS-53 (TI) - D-351115-2-D E1511 1/:: ""-23(H) CL*SS 2 HYDRO-TESTED
-TO CL*2C 1 REO"IREME"TS (150. ? )- i 3/4" CCD-54 (T1; 0-351115-2 0-2 51611 Iin nR-24fH; OIASS 2 ::YDRO-TEST TO CL*SS 1 n e AT.T T.~
.mv e* ..# .1.E. n .1,%
.M t*th. eM. f.T* .
12" CCB-2t (Enn? 2) D-351115-2 D-5 EC696,EC716 I/1; ""-- 2 3 (") CII4C 2 ::YORO TEST
-TO CL*S S 1 "EO" IRE"E"TS (150.1) 3/i" CCS-53 (T2; D-351115-2 D-5 E1513 I/H ""s 23(") CI *ic 2 "YDRG-TESTED-
-TO CI_'I S 1 h tP A 1_ %,
. ~ .f_f T_ D. .P._tA.r tP. P _e
. r
, 1_ f_ n.
3/4" CC" Si (T2; 0-351115-2 D-t EIM2 E/li RR 23 'H) OI.A00 2 *YDRO TESTED-
'TO CL*2C 1 REO"IR"E"TS (160.1) 12" CCS-24 (LOOP 3) D-351115-2 D-9 EG716 I/H--RR-24(H } CLASS-2-HYDRO-TESTED TG CLASS 1 REQUIRLII2iT3 *100.1)-
3/4" CCS-53 (T3; D-351115-2 D-9 E1513 I/M RR-23 (H) CLASS-2-HYDRO-TESTED TO C L".S S 1
- n. ~e A,n. . .r-n. eu.cu.,. .e., , s e. n. . S. i, e, . ,r L.
3/4" CCB-54 (T3' D-351115-2 E ~' E1513 I/:: ""- 2 3 (H) CLASS 2 ::YORO TESTED g T.'^. " . _
- _ " _ " '.
,, td REQUIREMEliT3 i 1 G G .1;' ! ',
l 3" CCB-21 (LOOP 1) D-351115-1 F-4 EG521,EG717 I/H RR-2 3 ( D) CLAES 2 HYDRO TESTEDi TO CLASS 1 ;k i REQUIREMENTS. TO Lp VALVES QV004A,B(D-5) ,a. i ,
PENETRATION (NO 19) L.
ci 2 (SI) 1E21-2 m ,, , f ,g Rev.: 7
o o o l J.M. Farley Nuclear Plant - Unit 1, Class 2 1
1E21-Safety Injection j Rydro ISI Bdry Dwg No. Coord Loc Dwg E===ination Period Relief First second Third Request Remarks
.f '
Component (160.1) -
1" CCB-50 D-351115-1 E-5 E3514 I/H RR-23(D) CIASS 2 HYDRO TESTED q TO CIASS 1 REQUIREMENTS UP TO PIPE CAP D.S. OF y "
VALVE QV029 (160.1) 2" CCB-21 (VA) D-351115-1 F-3 E0654 I/H RR-23(DI CIASS 2 HYDRO TESTED TO CIASS 1 REQUIREMENTS (160.1) ,
2" CCB-21 (VB) D-351115-1 E-3 E0695 I/H RR-23(D) CIASS 2 HYDRO TESTED To CIASS 1 REQUIREMENTS (160.1) 2" CCB-21 (VC) D-351115-1 F-3 E0695 I/H RR-23(D) CIASS 2 HYDRb TESTED TO CIASS 1 j REQUIREMENTS (160.1) i 3" CC3-22 (LOOP 1) D-351115-1 B-5 EG397 I/H RR-23(El CIASS 2 HYDRO TESTED f TO CIASS 1 (160.1)
REQUIREMENTS. FROM i QV063 THRU .
PENETRATION (NO. 20) 2" CCB-22 (VA) D-351115-1 C-4 E1351 I/H RR-23 (E) CIASS 2 HYDRO TESTED h TO CIASS 1 (160.1)
REQUIREMENTS. [
2" CCB-22 (VB) D-351115-1 B-4 E1278 I/H RR-23(E) CIASS 2 HYDRO TESTED k TO CIASS 1 (160.1) [
REQUIREMENTS. ;
2" CCB-22 (VC) D-351115-1 C-4 E1353 I/H RR-23(El CIASS 2 HYDRO TESTED l, TO CIASS 1 (160.1) h REQUIREMENTS. i
. L g:
3" CCB-30 (LOOP 1) D-351115-1 H-5 EG520,EG717 I/H RR-23 ( F) CIASS 2 HYDRO TESTED' g:
TO CIASS 1 (160.1)
REQUIREMENTS. FROM 2 (SI) 1E21-3 Rev.: 7 ,
, r t i \ ,
( : b v w.' vi g i
J.M. Farley Nuclear Plant - Unit 1, Class 2 4
1E21-Safety Injection ISI Bdry Examination Period Relief ,;
First Second Third Request E component Hydro Dwg No. Coord Loc Dwg Remarks QV068 THRU PENETRATION (NO. 81) 2" CCB-30 (VA) D-351115-1 G-4 E0775 I/H RR-23 (F) CLASS 2 HYDRO TESTED 4 TO CLASS 1 (160.1) {
REQUIREhENTS.
2" CCB-30 (VB) D-351115-1 G-4 E757 I/H RR-23 (F) CLASS 2 HYDRO TESTED iL 5h TO CLASS 1 (160.1)
REQUIREMENTS.
I/H RR-23(F) CLASS 2 HYDRO TESTED '
2" CCB-30 (VC) D-351115-1 G-3 E946 TO CLASS 1 (160.1)
REQUIREMENTS.
3" CCI-31 (LOOP 1) D-351115-1 J-5 EG397,EG717 I/H RR-23(G) CLASS 2 HYDRO TESTED j TO CLASS 1 (160.1) W t
REQUIREMENTS. FROM j QV072 THRU l PENETRATION (NO. 80) 2" CCB-31 (VA) D-351115-1 H-3 E1275 I/H RR-23(G) CLASS 2 HYDRO TESTED TO CLASS 1 (160.1) 1 REQUIREMENTS. !
2" CCB-31 (VB) D-351115-1 H-2 E1193 I/H RR-23(G) CLASS 2 HYDRO TESTED TO CLASS 1 (160.1) l REQUIREMENTS.
2" CCB-31 (VC) D-351115-1 H-2 E1131 I/H RR-23(G) CLASS 2 HYDRO TESTED
[
TO CLASS 1 (160.1) l REQUIREMENTS. l
- 4" C00 21 100.2 0-351115 i P' CC300 I/91 I/94 I/95 3" 000 21 160.2 D-351115-1 i' EG390,50520 I / 91---M/94 I/95 FRO" C.I- CMARGINC {
PUMPS-TO-VALVES GV01CA, C ,.
1" 000 50 150.2 D-351115 1 " -- 5 E3511,E3515 I/01 ::/04 I/05 MYDRO TESTED "P TO PIP S-GAP-4PGN 2 (SI) 1E21-4 Rev.: 7 q
' ' ' " ^ ' 8
4 ,.. ,.JA. 4 . A - .a. -- - t--. 4 .- .ma,wa a A6-dm 39a4ue_ .#.-m - 6 m.aeaa_ mea -i --A --gr_.. a .--a -.v- -- a,,
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NO EXAMINATIONS SCHEDULED THIS OUTAGE O
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._,a & As .a. m a4-.# +.b Jun J 4 mM.@m __.m.m4am..A e_W5 mJ-Es.v---.hdsWm-ee. m am n a,i-Maaea--Jk -AM.A*~4J 4*# e ds-Ma----m.mwr e, e 4mwe.--ammAe-.-m.me 4-eme-th4-.4,m- a-,
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TAB G TABLE OF CONTENTS PERSONNEL CERTS EQUIPMENT CERTS TRANSDUCER CERTS MATERIAL CERTS CALIBRATION BLOCK CERTS O ;
i O
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EXAMINATION PERSONNEL J. M. FARLEY UNIT 1 1998-RF-15 EXAMINER NDE CERTIFICATION UT PT VT MT RT CORDES, D. R. 111 Ill Ill 111 N/A DIVALERIO, P. II 11 11 11 N/A ERICKSON, S. R. 11 11 11 11 N/A O
o LJ r
l .
SHARED FIGURE 2 FNP-0-AP-31 l NDE Qualification Verification for FNP Contractor Personnel Rtype L1.27 NDE EXAMINER Cordes, D. R. 421-80-7509 SNC NAME SSN EMPLOYER !
WRITTEN PRACTICE I Written practice (s) which govemed the attached certifications for the above named examiner has/have .
been reviewed and approved as shown in the attached documentation.
AUX-H/FN-300 Rev.11 CERTIFICATIONS METHOD LEVEL CERTIFICATION RECERTIFICATION i
DATE DATE MT lli 7/15/96 12/19/00 l PT lli 7/15/96 12/19/00 UT lli 1/2/96 12/18/00 RT l VT-1 Ill 2/27/97 12/19/00 1
VT-2 Ill 2/27/97 12/19/00 O' VT-3 111 2/27/97 12/19/00 !
ET Remarks: lWEllWL VT Level lli Certification Date 2/27/1997 - Expires 12/19/2000.
Attach Certi/ication Records.
Note: Re;ertification required every three (3) years for Levels I and 11 and five (5) years for Level 111.
EYE EXAM Date of Eye Exam: 2!2/98 Attach Eye Exam Results.
Note: Eye exams required annually.
Written Practice Approval, NDE Certifications, m and Eye Exams Reviewed By: k)e )[v aCS f r /9!4I Sifnature j b a(e '
Group Supervisor (s) or Team Leader (s) Approval (s):
W -f uhs frs Signattytf Date '
r\
() Signature Date Signature Date Page 1 of 1 Revision 11 l
4 CERTIFICATE OF QUALIFICATION
- 'nspection and Testing Services Southem Nuclear Operating Company D.R. CORDES 07/01/80 06/03/82 Date of Employment: 421-80 7509 Date Assigned to NDE: ;
Education: HEWITT-TRUSSVILLE HIGH SCHOOL Level (s) of Certification:
Method Level Certification Date Recertification Date UT lil 01/02/96 12/18/00 PT lil 07/15/96 12/19/00
, MT lil, 07/15/96 12/19/00 VT ll1 02/27/97 12/19/00
- VT-lWEllWL lli 02/27/97 12/19/00
- Effective 9/9/96, certifications based on SNT-TC-1 A are valid until recertifmation is required.
Examination Results:
NDE Method: Basic: Method / General Specific: Practical: Composite:
UT 82 97 90 NA 89.7 PT- 82 95 100 NA 92 O- MT VT 82 82 95 94 100 80 NA NA 92 85 i
VT-lWEllWL 82 94 80 NA 85 Special Qualifications:
This is to certify that the above named individual is quahfied in accordance with AUX-H/F/V-300, Southe;n Nuclear Operating Company Procedure for Qualification and Certification Corporate SNC Level 111 Iws '
M a- Date: /o -/:L- 3 I SNC ITS Principal Level 111 a > .8 v Date: /o-/a-98 i
lan.1996 t
a e> = - - - -, - , + ,,- r ,, 2 ,,- * - , -
4-Pago 2 of 3 ;
i >
- NAME: CORDES D.R.
I EDUCATION I -
i O REFERENCE FROM TO l GRADUATE (
1967 1975 YES Grade Schools HEWITT-TRUSSVILLE HEWITT-TRUSSVILLE 1975 1979
! YES High Schools 4
i Junior College Technical Co11eget J
1979 1983 h NO ' College (Four Year): UAB i
i Degree 1
l
- Graduate School (s):
) Degree 4
i
~
i EXPERIENCE IN METEOD j
j REFERENCE LOCATION MTD/ LEV FROM TO h FACILITY / INDUSTRY i
B' HAM, AL PT-T&I 6/82 3/85 j SOUTHERN COMPANY SERVICES B' HAM, AL MT-T&I 6/82 12/86 SOUTHERN' COMPANY SERVICES B' HAM, AL UT-T&I 6/82 12/85
! SOUTHERN COMPANY SERVICES 1
B' HAM, AL VT-T&I 6/82 3/85
! SOUTHERN COMPANY SERVICES i
B' HAM, AL ET-T 6/82 3/85 l SOUTHERN COMPANY SERVICES" B' HAM, AL PT-II 3/85 1/91 SOUTHERN COMPANY SERVICES B' HAM, AL VT-II 3/85 1/91 SOUTHERN COMPANY SERVICES
! B' HAM, AL ET-I 3/85 1/91 l SOUTHERN COMPANY-SERVICES i B' HAM, AL MT-II 12/86 1/91 SOUTHERN COMPANY SERVICES .
l 1/91 t' B' HAM, AL UT-II 12/85 SOUTHERN COMPANY SERVICES i
>'- ' '*1 '
~
O ouraza" auc'=^* co">^"v SOUTHERN NUCLEAR COMPANY
"^". ^t B' HAM, AL ET-I 1/91 7/92 i
CORDES D.R. -CONTINUATION-EXPERIENCE IN METHOD REFERENCE FACILITY / INDUSTRY LOCATION MTD/ LEV FROM TO SOUTHERN NUCLEAR COMPANY B' HAM, AL MT-II 1/91 7/91 SOUTHERN NUCLEAR COMPANY B' HAM,. AL UT-II 1/91 5/91 SOUTHERN NUCLEAR COMPANY B' HAM, AL VT-II 1/91 2/97 SOUTHERN NUCLEAR COMPANY B' HAM, AL UT-III 7/91 PRES.
SOUTHERN NUCLEAR COMPANY B' HAM, AL PT-III 7/91 PRES.
SOUTHERN NUCLEAR COMPANY B' HAM, AL MT-III 7/91 PRES.
SOUTHERN NUCLEAR COMPANY B' HAM, AL VT-III 2/97 PRES.
O
. - - - ~ ~ . . . - - - . . , _ - . - . . . . - - . - . . - . ~ . ~ . _ . . . . ~ . . . . . _ . - . - . . - ~ . . . - . . . - . - - - - .
PAGE 3 OF 3 REFERENCE RELATED TRAINING SOURCE OR CO. LOCATION COURSE SUBJECT FROM TO CLASS BRS.
SCS B' HAM, AL PT-LEVEL I 6/82 6/82 4 SCS MT-LEVEL I 6/82 6/82 15 SCS-UT-LEVEL I 6/82 6/82 40 e
SCS
" UT-LEVEL I 9/82 9/82 4 C&L ENGINEER,INC " ET-LEVEL I 8/83 8/83 16 EPRI NDE CENTER CHARLOTTE NC VT-LEVEL I 6/84 6/84 40 EPRI NDE CENTER
" VT-LEVEL II 9/84 9/84 40 EPRI NDE CENTER
" UT-SLIC-40 9/84 9/84 13 C&L ENGINEER,INC B' HAM, AL ET-LEVEL I 2/85 2-85 24 SCS PT-LEVEL II 3/85 3/85 10 EPRI NDE CENTER CHARLOTTE NC UT-LEVELII 9/85 9/85 40 11/85 11/85 40 EPRI NDE CENTER UT (IGSCC) DET.
" UT-FLAW SIZING 5/85 5/85 40 EPRI NDE CENTER
, .EPRI NDE CENTER UT (WOR) 7/85 7/85 32 SCS B' HAM, AL MT-LEVEL II 11/86 11/86 12 2/87 2/87 40 EPRI NDE CENTER CHARLOTTE NC UT(SIZ. FRESHER SPERRY SCHOOLS B' HAM, AL RT FILM INTER 2/87 2/87 24 SCS
" UT AUTOMATED 9/87 9/87 40 GENERAL ELEC. SAN JOSE,CA VT-INVESSEL 7/88 7/88 32 ISSAQUAH,WA ET-LEVEL II 11/89 11/89 40 ZETEC i
SOUTHERN NUCLEAR B' HAM, AL UT' (ANNUAL 12/96 12/96 10 TRAINING)
SOUTHERN NUCLEAR B' HAM, AL VT IWE/IWL 12/97 12/97 16 4
' The above infonnation concerning my educational, training and j experience background is true and accurate to the best of my knowl ge i
m i+ - 2^- 9 4 Date Candidate fpr Core'ification
4 i
-CONTINUATION-REFERENCE RELATED TRAINING SOURCE OR CO. LOCATION COURSE SUBJECT FROM TO CLASS BRS.
]
1
)
i i
O
. i
" i I
l The above information concerning my educational, training'and experience background is true and accurate to the best of my j
O knowledge
? 9 e)
Y._ Date Candidate for Certification
~
~ ~ ~ ~
t #1 Examination Resort Southern Nuclear 6peratineDomn$ny j rne D h tet V. COME f SSI $2 N@o-7509
. .r 6 iic' inn / Examiner M . A. ' Br~n, De5Ntment W6 ,
Criteris Satisfied
{ } l NRC Licensed Operator Qualification According to:
- Yes ONo ON/A ANSI 3.4 1976, Revised 1983 10 CFR Part 55 Security Officer Qualification According to: Oyes No W/A NRC 10 CFR 73 A-=iin B Respirator Qualification According to: dyes No N/A OSHA 29 CFR 1910.134 NRC 10 CFR 20.1703 (a)(3)(v)
NRC NUREG - 0041 ANSI Z88.6 - 1983, Revised 1988 Fire Brigade Qualification According to: ~
Oyes No @/A OSHA 29 CFR 1910.156 Crane Operator / Rigger Qualification According to: Oyes No OS/A ASME/ ANSI B 30.2 - 1990 Dept. of Transportation Qualification According to : Yes No 9ff/A FMCSR 49 CFR 391.41 FMCSR 49 CFR 391.49 /
- tion Personnel Qualification According to: es No ON/A t ANSI / ASME BPV-XI-1 Evidence of d%=Wying diseas and/ of Medical Condition? Oyes No l
The em yee is capable of performing the required duties:
Without Restricitons O Corrective Lenses must be worn while performing duties Doistant ONear Both Hearing aid must be worn while performing duties O Must have second pair of corrective lenses on penon while performing duties Other Restriciton ifthis is a change in restriction, check here Exnlanation of restriction Does restriction require follow up? Yes ONo Iffesgiwfollow upplan.
' a. .e .M- "".ggj;g . g, gg4p:.g;:/;j:^ n 4.,;% g-;. : ; u,
, n:W J.3 ' i .g l
- c e:, vs FMility Representatw,Ie. _(5Ah.?.h> fk nu.<e.
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Page 12 of 14
SHARED
, FIGURE 2 FNP-0-AP-31 NDE Qualification Verification for FNP Contractor Personnel Rtype L1.27 O _NDE EXAMINER DIValerio, Paul 037-44-5685 SSI NAME SSN EMPLOYER WRITTEN PRACTICE Written practice (s) which govemed the attached certifications for tne above named examiner has/have been reviewed and approved as shown in the attached documentation.
SSl-A-005 Rev.17 and SSI-A-011 Rev. 8
~ ~ ~ ~ ~ ~
- CERTIFICATIONS 4 METHOD LEVEL CERTIFICATION RECERTIFICATION DATE DATE MT 11 3/24/96 5I2259
~
t PT 11 3/24/96 ~5722/99 UT ll 2/16/98 2/14/01
~
VT-1 11 2/14/98 2/13/0i- ~
VT-2 ll 2/14!98 2/i3/di~ ~~
VT-3 ll 2/13/98 2/13/01 ET Remarks N/A Attach Certification Records.
Note: Recertification required every three (3) years for Levels I and ll and five (5) years for Level 111.
EYE EXAM Date of Eye Exam: 10/15/98 Attach Eye Exam Results.
Note: Eye exams required annually. ,
Written Practice Approval, NDE Certifications, i I
and Eye Exams Reviewed By:
__j Signature f. . hh
\
.__ /6 /[-R Date Group Supervisor (s) or Team Leader (s) Approval (s):
~
5Ig' tu Signature Date Signature Date Page 1 of 1 Revision 11
M Sonic SystemsInternational, Integratedinspecam bernces &lnformanon Technology Inc.
y/
CERTIFICATE OF QUALIFICATION for Paul DiValerio 037-44-5685 i
This individual is ceniSed in accordance with Sonic Systems International, Inc.'s Qualificadon and Certification Procedure (s) SSI-A-005 Rev.17 and SSI-A-011 Rev. 8, which comply with the requirements of the American Society for Non-Destrucuve Testing Recommended Practice SNT-TC-1 A, ASME Section XI, and the American National Standard ANSI N45.2.6.
CERTIFICATIONS ;
i Method I Level l Certification Date i Ree rtification Date i Expiration Date i uguid Penetrant i 11 l 3/24/96 l N/A l 3/22/99 i Magnete Partete i il I 3/24/96 ! N/A 1 3/22/99 i Ultrasonte I il i 2/16/98 i N/A I 2/14/2001 1 Vrsual VT-1 l 11 1 2/14/98 i N/A I 2/13/2001 l Visual VT-2 ll 2/14/98 Pl/A ' 2/13/2001 l i l l l Visual VT-3 1 11 i 2/13/98 ! N/A ; 2/13/2001 l O
b umstatons: None.
2/17/98 N/A 2/17/99 j EYE EXAMS I j j l
ADDITIONAL CERTIFICATIONS / QUALIFICATIONS Appendix Vil Qualrfied i
RemewedBy l \
~
k.h O'N-W NDELewsIII f) Date
p ,
M QUALIFICATION AND CERTIFICATION
SUMMARY
Sonic Systems International, Inc. ,
O Name: Paul DiValerio SS#: 037-44-5685 V
CURRENT CERTIFICATION EXANilNATIONS METHOD LEVEL GENERAUBASICl SPECJMETHOD j PRACTISPEC. COMPOSITE j EXAMINER SCORE ;
SCORE l WT l SCORE l WT l SCORE l WT AE l l l l l l l l ET l l l l l l l l !
MT { li l 83.3 l0.33 90 j 0.33 l 97.5 l 0.34 l 90.3 i Paul A.Wngnt j PT l ll l 83.3 l 0.33 l 95 l 0.33 l 95 l 0.34 l 91.1 [ Paul A. Wngnt !
l RT i l l l l l l l :
UT 90 l 0.33 l 80 94 l 0.34 l 88.1 Paul A.Wngnt '
f l 11 l l 0.33 l I l W l l l l l l l l l VT 1 l ll l 86.68 l 0.33 l 100 l 0.33 l 92.5 l 0 34 l 93.1 ! Paul A. Wngnt l VT-2 l 11 l 90 l 0.33 l 85 l 0.33 l 95 l 0.34 l 90.1 i Paul A. Wngnt e VT-3 l 11 l 95 l 0.33 l 85 l 0.33 l 92.5 l 0.34 l 90.9 i Paul A. Wngnt t EDUCATION riigh School Graduate- South Kingston High School Wakefield, RI.,1980 TRAINING 40 Hours - Advanced Uttrasonic Flaw Detecton and Sizing, IESCO / Hellier /.ssociates
/]
(/
60 Hours - Visual Examinaton Techniques, VT-1,2,3 EPRI Equrvalent, SSI 8 Hours - Visual Examinaton Techniques, Contamment inspecton, EPRI Equivalent, SSI 96 Hours - Ultrasonic Laboratory /Practcal, STP, General Dynamics, Richardson X-Ray, Inc.
22 Hours - Uttrasonic Annual Retraining, STP, LMT 80 Hours - Basic Ultrasonic Techniques, Hartford Steam Boiler 24 Hours - Magnetic Partele Techniques, Electnc Boat Divsson of General Dynamics 16 Hours - Liquid Penetrant Techniques, Electnc Boat Divsion of General Dynamics 40 Hcwes - Visual / Dimensional Techniques, Electne Boat Divsion of General Dynamics 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> - Eddy Current Techniques, Electne Boat Dusion of General Dynamics 40 Hours - Blue Print Reading, Electne Boat Dmsion of General Dynamics 96 Hours - Radiography and Film Interpretaton Techniques, Connecteut Yankee Nuclear Generaung Staton 32 Hours - Laser Weld UT (LWUT) Collection & Analyss, Wesunghouse EXPERIENCE Initial Method Certification Date AE l ET l MT PT l RT l UT VT l VT-1 ! VT-2 l VT-3 l l 1/1/81 1/1/81 l l 1/1/81 l 1/1/81 l 1/1/87 l 1/1/87 The individual has been performing NDE/QC related actMues since 1981. He has gained expenence in Power Plant, Refinery, Aerospace, QC, Structural Steel and Manne inspecton performing visual, surface and volumetne examinatons on vessels, structural supports, manne hulls, turbine / generator, piping and related components.
Ths individual has gained expenence at the following Nuclear Power Plants: San Cnofre, Praine Island, Vogtle, Maine Yankee, Kewanee, South Texas Project, Farley, Comanche Peak, Braidwood, Calaway, Cooper, Ginna and Byron.
l l
l l The above sndsvudual meets or escaeds the uninal ancor connnued rernpcanon requsrements as specuped on Some Systems Internanonal, inc 's
( Quahpcation Procedures. For vabdanon currens eye test must accompany this cornpcanon. l
\ $
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NDE Revsew () Date
10/09/98 14:45:55 >
% r ., s .
s r- y 7 FNP-0-M-24 v t . .
FIGURE 2 ,
Southern Nuclear Operating Company / Farley Nuclear Plant
- Nondestructive Examination Personnel Vision Test i Employce Name Last Dii/4 teitto First ~PAOt M.I. E l SSN 037- W - %pff Part I pefsNewing ger.saises are de he asked by de exams &ser sad resneer recorded:
A. Can you see out d both eyes? des O No i B. Do you pnmently were conective lenses of any idad while perfamung ===t==? O Yes [No l C. Do you have any known probleens with yow eyesight? O Yes No D. Are you color blind or de6cient? O Yes [I4o (F l Part 2 For certi6 cation to ASME Section XI,1992 Edition,1992 Addenda Vision A6,i-w Cnterut Personnel shall rl==a=*ste natural or corrected acusty of 20/25 or greater Snellen fraction, with at least one eye, by reading words or identifying characters on a near distance test chart (Jaeger chart or equal) that meet the requirements ofiWA-2210.
Uncorrected Corrected IUght eye 7 SAT O UNSAT Right eye O SAT O UNSAT lea eye @ SAT O UNSAT LeAeye O SAT O UNSAT Part 3 For certi5 cation to all other Codes and Standards Near Vision A-- p = Cntena Personnel shall demonstrate natural or corrected acuity, in at least one eye as deternuned by the ability to read the Jaeger Number One on a standard Jaeger test or a distance test pattern equivalent to a Snellen fraction of 20/20.
Uncorrected Corrected Right eye EV SAT O UNSAT Right eye O SAT O UNSAT lea eye I SAT O UNSAT lea eye O SAT O UNSAT Part 4 Far Vision Ava~ Cntena Personnel shall demonstrate natural or w.4 far distance acuity, in at least one eye, equivalent to a Snellem O fraction of 20/30 or equivalent.
Uncorrected .
Corrected Right eye GI SAT- 0 UNSAT Right eye O SAT O UNSAT Le8 eye I SAT O UNSAT lea eye O SAT O UNSAT Part 5 For certification for methods that requae color identification Color vision Acceptance Criteria Personnel shall be able to identify all patterns or numbers in a standard Ishihara book, or equal method as described ia paragraph 8.1.1.3.
Ishihara NAT DUNSAT Other Method O SAT OUNSAT List color deficiencies 1
> 1 Part 6 F ;':-yu has successfully passed the vision test for:
ASME Section XI,1992 Edition,1992 Addenda (Part 2) ET Yes O No O N/A Near Vision (other than 1992 Section XI) (Pert 3) EP Yes O No O N/A Far Vision (Part 4) lip Yes O No O N/A Color Vision (Part 5) (Yes O No O N/A Medical Fm-na= Signature - Date pV Employee Signature / ., } Date j /u W uca> #&N Page1of1 Revision 16
r% M Sonic integratedInspecnon Systems International, Inc. '
Sernces & Informanon Technolog
( )
%J VISUAL ACUlTY EXAMINATION RECORD for DiValerio, Paul 037-44-5685 .
This visual acuity examination is in compliance with ASNT document ASNT-TC-1 A. the ASME B & PV Code, i Section XI, and Sonic Systems International. Inc.'s procedure SSI-ES-001, Rev 5.
- 1 Far Distance Acuity: ! Vision (Snellen Test).
i
@ Natural Q Right 20/20 other l O Corrected e Left 20/2c otner i i
@ Both 20/20 other l Near Distance Acuity: l 1 Natural Vision (Jaeger Chart).
i n~ Corrected O
V l .
8 Right J1 other Color Contrast Acuity:
! O Left J1 other (si Normal
~
I l ! S Both J1 other O At. norm 61 !
Comments None Administered By: W. Andrew Mixon 'lt.',M Q A d3
~
Date: 2/17/98 (3
Sunday, February 22.1998 CertWorns v4.1.3 Page 1 of 1
SHARED FIGURE 2 FNP-0-AP-31 NDE Qualification Verification for FNP Contractor Personnel __
Rtype L1.27 U NDE EXAMINER Erickson, Scott R. 473-76-5186 SSI NAME SSN EMPLOYER
--,ms .w.g= -
WRITTEN PRACTICE Written practice (s) which govemed the attached certifications for the above named examiner has/have been reviewed and approved as shown in the attached documentation.
SSI A-005 Rev.17 and SSI-A-011 Rev. 8
~ ~~~'~
CERTIFICATIONS METHOD LEVEL CERTIFICATION RECENTIFIChTION' DATE DATE MT ll 10/12/97 9/19/00
~
PT 11 10/12/97 9/19/00 UT 11 10/12/97 9[21/50 ' ~
RT 1 VT-1 11 10/12/97 9/25[dd~~ ~
VT-2 ll 10/12/97 9/5I/60~~~
VT-3 11 10/13/97 9/21/00 '
ET Remarks UT Certification Liraited to Non Section XI Examinations. 4 1
Attach Certification Records.
Note:
Recertification required every three (3) years for Levels I and 11 and five (5) ye{for Level ill.
EYE EXAM Date of Eye Exam: 10/8/98 Attach Eye Exam Results.
Note: Eye exams required annually.
Written Practice Approval, NDE Certifications, and Eye Exams Reviewed By: _
ja yf-f g Signature / Date Group Supervisor (s) or Team eader(s) Approval (s):
$_ - - - - . . - - . . _ l if-.--
Signature Date Signature Date Page 1 of 1 Revision 11
M Sonic IntegratedInspection SystemsInternational,Inc.
Services & Information Technology
~
CERTIFICATE OF QUALIFICATION -
l for l
Scott R Erickson 473-76-5186 l l
This individual is certified in accordance v.ith Sonic Systems International, Inc.'s Qualification and Certification Procedure (s) SEI-A>J05 Rev.17 and SSI A-011 Rev. 8, which comply with the requirements of the American Society for Non-Destructive Testing Recommended Practice SNT-TC. i 1A, ASME Section XI, and the American National Standard ANSI N45.2.6. !
I CERTIFICATIONS l Method I Level I Certification Date l Recertification Date l Expiration Date l Liquic ?enetrant l 11 l 10/12/97 l N/A l 9/19/2000 Magnetc Particle l 11 l 10/12/97 l N/A l 9/19/2000 Ultrasonic l 11 l 10/12/97 l N/A l 9/21/2000 Vrsual VT-1 l 11 l 10/12/97 l N/A l 9/21/2000 Vrsual VT-2 l !! l 10/12/97 l N/A l 9/21/2000 Vrsual VT-3 l 11 l 10/13/97 l N/A l 9/21/2003 t
V Limitatons: None.
O/8/98 N/A 10/8/99 EYE EXAMS l l l l ADDITIONAL CERTIFICATIONS / QUALIFICATIONS
[EPRl] Appendix Vill PDI Qualrfied - Depth Sizing in Femte and Austenitic including IGSCC
[EPRl] Appendix Vill PDI Qualtfied - Detection in Femte and Austenttic including IGSCC I
i l
RenewedBy J
) / [/ /O ~T -N Pau1A. Wright, N1$ElevelHI Date d
l'
M I
QUALIFICATION AND CERTIFICATION
SUMMARY
Sonic Systems International, Inc, q Name: Scott R Erickson SS#: 473-76-5186 N.I CURRENT CERTIFICATION EXAMINATIONS METHOD LEVEL GENERAL / BASIC ' SPECJMETHOD l PRACT/ SPEC. l COMPOSITE EXAMINER i SCORE SCORE l WT SCORE WT l SCORE l WT AE I l l ;
ET l l l 1 MT 11 l 96.7 0.33 90 0.33 98 l 0.34 l 94.9 l Paul A.Wnght PT 11 90 0.33 100 0.33 l 95 l 0.34 l 95.0 l Paul A. Wnght RT l l l l l !
UT 11 100 0.33 95 l 0.33 96 ; 0.34 j 97.0 l .oaul A. Wnght j l VT l l l l l VT-1 l 11 93.3 0.33 90 0.33 l 90.5 l 0.34 l 91.3 ! Paul A.Wnght !
VT-2 l 11 95 0.33 95 0.33 l 98 l 0.34 j 96.0 l Paul A.Wnght I, Paul A. Wnght VT-3 l 11 } 95 l 0.33 85 l 0.33 l 95 l 0.34 l 91.7 l l EDUCATION NDE Technology Hutchinson Area Vo-Tech. Institute- Hutchinson, MN.,10/01/1983 High School Gradua'e- Hutchinson High School- Hutchinson, MN,1981 TRAINING 55 Hours - Magnetc Partete Techniques, Hutchinson Vo-Tech p 60 Hours - Uquid PenetrantTechniques, Hutchinson Vo-Tech
(" ) 122 Hours Basic Ultrasonic Techniques, Hutchinson Vo Tech i 32 Hours - Advanced UT for Weld Overtay, EPRI l 40 Hours - Advanced UT for the SG:ing of IGSCC, EPRI 64 Hours - Advanced UT for the Detecton ofIGSCC, EPRI 20 Hours - Ultrasonic Techniques / Annual Retraining, LMT, Inc 84 Hours - Vtsual VT-1,2,3/4 inspecton Techniques (EPRI Equivalent), VCR, Inc 55 Hours - Visualinspecton Techniques, Hutchinson Vo-Tech EXPERIENCE initial Method Certification Date AE ET MT PT RT UT VT l VT-1 VT-2 VT-3 7/1/84 7/1/84 7/1/84 l 9/1/92 9/1/92 9/1/92 This individual has been performing NDE/QC related actvites since 1984 in Power Plant, industnal and Febncation Facilities. Expenence has been gained performing PSI /ISI visuat, surface and volumetne examinatons on Class 1 and 2 piping systems and related components in Inspection, Technical, Supervisory and Project Management Posibons.
This individual has gained experience at the following Nuclear / Fossil Power Plants: Fariey, Quad Cites, North Anna, Surry, Montcello, Maine Yankee, Palo Verde, Byron, Praine Island and Vogtle.
The above sndsvedual meets or exceeds she sninal an&or contsnued cernfncatson requorements as specifsed m Somc Systems /neernanonal, Inc.'s Qual)lcanon Procedures. For validation current eye test must accompany this certificanon.
O.
r <
dA.tvH+ /H 98 PaulA. Wright, NDE'l$velIIIRevsewer Date
/
a - - - , -2. . a. - -.m._ _ _ A.C ..a ---. . .d *- -.m=a. -+ a .sdaA e J * #i-- .moMar -'4 ,-a --s--+-eaa.--4 4--a d. a. a h --a*,-e--=
FIGURE 2 Southern Nuclear Operating Company / Farley Nuclear Plant Nondestructive Examination Personnel Vision Test f Employee Name: Last t:r;e 4 ru First /cs H M1 X l SSN Wf.1(-/7/ 6
\
Part I Defoueweng questbens are to be asked by ne exammar and resada recorded:
A. Can you see ov;of both eyes?
j LT Yes O No B. Do you presently were correcuve lenses of any kind while performmg exammanons? FYes C. Do you have any known problems with you eyssaght?
Ojo D. Are you color blind or deficasat?
O Yes O Yes Ofa O No Part 2 For cerufication to ASME Section XI,1992 Edition,1992 Addenda Vision Acceptance Critena:
Personnel shall demonstrate nanirs! or corrected acuity ot'20/25 or greater Snellen fraction. with at least one eye, by reading words or idenufymg characaers on a near distance test chart (Jacger chart or equal) that meet the requirements ofIWA-2210.
Uncorrected Corrected Right eye O SAT I UNSAT Right eye
[JAT O UNSAT O SAT [UNSAT Lea eye lea cye 1V SAT O UNSAT Part 3 For cernficanon to all other Codes and Standards Near Vision F=~e Criteria Personnel shall demonstrate natural or aM acuity, in at least one eye as determined by the ability to read the Jaeger Number One on a standard Jaeger test or a distance test panem equivalent to a Saclica fraction of 20/20.
Uncorrected Corrected Right eye O SAT I UNSAT Right eye [ SAT O UNSAT Lea eye O SAT C/ UNSAT lea sye SAT O UNSAT Part 4 Far Vision Acceptance Criteria Persoma l shall demonstrate nat ral or arrected far distance acuity, in at least one eye, equivalent to a Snellen fraction of10.h equivalent.
O Uncorrected Right eye O SAT Ef UNSAT Corrected Right eye [ SAT O UNSAT l Left eye O SAT I UNSAT I4A cye [ SAT O UNSAT '
Part S l For certification for methods that require color identificarion Color vision Acceptance Criteria Personnel shall be able to identify all pattems or numbers in a standard Ishihara book, or equal method as desenbod in paragraph 8.1.1.3. I Ishihara VSAT DUNSAT l Other Method O SAT CUNSAT )
List color deficiencies 1 l
1 l
Part 6 Employee has successfuDy passed the vision test for:
)
ASME Section XI,1992 Edition.1992 A/denda (Part 2) (Yes O No O N/A 1 Near Vision (other than 1992 Section XI)(12 *.3) ETYes O No O N/A Far Vision (Part 4) (Yes O No O N/A Color Vision (Part5) 7Yes O No O N/A 1 Medical Exammer Signature Date 1 7%) [A 1 * -/- tr CkoDI k. $hbr1 to W A 1 U l Page1of1 Revision 16 l
.. l I
i l
APPENDDC 1 NDE VISION EXAMUfATION REPORT SOUTHERN NUCLEAR NAME (LAST, FIRST, MJ. ) [A/cgge y, $co77 ff SSN 973-74-y/
PART I The following questions are to be asked by he examiner and te resuhs recorded.
A. Can you see out of bo6 eyes?
B. Do you p .iy wear corrective lenses when h No performing inspecnons?
C. Do you have any known problems with your cytsight?
hYES NO D. Are you color blind or deficient? YES 1
FART 2 The following vision tests art to be ' 4 by the czaminer. '
Uncometed 0Right 2W t av Conected Right 2W 2o l l ! aft 2W 2.s I.mit 2W {o .I Bos 2W 2 <
Uncorrected Rigar 2W L Comend Right 2W 7/
l Left 2W 7f laft 2W f'f lM 2W 7/ Both 2W ff rut ou s tsio% '
O l
TEST METliOD I ISHIHARA BOOK 1
ISHDIARA RESUL'IS Acceptable [ U= =-F-Mc PRACTICAL 17.ST COLOR WIRE CHECKLIST BLUE Pass Fail BLACK Pass Fail BROWN Pass Fail ORANGE Pass Fail RED Pass Fail #HITE Pass Fail PURPLE Pass Fail YELLOW Pass Fail GREEN Pass Fail GRAY Pass Fail APPLICANT HAS SUCCESSFULLY PASSED THE VISION EXAMINATION FOR NDE INSPECTIONS -
ACCORDING TO:
ANSI /ASME BPV Code, Sectica XI-1:
PAR VISION: YES_ NO _ NEAR VISION: YES NO _ COLOR VISION: YES[NO _
EXAMINER Date NAME(print) p3,g 7, , . f ,. j.9f Signanue of Frammer N M Dane /*~*
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8 In Ausa Ith the PDI implementation of Section XI, Appendix VIII
, . I Stemmary of Personal Qinalifications for
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Candidaie: Scott Erickson; ID#: 473-76-5186 b;.~/'y, 12... .j c
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Procedure Detection Length Sizing Through Wall Sizing __
Bolting Ferritic Austenitic Ferrific Austenitic Ferrific Austenitic Ferritic woncsec wacsec wencscc wacsce ..ncscc wncsec sins. hu i sing. tw i sing. punt sing. rm.: sing. Du.I sing. ths.1 sing. pu.i sing. twee sing. pu. sie.d s.ee s.ee sided sued sided sided sided sided sided sided sided sided sided sided sided sided sided sided sided sided sh. rr.he ernbe Endrs PDI-UT-1 v Aa0 Yes Yes PDI-UT-2 vAa0 Yes Yes .
PDI-UT-3 vAa0 Yes Yes a
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,. Performance Demonstration Initiative Program ", , ," g" i '* " " ," ,
1 In Accordance with the Ppl Implementation of Section XI, Appendix VIII e4tel3ee r
. Specific Detail of QualiGcations
, I .
_'.., , i
- q. .. ,, . . .I- Candidate: Scott Erickson ID#: 473-76-5186
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V %, 5 f.- Procedure: PDI-UT-1; Revision: A; Addenda: 0
. - p tw l.i, jjl ,
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- My..i,; '. -j 4,3 ( ... . I PDI Generic Procedure for the Ultrasonic Exasninption of Ferritic Pipe Welds f -
PIM)S Rev: 0 Date et Issue: Ol-Jas;% !
, , . ,'.J ,i,i, Owner: Ibformance I kmonstration inniative Analysis SW Typentev: N/A t
, . - (, , liardware: N/A g Operator SW Typester: N/A !
- . . ~ 'i 3 Category
- hping Scan Appilcetion: Manual
- $*, ;l I
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8 When " length Sizing
- is indicased. the 0.750 RMS accepeames crheria per she PDI Program Desestymon has been achieved When 'Through Wa5 Siring" is indicated the 0. I25 RMS accepeance crheria per the PDI Progeme Description has been achieved ;
i Teleesaces for neM appIIestions as follows:
Diameter:
- IE.er- 1se minimism diameser ciernonsirased ,
Upper: Diameters greasee than 24* need not be demonstrased Thickness:
Imwer: 0.100* can be adieracted from the minimum thickness demonstrated for boek ====aa=it ic and ferritic Upper: 1000* can 14 added to the maximum thickness demonsermoed for ferrific sne aerial
. 0 500* can be added to the manis men thickness demonstrated for aussenhic ruanerial.
l 5
' lnis candnisse has met the practical mpairements of Appendix Vil: No ,
Comments: 1 See procedure and a'1 ached Tatile 1 for a ast of qualiAed search unit 4nstrument combinations. l IJrnisations: +
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I Performance Demonstration Initiative Program ',[;';,.'""*,'l In Accordance with the PDI implementation of Section XI, Appendix VIII e4:e 3ee
~
, , , Specirsc Detail of Qualificalions y
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a Candidate: Scott Erickson ID#: 47}-76-5186
- i. 1. i. ..Q;[@ um. ,yj l'rocediare: PDI-UT-1; Revision: A; Addenda: 0 ,
! $ .4 ' 'S/hs[N , ,
hf! {i!f[.ij PDI Generic Procedure for the Ultrasonic Examination of Ferritic Pipe Welds .
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Ilardware:
Perfonnance Ikrnonstrwien Inish aive N/A Analysis SW Typetitev:
Operater SW Typenter: N/A N/A
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The above candidate has met the requirements of The Performance Denionstration I Initiative's Implementation of The Aenerican Society et .'4echanical Engineers Roller and essure Vs a sel Code, tion XI, Appendix VIII, as sev-d in this document. '
1 0
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, . .Ie R ' .2 7f CarlI I stiolais Performance Iksnonstration Initiative
- Piping and Bolting Supervisor /I.evel III ;
i I * l b.f f F.I Becker Performance Demonstration Initiative Administrator ;
s i
This docuument Es met authentic withent a raised seat.
P e 1 et 1
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. Performance Demonstration Initiative Program ,.;'gi '*""',"
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in Accordance with the PDI implementation of Section XI, Appendix VIII Specific Detall of Qualifications edleljee I
,' j -
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if; .[ ' Candidate: Scott Erickson ID#: 473-76-5186 '
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Procedure: PDI-UT-2; Revision: A; Addenda: 0 fg"
- f. i /g) l9,;f '
- . cl,.e{j . PDt Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Wekts
! '! ,) h 8 D 'iI id pu ns me,: 0 Date of Issue: 01 Jan%
\
[ 'l g Owner: IYrformance Demonstraelon Initisive Analysis SW Typester: N/A
+e } ,9 b4 j- $
,? Hardware: N/A Operater SW Typeater: N/A
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' I, g-Uf,N .'9 Ranges DeinenStrated; l Date: 27-Jun-94 04101300 ,
MinDiam: 2 000 MinThick: 0 337 !
Mand 6aan: 36 000 Me Thick: 2.900 i Material: Aussenitic with IGSCC !
Esassinatten: Ikiection ;
Acress: Ihnele Skled ~
WeW Cond: Grinnul Flush i WeW Cand: Hat Top Access: Single Sided ;
WeW Cond: Ground Flush WeW Cand: Flat Top l
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, "] Performance Demonstration Initiative Program ,,g In Accordance with the PDI implementation of Section XI, Appendix VIII eite:3ee Specific Detail of Qualifications
- ,_.,' ~ y 'Ni q,,
. Candidate: Scott Erickson ID#: 473-76-5186 p.g}-
I # :')[?.'N.
. ' ' c,I;.3 ;g.} Procedure: PDI-UT-2; Revision: A; Addenda: 0 ;
F ';.' ? PDI Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Wekts [
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, !* .' b ' t Owner: IVrfonnance Ekmonstration Initisive Analysis SW Type /Rev: N/A
. *d .I'. !; e. * [. Ifordware: N/A Operater SW1ypester: N/A !
. * ;;; i! ;fff {' i,.j Category: Piping Scan Applicalion: Manual
. .:, ( ,7 g1 i.:-
i The above candidate has met the requirements of The Performance Demonstration !
Initiative's Implementation of The American Society of Mechanical Engineers Boiler i and P urg Vesi i Code,Section XI, Appendix Vill,as stated in this document. ,
f
, J7 Date h -
Carl L. I.stinlais !
Performance Demonstration Initiative ;
i Piping and Bniting Supervisor /I.evel III f
v -
Date // r 7
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F. I. Becker Performance Demonstration Initiative Administrator ;
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i This decuaneneis met sotheaste witheast a rotsed seat. [
. - - - - _ _. ---________-___-_______--_--__-___--______?_#_ '* --__--_____--__-_-_______--__---_-__-~ - _ _ - -_
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, Performance Demonstration Initiative Program ";. 2"'"j' In Accordance with the PDI Irnplementation of Section XI, Appendix VIII eale 3ee '
i , Specific Detail of Qualifications
[
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, Candidate: Scott Erickson ID#: 473-76-5186 :
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V. ;s Procedure: PDI-UT-3; Revision: A; Addenda: 0 j,hih'[f f,i it,:
._ PDI Generic Procedure for the Ultrasenic Through Wall Siring in Pipe Welds
,f ' I '
.W!
jj , 3*Dys me,: 0 Date of Essue: , 01-Jan-%
i' f Owner: I erformance Demonstration Inisimive Analysis SW Typentev: N/A
[. '",. 7 - [j';D
.* '. ,,-g; - Ilardware: N/A Operaler SW Type / Iter: N/A i
M ;; 6 Category: INping Scan Appilcaelen:
' , l'/ f'. '> .: -
Manuel
.> i Ransres Densionstrated:
h.
Dele: 27.Jun 94 041Ql300 Date: 27.Jun-94 04101300 Minnlem: 4 000 Minnkk: 0337 MinDiam: 4 000 Minnkk: 0 337 Me Diam: 36 000 Meankk: 2 625 Memplem: 50 000 Mesukk: 3 850 fs Meteriel: Aussemitic wish IGSCC Meterial: Territic Examingelan: Brough Well Siting Esen Instlen: Drough Well Siring
- Access: DouNe Sided Access: Doulde Sided -
WeW Cond: Ground I%sh WeW rend: Ground Flush I
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i Performance Demonstration Initiative Program " , . ' ' "J';,.2*-""]
In Accordance with the PDIImpiesnentation of Section XI, Appendix VIII estel3ee .
Specific Detail of ()nalifications
' i Candidate:Scon Erickson ID#: 473-76-5186 p .. .
Yb . ~. 4, g. ~i ,1 Procedure: PDI-UT-3; Revision: A; Addenda: 0 ,
i i ;f) [. .,$.
p PDI Generic Procedure for the Ultrasonic Through Wall Siring in Pipe Wekts
- i_ , Y f 'I t h$2EM [d[,5 . rpQs Rey
- 0 ' pale ofIssue: 01-Jan-%
> . r - c' [o .ift g* * % Owner: Analysis SW Type /Rev: N/A
- I fi,.g i Performance Demonstration initissive
.,- e :) , f , rj Hardware: N/A Operater SW TypelRev: N/A ,
' ' I .y j Category: liping i Scan Application: Manual i
When
- Length Sizing"is indicased. the 0.750 RMS acceptance criteria per the PDI Program Description has been achieval.
When *1brough Wall Siring
- is indicated, the 0.I25 RMS recqtance criteria per the PDI Prograsn Descriptson has been achieved.
i Tolerances for neld applicselens as follows:
Diameter; lewer: The minimum diameter dernonstrased _
Upper. Diameters greater than 24" need not be demonstrated.
Thickness:
Imwer 0.100* can te subtracted from the mankman thickness demonstrasal for both auseenitic and ferride Uppqr: 1000" can te added to the ineximum thickness demonstrated for ferritic material. .
0 500* can be added to .he maximum thickness demonstrated for austenitic maserial.
~
8 This candidase has met the pracdcal requirements of Appendix VII: No s
Comments: 1 See procedure and attached Tate.e 1 for a Nst of quaHRed search unMnstrument combineWons.
[
I. imitations: 1 This procednekarx9date is not cpsaHRed to depth size Raws located on the far side of the weld where the utnsonic beam is required to propagate tirough weld ;
material. ConArmaton of Raw size from sie opposite drection, when possible is acx:eptable.
2 This proceduratandidate is only quahRed to depdi size Raws crfentated in Wie circumferenflaf dirockon.
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.. j Page 2 of 3 ;
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,s Perforniance Demonstration Initiative Pronram D PDQS No: 54 i-
. In Accordance with the PDI implementation of Section XI, Appendix VIII e4:st3ee 1
. Specific Detail of Qualifications
";. , . , Mt .. L.ka. 4' Candidate: Scott Erickson ID#: 473-76-5186 1
', .,. u n v,c,:p4',;j:,
., %p.'t. FQ; Procedure: PDI-UT-3; Revision: A; Addenda: 0 PDI Generic Procedure for the Ultrasonic Through Wall Siring in Pipe Welds
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( PDQS Mev: 0 Date of Isame:
Analy* SW Type /Itev:
OI.Jan 96
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. y .; Category: Mping Scan Application: Manual
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The shove candidate has met the requirements of The PerfC-- c Demonstration Initiative's implementation of The American Societ of Mechanical Engineers Boiler ,
and P ode,Section XI, Appendix VLi, as stated in this document.
ire Vessel { $ A- i
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Carl 1. I.atiolais 6
Performance Demonstration Initiative i Piping and Bolting Supervisor /I.evel III l
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M M_ t F.I. Rectier i
Performance Demonstration Initiative Administrator l l
I This docuseeni is niet authemele with=sut a rolsed seal.
Page 3 et 3
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PROCEDURE LIST
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The following procedures were used in the performance ofInservice Examinations at the Farley Nuclear Plant - Unit I during the 15th refueling outage. Copies of the procedures are available in the FNP Document Control.
PROCEDURE TITLE REVISIONffCN NUMBER FNP-1-STP-156.2 CLASS 1 PIPING INSERVICE PRESSURE TESTING 0 FN P-0-NDE- 100.21 VISUAL EXAMINATION VT-1 1 l 1
FNP-0-NDE-100.22 VISUAL EXAMINATION VT-2 2 l 0 -
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NG EXAMINATIONS SCHEDULED THIS OUTAGE l
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i ALL NIS-2 FORMS INCLUDED WITH OUTAGE REPORT FOR INTERVAL 3 PERIOD 1 OUTAGE 1 l
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