ML061840549
| ML061840549 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 06/29/2006 |
| From: | Pace P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MC9639, TAC MC9640, TAC MC9641 | |
| Download: ML061840549 (28) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 JUN 2 9 2006 10 CFR 50.4 U.
S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C. 20555-0001 Gentlemen:
In the Matter of
)
Docket No.
50-390 Tennessee Valley Authority WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)
INSERVICE INSPECTION (ISI) PROGRAM REQUEST FOR RELIEF 1-ISI-16, I-ISI-17, 1-ISI-18, AND I-ISI-19 REQUEST FOR ADDITIONAL INFORMATION (TAC NOS.
The purpose of this letter is to provide a response to NRC's request for additional information dated April 27, 2006, concerning TVA's request for relief dated January 25, 2006.
The Enclosure provides TVA's response to NRC's questions.
There are no regulatory commitments associated with this submittal.
If you have any questions concerning this matter, please call me at (423) 365-1824.
Sincerely, P..Pace Manager, Site Licensing and Industry Affairs Enclosure Cc:
See Page 2 Pmted on wrced pawr
U.S. Nuclear Regulatory Commission Page 2
-JUH 2 9 2006 Enclosure cc (Enclosure):
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr.
D.
V. Pickett, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08G9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23T85 Atlanta, Georgia 30303
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 REQUEST FOR RELIEF I-ISI-16, I-ISI-17, I-ISI-18, AND 1-ISI-19 This letter provides TVA's response to NRC's request for additional information dated April 27, 2006, concerning TVA's Inservice Inspection Program requests for relief dated January 25, 2006.
Below are the responses to NRC's questions:
RELIEF REQUEST 1-ISI-16:
NRC QUESTION 1 Are there any other welds, within the examination category, that can be examined that will provide essentially 100 percent coverage of the examination volume?
TVA RESPONSE The risk informed segment which includes weld SIF-D092-15 is classified High Safety Significant.
The postulated failure mechanisms for the segment include Stress Corrosion Cracking (SCC).
All welds in this segment that are subject to SCC must be examined every ten years.
Weld SIF-D092-15 is the only weld in this segment that is subject to SCC.
Therefore, there are no other welds in this segment to substitute for SIF-D092-15.
NRC QUESTION 2 Please confirm that personnel performing the single-sided examination were Performance Demonstration Initiative-qualified, and provide the appropriate ASME Section XI, Appendix VIII supplement(s) to which they qualified.
TVA RESPONSE TVA confirms that personnel performing the single-sided examination were Performance Demonstration Initiative (PDI) qualified.
Copies of the individual qualified examiner's certifications are provided in Attachment 1. The appropriate ASME Section XI, Appendix VIII Supplement to which the examiners were qualified, are listed on the Certifications.
NRC QUESTION 3 Other than radiographic examination, what other volumetric techniques were considered to increase volumetric coverage, and why were they not pursued?
E-1
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 REQUEST FOR RELIEF I-ISI-16, 1-ISI-17, I-ISI-18, AND I-ISI-19 TVA RESPONSE Currently, ASME Section XI lists three types of volumetric examination methods (Eddy Current, Radiography, and Ultrasonics).
As required by ASME Section XI, and listed in the latest edition of the Electric Power Research Institute (EPRI)
PDI qualified procedure, PDI-UT-2, "Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds," Revision C, the required examination volume to be examined is basically the lower one third thickness of the weld for a distance of 1/4-inch from the toe of the weld.
In order to perform an adequate examination of the required volume utilizing the Eddy Current Examination Method, an extensive modification would be required to gain access to the inside diameter of the weld since the component is a Pipe to Tee weld configuration.
Although radiography could be utilized, it is a less sensitive examination in detecting flaws unless the radiographic beam passes thru the weld oriented along the same plane as the flaw, which may require several radiographic shots resulting in additional dosage to personnel.
As indicated above, the Appendix VIII qualified ultrasonic examination technique was developed to provide the best method for detecting flaws in the required examination volume, as required by Supplement 2 of ASME Code Section XI and mandated by 10 CFR 50.55a.
NRC QUESTION 4 What are the general area, contact, and 12" dose rates at weld SIF-D092-15?
TVA RESPONSE Weld SIF-D092-15 is at the intersection of the 6-inch emergency core cooling system (ECCS) flow path with the 14-inch Residual Heat Removal (RHR) letdown line off of reactor coolant system (RCS)
Loop 4 hotleg.
The weld of the 6-inch elbow to the 14-inch x 14-inch x 6-inch Tee is just a few feet from the RCS piping.
No specific radiological survey was performed for this weld inspection activity.
- However, a pre-shielding survey of the hot legs on RCS Loops 1 and 4 was conducted just days before the weld E-2
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 REQUEST FOR RELIEF I-ISI-16, l-ISI-17, 1-ISI-18, AND I-ISI-19 inspection.
The results of the radiological survey were as follows:
General area 25 millirem per hour (mrem/hr) 30 centimeters 35-40 mrem/hr Contact 80-100 mrem/hr These survey results are a good approximation of the dose rates at the weld location since the weld is only a few feet off of the RCS loop.
RELIEF REQUEST 1-ISI-17 AND 1-ISI-18:
NRC QUESTION 5 Provide an explanation of Actual Increment and Scan Positions in relation to the limitations of the weld scans.
TVA RESPONSE The actual increment and scan positions indicate the specific start and stop position readouts indicated by the scanner for the raster scans.
Depending upon the specific scanner axes used for incrementing and scanning, the readouts typically represent inches or degrees.
These readouts allow the examiner to determine the length of the scan that was accomplished at each increment location, which is used to compute coverage obtained.
NRC QUESTION 6 Compare the limitations on coverage of welds W01-02, W02-03,
- W2A, W2B,
- W2C, W2D, W2E, and W2F, with the limitations from any previous scans of the welds, such as preservice inspections, and explain any areas of less coverage than on previous exams.
Discuss the results of the comparison.
TVA RESPONSE The Pre-Service Examination of the WBN reactor vessel was performed during October-November, 1978.
The exams were performed to the requirements of Section V and Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition through the Summer 1975 Addenda.
In accordance with Paragraph 1-5213 of Section XI, only the limitations were required to be listed on the examination report.
The requirement to calculate the extent of coverage was not required until Regulatory Guide 1.150, E-3
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 REQUEST FOR RELIEF 1-ISI-16, I-ISI-17, 1-ISI-18, AND 1-ISI-19 "Ultrasonic Testing of Reactor Vessel Welds during Pre-Service and Inservice Examinations," dated June 1981 was issued.
The Pre-Service Examination was performed prior to issuance of this regulatory guide.
As a result, the limitation of each component was recorded by the obstruction, and no coverage estimates of the volume were calculated.
As a result, a direct comparison of the extent of coverage cannot be accurately determined.
The 2005 Inservice Inspection was performed to Appendix VIII qualified PDI guidelines which utilize qualified personnel and techniques as required by 10 CFR 50.55a and Section XI.
A listing of the reported coverage and limitations for the inservice inspection and limitations for the pre-service inspection is included in Attachment 2.
RELIEF REQUEST 1-ISI-19:
NRC QUESTION 7 Provide details showing ultrasonic beam angles used to find the two code allowable indications in weld-18 and the coverage obtained in the area of the flaws.
Also, provide details showing the ultrasonic beam angles for any additional interrogation of these two code allowable indications in weld-18 and any additional coverage obtained in the area of the flaws.
TVA RESPONSE The nozzle to vessel welds were examined with vendor PDI qualified procedures, and were scanned from the inside surface of the vessel and from the nozzle inside surface.
The following information (listed in the vendor's final report) is described below.
- Nozzle to vessel weld from the inside surface of the vessel.
The inner 3.25 inches including the weld metal and adjacent metal for 1/2-inch beyond the weld fusion line'was scanned with a module designed to generate 50 and 70 degree shear and longitudinal waves.
The weld metal and adjacent material in the outer volume beyond 3.25 inches was scanned with a module to generate 45 and 55 degree shear wave search units.
E-4
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 REQUEST FOR RELIEF 1-ISI-16, l-ISI-17, I-ISI-18, AND l-ISI-19
In order to achieve coverage through the examination volume, the nozzle to shell welds were examined from the nozzle bore using longitudinal wave beam angles ranging from 5 degrees to 40 degrees and shear wave beam angles from 35 degrees to 45 degrees.
The indications were located in the outer 85 percent of the vessel and were ultrasonically detected from the inside diameter of the nozzle bore using the phased array technique.
The indications were subsequently sized using the vendor's PDI qualified phased array sizing procedure.
A nozzle sketch from the vendor examination report, which shows the beam angles utilized for the outlet nozzle to vessel scan is included in Attachment 3.
This sketch identifies the transducer and scan direction performed during the inspection.
NRC QUESTION 8 Compare the two code allowable indications with the results of any previous examinations for weld-18 and discuss the results of the comparison.
TVA RESPONSE As discussed in Question 7 above, the two code allowable indications were detected from the inside bore surface of the nozzle with a qualified vendor procedure using a Phased Array technique.
During the pre-service examination, there were no flaws detected.
The examination was performed utilizing 10, 15, and 45 degree refracted longitudinal waves, and 41.5, 45, and 60 degree shear waves in accordance with ASME Section V and ASME Section XI.
The two code allowable indications were detected and sized using a PDI qualified technique, which was not available at the time of the pre-service inspection.
E-5
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 REQUEST FOR RELIEF I-ISI-16, 1-ISI-17, I-ISI-18, AND 1-ISI-19 NRC QUESTION 9 Describe the outlet nozzle integral extension and how it restricts the ultrasonic search unit scan surface, thereby limiting the two-direction transverse coverage.
TVA RESPONSE The sketch referenced in Question 7, (Attachment 3),
shows a basic outline of the integral extension of the outlet nozzle.
As seen in the sketch, the outlet nozzle extension extends outward from the inside surface of the nozzle.
The height and radius of this design prevents the transducers from mating to the surface, thereby, preventing sound from passing from the transducer to the inside surface of the reactor vessel.
E-6
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 REQUEST FOR RELIEF 1-ISI-16, 1-ISI-17, I-ISI-18, AND I-ISI-19 EXAMINERS CERTIFICATIONS
A*A7 Sonic Systems International Sonic Systems Visual AcUity Examination Record for Jason Polisensky 0009666 This vision acuity examination is in compliance with ANSI N45.2.6, NOA-1. ASNT SNTf-TC.1A. ANSIIASNT CP-1159. and ASME Section XI 1992 with 1992 addenda and Later editions.
SSf Visual Acuity Examination Procedure No.
SSI-A-020 Rev. 02 Far Distance Acuity:
Far Vision Snellen Test Natural
ý- Right2O/20
- Corrected 2 Left 20/20 e Both 20120 Near Distance Acuity:
Near Vision ASME X1 Test Card Natural
[ty Right J1-20/25 W. Left J1-20/25 Corrected i Both JI-20/25 Color Contrast Acuity:
f;: Normal Abnormal For employment, Individuals having a color perception deficiency, shall be considered
'normal', where discrimination of color contrast or the primary colors can be demonstrated to the examiner.
Comments:
Vision acuity examination given by a WGI Level I1l. Documentation on file.
Eye Test Date 8.124'/2004 81/24/2003 Eye Test Lxpirafibn Date AdministeredIlyjtýj,,ý Sephew.
d8d Stephen K. Hubbard Level Ill 8/2417004 Date 8,12412004 Date J Michael Robbins WGI Level III
Sonic Systems International Page Iof I 1Sonic Systems Certificate of Qualification jb r Jason Polisensky 0009666 This individual is certified in accordance with Sonic Systems International Inc.'s Nondestructive Examination Qualification and Certification Program. which Is in compliance with the applicable portions of ASNT SNT-TC-1A. CP-189 and ASME Section Xt.
$SI NDE Certification Procedure(s) No.
SSI-A-005 Rev. 20 ICN 01 for MT. PT & VT1,2.3: SSI-A-013 Rev. 1 for UT CERTIFICATIONS Method Level Certification Date Recertificatlon Date Expiration Date Liquid Penetrant II 1/14/2004 NIA 1/12/2007 Magnetic Particle
/II 114/2004 NIA 1/12/2007 Ultrasonic Il-PoI 1/13/2004 N/A 1/13/2007 Visual VT-i II 1114/2004 N/A 1/12/2007 Visual VT-2 I1 1/14/2004 N/A 1/12/2007 Visual VT-3 11 1/14/2004 NIA 1/12/2007 Limitations:
None.
Test Techniques: MT: Indirect; PT: Color Contrast and Flourescent, Solvent Removable and Water Washable: UT:
Contact:
VT-I: VT.
2: VT-3, Direct and Remole.
EYE EXAMS Not valid vithoul current eye exam attached.
ADDITIONAL CERTIFICATIONS I QUALIFICATIONS Appendix VIII POI Qualified for Detection In Fedlic and Austenitic with IGSCC-Expires - Exp Date 10/24/2007 Appendix VIII POI Qualified for Length Sizing for Ferdlic and Austenitic with IGSCC. Expires. 10/24/2007 4
'ri.,
Slej~he K, Ilubbard, PrincilpaI Level If/
DWIi
N 1,
AlQualification and Certification Summary U
WSonic Systems Inteinational Name:
Jason Poliseusky Badge: 0009666 CURRENT CERTIFICATION EXAMINATIONS METHOD LEVEL GENERAL/BASIC SPEC./METHOO PRACT./SPEC.
COMPOSITE EXAMINER SCORE WT SCORE WT SCORE WT SCORE AE ET MT II 92.5 0.333 100 0.333 100 0.333 97.4 Stephen.K. Hubbard PT If 95 0,333 90 0.333 100 0.333 94.9 Stephen K. Hubbard RT UT I[.POI 81.6 0,333 100 0.333 60 0.333 87.1 S.K. Hubbard & EPRI POI VT VT-1 II 81.7 0.333 93 0.333 100 0.333 91.5 Stephen K. Hubbard VT.2 II 81.7 0.333 93 0.333 100 0.333 91.5 Stephen K. Hubbard VT-3 II 81.7 0.333 93 0.333 100 0.333 91.5 Stephen K. Hubbard EDUCATION Diploma-Union-Endicotl High School-Endicott, NY. 1990 TRAINING CLS
.AB 28 12 4
80 15 36 4
12
'24 141
.25 Hours - Magnetic Particle. Ocean Corp.
Hours. Liquid Pcnetrant. Ocean Corp.
Hours o Liquid Penetrant, SSI Hours - Ultrasonic, Ocean Corp.
Hours - PDI. EPRI Hours - Smart 2000. GE Nuclear Hours - VT-1.2.3 (ISI), Hellier Hours - VT1.2.3. SSI EXPERIENCE Initial Method Certificatfon Date mg
)
PT RT LIT vT-i V1T-VT3 21111 992 v/111992 112/l1/1992 119/23/1998 19/23/1998 19/23/1998 The ubove individual meets or exceedsr the certlifcanon requiremcnt.1 as specified in Sonic System Interiwijonal. Inc. s Qualificalion Progeram.
V 1-L-41-14il n(,
,I A IAS Individual Experience summary Record Sonic Systems International Documented records are maintained on rite and meet at least the minimum Sonic Systems International File Date requirements for each certificalion discipline. These and additional records (when referenced) provide objective evidence supporting Qualification and Certification.
Name: Jason Polisensky Badge: 0009666 Prior Certification:
Raytheon Level I1 VT, PT Level I MT Longview Level II UT. PT DNV-1 997 GE UT Level II LMTLevel II PT, MT. UT Documented Experience AE eT '"MT PT RT UT Vr VT-1 VT-2 Vr-3 Date Company Level II I
II-PDI il I.
1 I
02/92 to 1'2J97 GE I I 0
0 0
0 0
4231 0
0 0
0 01/98 to 03198 Longview II 0
0 0
100 0
300
.0
'0 0
0 03/98 to 04/00 Raytheon TRN 0
0 0
0 0
0 0
837 372 372 03/98 to 04/00 Raytheon II 0
0 620 695 0
892 0
0 0
0 09/00 to 10/00 LMT II 0
0 113 100 0
79 0
0 0
0 10/01 to 04104 SSI II 0
0 424 333 0
944 110 168 165 169 Total Experience 0
0 1157 1228 0
6446 110 1005 537 541
.-Y supporting documented records have been reviewed and are true and correct to the best of my knowledge.
gep~en K. Hubbard. Principal Level I/i a
VY TJf Sonic SyStems International, Inc.
AV'LA A
The Nude"r Refueilre and Inpeaion Spedcl~ru 1880 Dairy Ashford Suite 207 1 lousion. Texas 7 7077 (28))531-7611 ASME XI Appendix VIII.
Hands-on-Practice (8 Hours)
Documentation Candidate Name: Jason Polisensky Date: October 24, 2004 SS# / ID#: 0009666 Mr. Polisensky successfully completed qualification for Detection and Length Sizing for Feritic and Austenitic, PDI-UT-I and PD[-UT-2 with IGSCC at the EPRI NDE Center on October 24, 2004.
Due Date: May 24, 2005 Verified by: ___
Level: "
eIII
C.
S.. ".;.
Topics Covered:
A. Review of ASME B. Review of ASME C. Feasibility of Lllt Sa.
Prese
- D ttsApril 22, 4' 4.......'..".
Pi ping W.ld s PD"
:a.
T" iiss orr
""'*,;i',*
E. Revsiewa Met'alM
- a. PDI Preset Name
~....,,,.
-.4..DIPr e
ssroom Time 10 ho, NDE Instructor Washington ASME Section X, Appendix VII Annual Training Section XI, Appendix VII, 1995 Edition Section XI, Appendix VIII Supplement Identification asonic Examination of Dissimilar Metal Welds ntation by Carl Latiolais & Jeff Landrum, EPRI NDE Centcr 002 Dissimilar Metal Weld Program ntation by Carl Latiolais, EPRI NDE Center, April 12, 2002 Melds - Program Issues atation by Carl Latiolais, EPRI NDE Centcr, December 17.
edure for the Ultrasonic Examination of Dissimilar Metal
-UT-10, Rev. A 12120/2002 dure has been qualified at the EPRI NDE Center
/
Date
/
A~~/ A~4~2~
SSonic Systems International, Inc.
AVA,&W The Nucltar Refuel*ng and tpidloCn Spedaliiu 1880 Mairy Ash ford Suitc 207 Houston. Texas 77077 (281) 531-761t ASME X1 Appendix VII Annual Training (10 Hours)
Documentation Candidate Name: Jason Polisensky Completion Date: 08/25/2004 1D#: 0009666 Mr. Polisensky received 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> of Annual Training.from the Washington Group on August 25, 2004. 1 have reviewed the documentation signed by a Washington Group Level IlI Instructor. I accept this training as meets the Annual Training requirements outlined in SSI-A-013 Rev. 02.
Retraining due date: 08/25/2005 Stehe i~u, bh a rrd Lccvc1 If I1/ 1 n s t r uuc ttoorr Approved:
Performance Demonstration Initiative Program In Accordance with the PDI Implementation of Section XI, Appendix VIII IGSCC Requalification Signature Sheet Candidate: Polisensky Jason Original Procedure: PDI-UT-2 vBaO (Limitations and Comments listed on original PDQS still apply)
Car L. Laiots Performance Demonstration Initative Piping and Bolting Supervisor/Level HI Date_91
_ 8._ooq Date 7/
F. L?.
B ec k e -
Performance Demonstration Initative Administrator Page 2 of 2 Page 2 of 2This docurnni is not~ *uthentic '&h~'.t 3 raised seal
Performance Demonstration Initiative Program In Accordance with the PDI Implementation of Section )U, Appendix VIII IGSCC Requalification Summary Sheet Candidate: Polisensky Jason Original Procedure: PDI-UT-2 vBaO (Limitations and Comments listed on original PDQS still apply)
Revision it Addenda Requal Date 07/05/2004 07/05/2004
.ippcing Mau Piping Manual Piping Manual
- E.x~am.Ty._c Detection Detection Single Dual C
0 Page I of 2
I..
.. *.~
~
~
Performance Demonstration Initiative Program In Accord-ance with the PDI Iniplementalion of Section X1, Appendix VI[l Specific Detail of Quailfications Printed:
17.*%ov.04 t'flQS:1o':
448 04061 103 Candidate: Jason Polisensky ID#:
Procedure: PDI-UT-2; Revision: C; Addenda: 0 PDI Generic "Procedure for the Ultrasonic Examination of Austenitik Pipe Welds rplQs Ret:
o onner:
Ptrfrnwiuce D~imnrinsration Initiative ItArdwvare:
NI~A Catrrjry:
Piping D21C nt Issue:
Analysis SW Trpeilttv.
Operator SW"ITvpcl1rTe:
SScan Application:
17-Nov-04 MA N/A Manual The above candidate has met the requirentents of The Performance Demonstration Initiative's Implementation of The American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Appendix VIII, as stated in this document.
Carl L La--totals Performance Demonstration Inittifive Piping and Bolting Supervisor/Let'el Ill F. L Becker Performance Demonstration Initiative Administrator Date:
D ateC:
TIhis docturnent is sni autthemi ivthout a rofsntj set.L
Performance Demonstration Initiative Program In Accordance iAith the PDI Implementation of Section Xl, Appendix VIf Specific Detail of Qualifications Printed 03-Dec-04 PDQS No:
445 04061103 Candidate: Jason Polisensky ID#:-
Procedure: PDI-UT-2; Revision: C; Addenda: 0 PDI Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds.
PDQS Rev:
0 Owner:
Performance Demonstration Initiative llardware:
NA Category:
Piping Date of Issue:
17-Nov-04 Analysis SW Type/Rev:
NIA Operator SW Type/Rev: NIA Sean Application:
.fsnual When "Length Sizing' is indicated. the 0.750 RMS acceptance criteria per the PD1 Program Description has been achieved.
When 'Through Will Sizing" is indicated, the 0.125 RMS acceptance criteria per the PDI Program Description has been achieved.
Tolerancea for field applications as follows:
Diameter:
Lower:.500" can be subracted from the minimum diameter demonstrated.
Upper: Diameters greater than 24' need not be demonstrated.
Thickness:
Lower: 0.100" can be subtracted from the minimum thickness demonstrated for both austcnitic and ferritic Upper: 1.000" can be added to the maximum thickness demonstrated for ferrilic material.
0.500" can be added to the maximum thickness demonstrated for austenilic material.
This candidate has met the practical requirements orAppcndix VII. Yes Comments:
Limliatlons: I This proeedurccandidate is not qualificd to detect axially orientated flaws located on the far side of the weld %here access is limited to cnc side and the ultrasonic bcam is required to propagate through austenitic weld material.
Z The austenitic single side qualifriclions. documented on this summary. demonstrate application of best available technology. but do nut meet the requirements of IOCFR 50,.SaibX2) (xvi) 11).
PFar 2 of 3
Performance Demonstration Initiative Program In Accnrdatcc wid the PD1 Implementation of Sectlon XI. Appendix VIII Specific Detsil of Qu12ificationf Po~inted:
VT-0ar-Pr~
n 4
04061 101 Candidate: Jason Polisensky ID#: -mm-Procedure: PD1-UT-2; Revision: C; Addenda: 0 PD! Generic Procedure for the Ultrasonic Examination of Austenitic Pipe Welds PO)QS Rev.
iV OwneCr:
Pe-'snu'-ce Demniostntivit n ii sA.s4 llardAre-:
NcA Cate.-ory:
pipauv Date oft Istuit Anzlysis SW Typellli':
OperiatrSAV Type/lr:v Scott Applicition:
I 7-Nuv-(44 Ran.es Demonstrated:
Dowe.
25-Oct-04 7M1nDiomu
- 2.000 NMlnThlcL-0.737 hf2XD12M:
36.000
!slaxThicL-2.900 h.
M'.tterial:
Austenoke wi~th lGSCC Extmirstrion:
Detection Access-D nulle Sided Weld Cand:
Grwndi Flush Weld Cond:
Flat Top Weld Cond.
As %Vcfdcd MCces:
Singi.- Sided WeVld Coat!:
Gwwousd Flush Weld Coond:
Fist Top Weld Cant!:
As Welded Pag2. 1.1 3
Performance Demonstration Initiative Program In Accordance with the PD Inmplementation of Section0 X, Appendix V111 Specific Detnil of Qualificatious I'rintrtl:
1l.NOV-04 rD)QS KO:
449 0.106110.1 Candidate: Jason Polisensky ID#:.
~-
Procedure: PDI-UT-1; Revision: C; Addenda: 0 PDI Generic Procedure for the Ultrasonic Examination of Ferritic Pipe Welds 11)Q! Re':
0 Owntr '
Pcorlrmroicc tkmnwn-tiun loillmnve Ilard%%zre*
MA CwTe'ury:
Pipuaig Date of Twit:
Anastysis SW TypclRev:
Optrstor SW Typr(Rev:
Scan Application:
17-Now-04 N/A
'NA Manual The above candidate has met the requirements of The Performance Demonstration Initiative's Implementation of The American Society of Mech2nical Engineers Boiler and Pressure Vessel Code, Section XT, Appendix VIII, as stated in this document.
Cart L. Latiolais Perfornance Demonstration Inltiatlvt Piping and Bolting SupervisorfLevel III F. L. Hecker Performxnce Oemonvir2tion Initiative Administrator Dafte:
/7 Date:/':
~7 This documnent Is not suth..ntic olihast 2 T~iCt MOa.
Fare. 3ut 3
Performance Demonstration Initiative Program In Accordance witin ate PD' iniplementatiol, of Section XT. Appendix VIll
.Specific Detail of Qualifications-1'DQS No:
44 04061103 Candidate: Jason Polisensky IM#:
Procedure: PDI-UT-I; Revision: C; Addenda: 0 PD1 Generic Procedure for the Ultrasonic Examination of Ferritic Pipe Welds P)QS Rev:
0 Owner:
Vcertoamnace flervamrrion initiative Hardware:
'WVA Date orss~ut:
An. lySIS SW~lp-H Operator SNS TypdJllt%
Sran Arp~licaionz.
?.tunu~al
- When 'Lcnpth Sizrnt' is in dicated: thtcO.7ý0 PUMS actcptaflcc criteria pci the PD1 f'rvypin Dicscuipticn has ken 2chieved.
When 'T1vugeh Wall Sizing' is indicated. the 0.123 RtMS itccertance criteria pci the PDI Prorrairi Decripfson has teen :tchtcvd.
Tolerances for field 2pplieatioacs as rollows:
Diamerter:
- Loemer:.500" can be subracted fonha~vda~wdmosrrd
- Upper: Dimrietas zirairr than 24' need nlot be d'mfxtstrated.
Thickriess:
Lo%%vr-0.l0O* can be subtracted ftomn the minimum titickniess demanstrated fer both austenitic and fceizitc Utpper 1000'r cant be added to the rna'cinum ulridcncs deinonstrxcil fix furitic mairdial.
0.500" can (m added to the,ntm.'rrnrs thick-nets demionstrated rLve mus.1-itic retriarr21.
This candidate has rnt thec practice! requirenments cfAppcndix ViI:
NO Ctimmeirs:
1intitations.:
I Tliis pnmcedure-vandidite i% emlyqu~aifivt ticn lntit si 7e Ilar%"
m'ictalcd in the c itctiinrltec1t1131 d~ccti on.
PIme 2 of 3
Performance Demonstration Initiative Program In Accordance with the PDI Imnplementation ofSection XI, Appendix VIII Specific Detail of Qualiflications
,IflQS -Nc:O
.448 0406'. I Candidate: Jason Polisensky ID#:
Procedure: PD[-UT-1; Revision: C; Addenda: 0 PDT Generic Procedure for the Ultrasonic Examination of Ferritic Pipe Wehlds MDQS Re':
0 Oateet" itue:
17-.NOv-sb1 Owner:
P'roibirncuc cmnm's:-ritio finitiati*c Au3lysh.SW TyptiRev:
N!A Hardware:
'.A OprrnorSW TyprlRnt:
N,"A Colt-gor :
Pipinig Scan Ap*laieation:
MallU21 Ranges Demonstrated:
Date:
25-M-t-04
>tinDians:
4.00M MInThillu 0.337
.NlzxDiarf:
50.000 Maxihick:
3850 E~xamination:
Deiection Aceestu Double Sided Wtld Cond:
Ground Flush Weld Cond:
Flit Top Weld cond.
As Wtided Access:
SinelcSkkde Weld Cood:
Ground Flush Weld Cond:
PatslTop Weld Cond:
As Welded Pa.*r I of.
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 REQUEST FOR RELIEF I-ISI-16, 1-ISI-17, I-ISI-18, AND I-ISI-19 LIST OF LIMITATIONS
WBN RAI QUESTION #6 PRE-SERVICE VS ISI RPV EXAMINATIONS COVERAGE OF REQUESTED WELDS ISI Weld # % Coverage Restrictions listed In ISI Report
% Coverage Restrictions listed in Pre-Service Report No Examinations from the cap side due to W01-02 60%
Limited to bottom head penetrations None Performed instrumentation tue interference Limited due to proximity of core barrel Limited Examination due to core support lug W02-03 72%
stabilizing lugs None Performed interference.
Limited due to the bottom head penetrations and core barrel Limited examination due to core support lug W2A 79%
stabilizing lugs None Performed intereference.
Limited due to the bottom head penetrations and core barrel Limited examination due to core support lug and W2B 84%
stabilizing lugs None Performed instrumenation tube intereference.
Limited due to the bottom head penetrations and core barrel Limited examination due to core support. lug and W2C 85%
stabilizing lugs None Performed instrumenatlon tube intereference.
Limited due to the bottom head penetrations and core barrel Limited Examination due to core support lug W2D 85%
stabilizing lugs None Performed interference.
Limited due to the bottom head penetrations and core barrel Limited examination due to core support lug and W2E 85%
stabilizing lugs None Performed instrumenatton tube intereference."
Limited due to the bottom head penetrations and core barrel Limited examination due to core support lug and W2F 67%
stabilizing lugs None Performed instrumenation tube intereference.
ENCLOSURE WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 REQUEST FOR RELIEF I-ISI-16, 1-ISI-17, 1-ISI-18, AND I-ISI-19 VENDOR'S NOZZLE SKETCH
"jodule Pivot Point 2238 R83.00 From Vessel C.L to CJad of Intogral Extension U'.to Ciad 0
Vt
- 2.
MtPldj Pjot Point 243' Outlet Nou43es N43$ & N-17 O rly t
N lO)
SUC'40 Incident Point
, Modut Pivot Point 3136 S, It I.
Note: Check for tImitatlris due to the proximity of shell wtll taper and Integral extension.