ML060870447
| ML060870447 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/15/2006 |
| From: | Brandi Hamilton Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2006-ON-001 | |
| Download: ML060870447 (32) | |
Text
BRUCE H HAMILTON M k Vice President f-Stw ere Oconee Nuclear Station Duke Power ON0I VP / 7800 Rocherster Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax March 15, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Duke Energy Corporation Oconee Nuclear Station, Units 1, 2, and 3 Docket Nos. 50-269, -270, -287 Request for Relief No. 2006-ON-001, Revision 1 By letter dated February 2, 2006, Duke Energy (Duke) submitted Request for Relief No. 2006-ON-001 pursuant to 10 CFR 50.55a(a)(3)(i). That request addressed Duke's plan to replace all Pressurizer level tap and sample tap nozzle safe ends composed of Alloy 600 at Oconee Nuclear Station (ONS),
Units 1,- 2, and 3. Duke requested an alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, NB-5222(a), requiring that Code Class 1 weld joints be examined via radiographic methods to satisfy non-destructive examination requirements.
In the previous request, ASME Section III Code Case N-659-1 was cited and an argument of its ability to provide an acceptable level of quality and safety, in accordance with 10 CFR 50.55a (a)(3)(i), was made. In Revision 1, Duke is modifying the previous request by citing ASME Section III Code Case N-659-0 and making a case for why compliance with the requirements of ASME,Section III, NB-5222(a) would result in hardship or unusual difficulty without a compensating increase in the level.
of quality and safety, in accordance with 10 CFR 50.55a(a)(3)
(ii). Furthermore, Revision 1 provides greater insight into the preliminary coverage attainable by the requested alternative ultrasonic inspection technique. Therefore, Duke hereby submits Request for Relief No. 2006-ON-001, Revision 1, attached, which has been modified to include the improvements mentioned above, as well as the information from Revision 0 that remains unaltered.
A04-7 www.dukepower. corn
U. S. Nuclear Regulatory Commission March 15, 2006 Page 2 Duke plans to replace three ONS Unit 3 level tap nozzle safe ends during the outage scheduled to begin on April 29, 2006.
Duke currently plans to use the proposed alternative during all.
of the ONS replacement work for all Pressurizer level tap and sample tap nozzle safe ends composed of Alloy 600 through the end of 2007.
An expedited approval of the attached Request for Alternative is requested by April 14, 2006 to support planning and preparation activities for the ONS Unit 3 refueling outage that is scheduled to begin on April 29, 2006.
Please refer any questions regarding this submittal to Randy Todd ONS Regulatory Compliance at (864) 885-3418.
Sincerely, Bruce Hamilton, Vice President Oconee Nuclear Site
Enclosures:
- 1. 10 CFR 50.55a Request Number 2006-ON-01
- 2. Framatome Fabrication Drawings
- 4. Flaw Tech Qualification Block Drawings
- 5. Preliminary Coverage Drawings
U. S. Nuclear Regulatory Commission March 15, 2006 Page 3 xc w/att: Mr. William D. Travers Administrator, Region II U.S. Nuclear Regulatory Commission Atlanta Federal Center 61 Forsyth St., SWW, Suite 23T85 Atlanta, GA 30303 L. N. 0ishan, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 xc(w/o attch):
M. C. Shannon Senior NRC Resident Inspector Oconee Nuclear Station Mr. Henry Porter Division of Radioactive Waste Management Bureau of Land and Waste Management SC Dept. of Health & Environmental Control 2600 Bull St.
Columbia, SC 29201
Request No. 2006-ON-01, RevI Enclosure I 10 CFR 50.55a Request Number 2006-ON-01, Revision 1
Request No. 2006-ON-01, RevI Enclosure I Page 1 of 9 10 CFR 50.55a Request Number 2006-ON-01, Revision 1 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(ii)
--Compliance with Requirements Results in Hardship Without a Compensating Increase in Quality and Safety--
Duke Energy Corporation Station Oconee Units 1, 2 & 3 Request for Alternative 2006-ON-01, Revision 1 Pursuant to 10CFR50.55a(a)(3)(ii), Duke Energy Corporation requests to use an alternative to the 1983 Edition of Section III of the ASME Boiler and Pressure Vessel Code. Information is being submitted in support of our determination that compliance with the specified requirements of this code results in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
I. ASME Code Component(s) Affected:
All ASME Section III Code Class 1 Reactor Coolant System butt-welds between the Pressurizer Level and Sample Tap Nozzles and their respective Safe Ends at Oconee Nuclear Station (ONS), Units 1, 2, and 3.
A total of six level taps are being replaced in each unit of ONS (three in the steam space, and three in the water space), as well as one sample tap on each ONS Pressurizer. This amounts to a total of seven replacements per CONS Pressurizer. The existing weld numbers for the ONS Units 1, 2, and 3 level and sample nozzle-to-safe end welds are: 1PZR-WP63-1 through 1PZR-WP63-7, 2PZR-WP63-1 through 2PZR-WP63-7, and 3PZR-WP63-1 through 3PZR-WF'63-7, respectively. These welds are expected to be given new "vendor weld numbers" as they are replaced by the individual modification packages. A copy of the fabrication drawings for the current pressurizer safe end design and installation is located in Enclosure 2.
II. :Applicable Code Edition and Addenda:
ASME Code, Section Xl 1998 Edition, through the 2000 Addenda.
ASME Code,Section III 1983 Edition, with No Addenda.
Request No. 2006-ON-01, Rev1 Enclosure I Page 2 of 9 Ill. Applicable Code Requirements:
The 1998 ASME Code,Section XI, through the 2000 Addenda, IWA-4221 requires that items used for replacement meet the owner's design specification and original construction code for the component. However, it also states that Section IlIl may apply when the Construction Code was not Section IlIl, provided the requirements of IWA-4222 through IWA-4226 are met.
ASME Code, Section IlIl requires that Class 1 weld joints be examined via radiographic methods to satisfy non-destructive examination (NDE) requirements as part of final weld acceptance during construction. For the ASME Code components listed previously, relief is requested from the requirements of 1983 ASME Section Ill paragraph NB-5222(a).
(a) "Butt welded joints shall be examined by the radiographic and either the liquid penetrant or magnetic particle methods."
IV. Reason for Request:
Duke Energy plans to replace all Pressurizer level tap and sample tap nozzle safe ends composed of Alloy 600 with corrosion resistant, low carbon stainless steels. The design of the replacement safe ends and welds are configured to be like those in the original designs.
The 1998 ASME Code, Section Xl, IWA-4221(c), states that Section Ill may apply for items used for replacement provided the requirements of IWA-4222 through IWA-4226 are met. The ASME Code, Section 1I1,NB-5200, "Required Examination of Welds," requires that circumferential welded joints in piping, pumps, and valves be examined using the radiographic (RT) method and either liquid penetrant or magnetic particle examination methods.
The geometry of the Safe End to Nozzle weld joint configuration makes RT very difficult due to the steep thickness taper and small inner diameter of the nozzle (see Enclosure 2). This configuration yields less than desirable RT results for detecting weld metal defects and presents a significant potential for re-examination due to radiographic density variation. Duke Energy believes that the present nozzle to safe end weld geometry does not yield itself to a radiographic technique that produces high confidence that will detect all unacceptable weld metal defects. Duke Energy has determined through radiographic test exposures on a mockup test piece that performing RT on this weld will require a minimum of 34 exposures to obtain full coverage. Due to this number of exposures, it has been determined that approximately 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> is required to perform the RT examination for one weld. Since the performance of RT involves the use of highly penetrating radioactive isotopes, there exists a personnel safety risk of
Request No. 2006-ON-01, RevI Enclosure 1 Page 3 of 9 inadvertent or accidental exposure. Also, outage duration and costs are greatly increased due to the fact that parallel path outage work within the vicinity is not possible during examination of the welds using RT. Duke Energy has evaluated ihe use of an alternative ultrasonic method and determined that its use will provide an acceptable level of confidence for detecting weld metal defects and provides an acceptable level of quality and safety.
In short, compliance with the requirements of ASME,Section III, NB-5222 would result in hardship without a compensating increase in the level of quality and safety.
V. proposed Alternative:
The alternative involves ultrasonic and surface examinations of Class 1 repair replacement welds. The alternative examinations will be made to satisfy the construction code requirement for radiographic examination. This proposed alternative ultrasonic examination will eliminate the hardships associated with performing radiographic examinations, while ensuring an adequate level of safety and quality. The alternative provides adequate verification that the Class 1 welds are free of unacceptable flaws that could affect structural integrity.
Prior to the use of the alternative examination, the effectiveness of the ultrasonic
- techniques will be demonstrated on a qualification block containing a weld with representative flaws.
The proposed alternative method will meet the requirements of ASME Section III Code Case N-659-0, "Use of Ultrasonic Examination in Lieu of Radiography for Weld Examination,Section III, Division 1" (see Enclosure 3), with stated exceptions. Duke's strategy to meet all of the requirements of the code case is discussed below. Where literal compliance may not be met, supplemental actions are specified.
(a) Case Requirement The ultrasonic examination area shall include 100% of the volume of the entire weld, plus 0.5T of each side of the welds, where T is the thickness of the weld. The ultrasonic examination area shall be accessible for angle beam examination in four directions, two directions perpendicular to the weld axis and two directions parallel to the weld axis. Where perpendicular scanning is limited on one side of the weld, a technique using the second leg of the V-path may be credited as access for the second perpendicular examination direction provided that the detection capability of that technique is included in the procedure demonstration described in (c) and (d) below.
Duke Strategy: Duke Energy must take exception to the 100% coverage requirement. At least 95.5% of the volume of the entire weld, plus 0.5T of
Request No. 2006-ON-01, Rev1 Enclosure 1 Page 4 of 9 each side of the weld will be examined during the ultrasonic inspection. The most conservative approach to find 0.5T is to derive the actual weld thickness at each weld edge according to the fabrication drawings found in Enclosure 2.
This results in 0.526" to be examined from the safe-end weld edge and 0.740" to be examined from the nozzle weld edge. When utilizing a full sectc'rial scan from 18° to 78° in conjunction with linear multiple-line scans of 250 and 350, an axial scan in the direction of the nozzle results in 98.82% coverage, and an axial scan in the direction of the safe-end results in 98.49% coverage.
When applying the 10 degree difference between angles as required in (b) below, the coverage of the higher end (780 to 680) of the sectorial scan is reduced, recalculating to 95.54% for an axial scan in the direction of the nozzle, and 97.36% for an axial scan in the direction of the safe-end.
Circumferential scans, which allow closer access to the taper, are predicted to produce coverage percentages that are at least equal to the cited axial percentages. The preliminary coverage drawings located in Enclosure 5 show the minimum anticipated coverage of the weld and base metal for each scanning direction. Further development may be able to produce 100%
coverage in all directions. Axial and circumferential notches are being planed in the qualification block in areas considered most difficult to inspect in order to demonstrate detection capabilities. A surface dye-penetrant examination required by Section III will also be performed in this area, which will, in effect, supplement UT coverage.
i~b) Case Requirement: The ultrasonic examination shall be performed in accordance with Section V, Article 5 up to and including the 2001 Edition. A straight beam and two angle beams having nominal angles of 45 and 60 deg should generally be used; however, other pairs of angle beams may be used provided the measured difference between the angles is at least 10 cleg.
Alternatively, ultrasonic examination may be performed by a procedure qualified in accordance with the performance demonstration methodology of Section Xl, Appendix Vil provided the entire volume of the weld examination is included in the demonstration.
Duke Strategy: The ultrasonic examination will be performed in accordance with ASME Code,Section V, 1998 Edition through the 2000 Addenda, Article 5, using an automated phased array system. The requirements for straight and angle beams, as discussed above, will be met in the phased array process.
'c) Case Requirement: A written procedure shall be followed. The procedure shall be demonstrated to perform acceptably on a qualification block or specimen with both surface and subsurface flaws as described in (d) below.
Duke Strategy: A procedure will be written and performed to demonstrate its success on the qualification block described in (d).
Request No. 2006-ON-01, RevI Enclosure 1 Page 5 of 9 (d) Case Requirement: The qualification block material shall conform to the requirements applicable to the calibration block. The material from which blocks are fabricated shall be one of the following: a nozzle dropout from the component; a component prolongation; or material of the same material specification, product form, and heat treatment condition as one of the materials joined. For piping, if material of the same product form and specification is not available, material of similar chemical analysis, tensile properties, and metallurgical structure may be used. Where two or more base material thicknesses are involved, the calibration block thickness shall be of a size sufficient to contain the entire examination path. The qualification block configuration shall contain a weld representative of the joint to be examined, including, for austenitic materials, the same welding process. The qualification blocks shall include at least two planar flaws in the weld, one surface and one subsurface oriented parallel to the fusion line, no larger in the through-wall direction than the diameter of the applicable side-drilled hole in the calibration block shown in Fig. T-542.2.1 of Section V, Article 5, and no longer than the shortest unacceptable elongated discontinuity length listed in NB-5330, NC-5330, or ND-5330 for the thickness of the weld being examined. Where a Section Xl, Appendix VilI, performance demonstration methodology is used, supplemental qualification to a previously approved procedure may be demonstrated through the use of a blind test with appropriate specimens that contain a minimum of three different construction-type and fabrication-type flaws distributed throughout the thickness of the specimen.
Duke Strategy. A calibration block will be made to meet the requirements of ASME Section V, Article 5, and the thickness will be of a size sufficient to contain the entire examination path. The qualification block (See Enclosure 4), conforms to the requirements applicable to the calibration block, as well as to all material and weld requirements discussed above. The qualification block materials are composed of the same material specifications, product forms, and heat treatment conditions as the actual components being welded. Additionally, the weld of the qualification block is formed by the same welding process as will be performed in the field. The qualification block includes one surface crack and two subsurface lack of side-wall fusion flaws oriented parallel to the fusion line with dimensions meeting the specifications of ASME Code,Section V, 1998 edition, through the 2000 Addenda, Article 5, and ASME Code, Section 1II, 1983 edition, NB-5330.
Axial and circumferential notches (Enclosure 4, Notches 4 and 5, respectively) are also being placed in the qualification block in areas considered most difficult to inspect in order to demonstrate detection capabilities.
(e) Case Requirement: This Case shall not be applied to weld examination volumes that include cast products forms or corrosion-resistant-clad austenitic piping butt welds.
Request No. 2006-ON-01, Revl Enclosure 1 Page 6 of 9 Duke Strategy: The welds being examined do not include cast product forms or corrosion-resistant-clad austenitic piping butt welds.
(f) Case Requirement: A documented examination plan shall be provided showing the transducer placement, movement and component coverage that provides a standardized and repeatable methodology for weld acceptance.
The examination plan shall also include ultrasonic beam angle used, beam directions with respect to weld centerline, and volume examined for each weld.
Duke Strategy. A conservative preliminary coverage drawing, utilizing a full sectorial scan from 180 to 780 in conjunction with linear multiple-line scans of 250 and 350, is located in Enclosure 5. Various scan techniques that employ full use of steering, sweeping, and skewing shall be applied. A final documented examination plan containing the information requested above is being prepared and will be available on site for review upon request of the ANII and/or NRC inspectors prior to use.
(g) Case Requirement: The evaluation and acceptance criteria shall be in accordance with NB-5330, NC-5330, or ND-5330, as acceptable.
Duke Strategy: The evaluation and acceptance criteria will be in accordance with NB-5330. Additionally, any flaws characterized as surface-connected cracks, lack of fusion, or lack of penetration may be evaluated by a supplemental penetrant examination performed in accordance with NB-5000.
(h) Case Requirement: For welds subject to inservice ultrasonic examination, the examination and evaluation shall also meet the requirements of the applicable Edition of Section Xl for preservice examination.
Duke Strategy: These welds are exempt from Section Xl volumetric pre-service and in-service examinations due to their size.
(i) Case Requirement: The ultrasonic examination shall be performed using a device with an automated computer data acquisition system.
Duke Strategy: The UT examination will be performed using a device with an automated computer data acquisition system.
'j) Case Requirement: Data shall be recorded in unprocessed form. A complete data set with no gating, filtering, or thresholding for response from examination volume in (a) shall be included in the data record.
Duke Strategy: Data will be recorded in its raw form and fully documented when creating data records.
{k) Case Requirement: Personnel who acquire and analyze UT data shall be qualified and trained using the same type of equipments in (i), and
Request No. 2006-ON-01, RevI Enclosure I Page 7 of 9 demonstrate their capability to detect and characterize the flaws using the procedure as described in (c).
Duke Strategy: UT Level 11and Level III examiners will acquire the UT data, and a UT Level Ill will analyze the data. The capabilities of all participants to detect and characterize the flaws using the procedure will be demonstrated to the Authorized Nuclear Inservice Inspector prior to inspection.
(I) Case Requirement: Review and acceptance of the procedure by the Authorized Nuclear Inspector is required.
Duke Strategy: Review and acceptance of the procedure by the Authorized Nuclear Inservice Inspector will be achieved prior to beginning inspections.
(m)Case Requirement. All other related requirements of the applicable subsection shall be met.
Duke Strategy: Related requirements of the applicable subsection will be met.
'n) Case Requirement: Flaws exceeding the acceptance criteria referenced in this Case shall be repaired, and the weld subsequently reexamined using the same ultrasonic examination procedure that detected the flaw.
Duke Strategy: Flaws exceeding the acceptance criteria will be repaired and reexamined using the same ultrasonic examination procedure.
o) Case Requirement: This Case number shall be recorded on the Data Report.
Duke Strategy: The Data Report will reference Code Case N-659-0.
VI. -Justification for Granting of Alternative:
As discussed previously, the requirement specified in ASME Section III, t:hat circumferential welded joints in piping, pumps, and valves be examined using RT, results in a significant hardship without a compensating increase in the level of quality and safety.
Based on the review of the joint configuration of the planned welds it has been determined that performing RT would be a very difficult task, requiring a iminimum of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> for 34 shots per weld without a high confidence level that the weld geometry will yield itself to a RT technique that would detect all unacceptable weld metal defects. Since the performance of RT involves the use of highly penetrating radioactive isotopes, using a qualified UT method will eliminate the associated personnel safety risks and the normal anticipated exposure to the background radiation levels. Also, outage duration and costs will
Request No. 2006-ON-01, RevI Enclosure 1 Page 8 of 9 be reduced by allowing parallel path outage work to progress uninterrupted during examination of the welds.
Furthermore, given their intended use as described in this alternative request, qualified ultrasonic methods are an acceptable substitute for radiography. By meeting requirements of ASME Section III, Code Case N-659-0, assurance is provided that flaws will be detected.
A qualified UT method meeting requirements of ASME Section 11I, Code Case N-G359-0 would, while avoiding the hardships associated with RT, provide adequate results compared to the RT method. NRC staff approval is requested in accordance with 10 CFR 50.55a(a)(3)(ii).
VII. Duration of Proposed Alternative:
This relief will be implemented during the next scheduled refueling outages for each of the three Oconee Units. Duke currently plans to replace three ONS Unit 3 level tap nozzle safe ends during the outage scheduled for April 2006. In October of 2006, Duke plans to replace all seven ONS Unit 1 level and sample tap nozzle safe ends. Replacement of the seven level and sample taps for ONS Unit 2 is expected to occur during the Spring of 2007 outage. In October of 2007, Duke plans to replace the remaining level and sample taps for ONS Unit 3.
The expected date for completion of all of the pressurizer level and sample tap replacements is by the end of 2007.
An expedited NRC staff approval is requested by April 14, 2006 to support planning and preparation activities for the ONS Unit 3 refueling outage that is scheduled to begin on April 29, 2006.
Vil. Precedents This proposed alternative is similar, but not identical, to a relief request submitted by Union Electric Company's Callaway Plant in a letter dated November 18, 2004 (i.e. ADAMS Accession Number ML043450359), as approved by NRC letter dated May 19, 2005 (i.e. ADAMS Accession Number ML050760129).
This proposed alternative is similar, but not identical, to a relief request submitted by Progress Energy Corporation's Brunswick Plant in a letter dated August 9, 2005 (i.e. ADAMS Accession Number ML052280213).
Request No. 2006-ON-01, RevI Enclosure I Page 9 of 9 IX.
References:
- 1. Title 10 of the Code of Federal Regulations, Part 50, Section 55a, Codes and Standards (i.e., 10 CFR 50.55a)
- 2. ASME Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1998 Edition, through the 2000 Addenda
- 3. ASME Code, Section 1II, "Rules for Construction of Nuclear Power Plant components," 1983 Edition, with no addenda
- 4. ASME Code, Section 1I1,Code Case N-659-0, "Use of Ultrasonic Examination in Lieu of Radiography for Weld Examination Section 1II,Division 1." September 17,
'002
- 5. EPRI Technical Report 1003545, "Alternative Volumetric Examination Methods:
UT in Lieu of RT for Repair/Replacement Activity," December 2002
- 6. NRC "Safety Evaluation by the Office of Nuclear Reactor Regulation, Second Ten-year Interval Inservice Inspection Program Plan, Request for Relief to use an Alternative Examination Method, Union Electric Company, Callaway Plant, Unit 1, Docket No. 50-483." ML050760129, 05-19-2005
- 7. Progress Energy. "Brunswick, Units 1 & 2, Relief Request RR-36, Use of Ultrasonic Examinations in Lieu of Radiographic Non-Destructive Examinations."
ML052280213, 08-09-2005
- 8. Union Electric Co. "Callaway, Unit 1, Request for Relief from ASME Section III Requirements Regarding Non-Destructive Examination of Welds Performed Under Site Repair/Replacement Program." ML043450359, 11-18-2004 Prepared By: Date: 3lJJ5JouQ ahel oss NDE Level III Review B Date: 3//5/d_
Reviewed By: ____________ Date: 3 J31Ob David W. Peltola
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Request No. 2006-ON-01, RevI Enclosure 3 ASME Section III Code Case N-659-0
Request No. 2006-ON-01, Revl Enclosure 3 Page 1 of 2 CASE N-659 CASES OF ASMEB: It()LER ANt) P'RISSUR; VE SSt:l. CODE Approval Date: September 17, 2002 See Numeric Index for expiration and any reaffirmation dates.
Case N-659 The material from which blocks are fabricated shall use or Ultrasonic lxaminiation in Lieui of be one of the following: a nozzle dropout from the Radiographiv for Weld Examination component: a component prolongation: or material of Set1io I. D)ivision I the same material specification, product form, and heat treatment condition as one of the materials joined. For Inquiry: Under what conditions and limitations may piping, if material of the same product fcrm and an ultrasonic examination be used in lieu of radiography specification is not available, material of similar chemi-where radiography is required by NB-5200. NC-5200, cal analysis, tensile properties, and metallurgical strus-ND-5200 and substitution of ultrasonic examination ture may be used. Where two or more base material would not otherwise be permitted? thicknesses are involved. the calibration block thickness shall be of a size sufficient to contain the entire Reply: It is the opinion of the Committee that all examination path. lThe qualification block configuration welds in material 1/2in. or greater in thickness may shall contain a weld representative of the joint to be be examined using the ultrasonic (UT) method in lieu examined. including, for austenitic materials, the same of the radiographic (RT) method, provided that all of welding process. The qualification blocks shall include the following requirements are met: at least two planar flaws in the weld, one surnace and (a) The ultrasonic examination area shall include one subsurface oriented parallel to the fusion line, no 100% of the volume of the entire weld, plus O.5T of larger in the through--wall direction than the diameter each side of the welds, where T is the thickness of of the applicable side-drilled hole in the calibration the weld. The ultrasonic examination area shall be block shown in Fig. T-542.2.1 of Section V, Article accessible for angle beam examination in four directions. 5, and no longer than the shortest unacceptable elongated two directions perpendicular to the weld axis and two discontinuity length listed in NB-5330, NC-5330, or directions parallel to the weld axis. Where perpendicular ND-5330 for the thickness of the wveld being examined.
scanning is limited on one side of the weld, a technique Where a Scetion Xl, Appendix Vill. performance dem-using the second leg of the V-path may be credited onstration methodology is used, supplemental qualifica-as access for the second perpendicular examination tion to a previously approved procedure may be demon-direction provided that the detection capability of that strated through the use of a blind test with appropriate technique is included in the procedure demonstration specimens that contain a minimum of three different described in (c) and (d) below. construction-type and fabrication-type flaws distributed (b) The ultrasonic examination shall be performed throughout the thickness of the specimen.
in accordance with Section V, Article 5 up to and (e) This Case shall not be applied to weld examina-including the 2001 Edition. A straight beam and two tion volumes that include cast products forms or corro-angle beams having nominal angles of 45 and 60 deg sion-resistant-clad austenitic piping butt welds.
should generally be used; however, other pairs of angle WJ) A documented examination plan shall be provided beams may be used provided the measured difference showing the transducer placement, movement and com-between the angles is at least 10 deg. Alternatively, ponent coverage that provides a standardized an i rcpeat-ultrasonic examination may be performed by a procedure able methodology for weld acceptance. The examnination qualified in accordance with the performance demonstra- plan shall also include ultrasonic beam angle used.
tion methodology of Section Xl, Appendix Vil provided beam directions with respect to weld centerline, and the entire volume of the weld examination is included volume examined for each weld.
in the demonstration. (g) The evaluation and acceptance criteria shall be (c) A written procedure shall be followed. The proce- in accordance with NB-5330, NC-5330, or ND-5330, dure shall be demonstrated to perform acceptably on as acceptable.
a qualification block or specimen with both surface (Ih) For welds subject to inservice ultrasonic cxamina-and subsurface flaws as described in (d) below. tion, the examination and evaluation shall also meet (d) The qualification block material shall conform the requirements of the applicable Edition of Section to the requiremits applicable to the calibration block. Xl for preservice examination.
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Request No. 2006-ON-01, RevI Enclosure 3 Page 2 of 2 CASE (continued)
N-659 CASES or ASNlI ItOI.l:R AND) PRFSSURIt VriSE:I. CODIE (i) The ultrasonic examination shall be performed (I) Review and acceptance of the procedure by the using a device with an automated computer data acquisi- Authorized Nuclear Inspector is required.
tion system. (m) All other related requirements of the applicable (J) Data shall be recorded in unprocessed form. A subsection shall be met.
complete data set with no sating, filtering, or thresh- (it) Flaws exceeding the acceptance criteria refer-olding for response from examination volume in (a) enced in this Case shall be repaired, and the weld shall be included in the data record. subsequently reexamined using the same ultrasonic ex-(k) Personnel who acquire and analyze UT data shall amination procedure that detected the flaw.
be qualified and trained using the same type of equip. (o) This Case number shall be recorded on the Data ment as in (i), and demonstrate their capability to Report.
detect and characterize the flaws using the procedure as described in (c).
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