ML052510117
| ML052510117 | |
| Person / Time | |
|---|---|
| Issue date: | 09/08/2005 |
| From: | Norris W Materials Engineering Branch |
| To: | |
| Norris W 415-6796 | |
| References | |
| DG-1125 RG-1.147, Rev 14 | |
| Download: ML052510117 (31) | |
Text
This regulatory guide identifies the Code Cases that have been determined by the NRC to be acceptable alternatives to applicable parts of Section XI. The latest editionsand addenda of Section XI that the U.S. Nuclear Regulatory Commission (NRC) has approved for use are referenced in 10 CFR 50.55a(b).This guide was issued after consideration of comments received from the public. The NRC staff encourages and welcomes comments and suggestions in connectionwith improvements to published regulatory guides, as well as items for inclusion in regulatory guides that are currently being developed. The NRC staff will revise existingguides, as appropriate, to accommodate comments and to reflect new information or experience. Written comments may be submitted to the Rules and Directives Branch,Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.Regulatory guides are issued in 10 broad divisions: 1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials Facilities; 4, Environmental and Siting;5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Health; 9, Antitrust and Financial Review; and 10, General.Requests for single copies of draft or active regulatory guides (which may be reproduced) should be made to the U.S. Nuclear Regulatory Commission, Washington, DC20555, Attention: Reproduction and Distribution Services Section, or by fax to (301) 415-2289; or by email to Distribution@nrc.gov. Electronic copies of this guide andother recently issued guides are available through the NRC's public Web site under the Regulatory Guides document collection of the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRC's Agencywide Documents Access and Management System (ADAMS) athttp://www.nrc.gov/reading-rm/adams.html, under Accession No. ML052510117. Note, however, that the NRC has temporarily suspended public access to ADAMS sothat the agency can complete security reviews of publicly available documents and remove potentially sensitive information. Please check the NRC's Web site for updatesconcerning the resumption of public access to ADAMS.U.S. NUCLEAR REGULATORY COMMISSIONRevision 14August 2005REGULATORY GUIDEOFFICE OF NUCLEAR REGULATORY RESEARCHREGULATORY GUIDE 1.147(Draft was issued as DG-1125, dated August 2004)INSERVICE INSPECTION CODE CASE ACCEPTABILITY,ASME SECTION XI, DIVISION 1A. INTRODUCTIONGeneral Design Criterion (GDC) 1, "Quality Standards and Records," of Appendix A, "General DesignCriteria for Nuclear Power Plants," to Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50),"Domestic Licensing of Production and Utilization Facilities," requires, in part, that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Where generally recognized codes and standards are used, Criterion 1 requires that they be identified and evaluated to determine their applicability, adequacy, and sufficiency and be supplemented or modified as necessary to ensure a quality product in keeping with the required safety function.Provisions of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)Code have been used since 1971 as one part of the framework to establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components important to safety.
Among other things, ASME standards committees develop improved methods for the construction and inservice inspection (ISI) of ASME Class 1, 2, 3, MC (metal containment), and CC (concrete containment) nuclear power plant components. A broad spectrum of stakeholders participates in the ASME process, which helps to ensure that the various interests are considered.
1Copies may be obtained from the American Society of Mechanical Engineers, Three Park Avenue, New York, NY 10016-5990; phone (212) 591-8500; fax (212) 591-8501; www.asme.org
.RG 1.147, Rev. 14, Page 2The regulation in 10 CFR 50.55a(g), "Inservice Inspection Requirements," requires, in part,that Class 1, 2, 3, MC, and CC components and their supports meet the requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"
1 of the ASME BPV Codeor equivalent quality standards. Every 3 years, the ASME publishes a new edition of the BPV Code, including Section XI, and new addenda are published every year. The latest editions and addenda of Section XI that the U.S. Nuclear Regulatory Commission (NRC) has approved for use are referenced in 10 CFR 50.55a(b). The ASME also publishes Code Cases quarterly. Code Cases provide alternatives to existing Code requirements that the ASME developed and approved. This regulatory guide identifies the Code Cases that the NRC has determined to be acceptable alternatives to applicable parts of Section XI. Licensees may use these Code Cases without requesting authorization from the NRC, provided that they are used with any identified limitations or modifications.Section XI Code Cases that the NRC has not yet endorsed may be implemented through 10 CFR 50.55a(a)(3), which permits the use of alternatives to the Code requirements referenced in 10 CFR 50.55a, provided that the proposed alternatives result in an acceptable level of quality and safety and that their use is authorized by the Director of the NRC's Office of Nuclear Reactor Regulation.The ASME Code is incorporated by reference into 10 CFR 50.55a, which the NRC will amendto incorporate this guide by reference; 10 CFR 50.55a states the requirements governing the use of Code Cases. Because of the continuing change in the status of Code Cases, the NRC staff plans periodic updates to 10 CFR 50.55a and this guide to accommodate new Code Cases and any revisions of existing Code Cases. NRC approved Code Cases provide an acceptable voluntary alternative to the mandatory ASME Code provisions.This regulatory guide does not contain a new or amended information collection requirementsubject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). This revision of RegulatoryGuide 1.147 would decrease the paperwork burden for those licensees choosing to use ASME CodeCases N-508-2 and N-600. The paperwork burden reduction is discussed in detail in the rulemaking package for this guide. Because the burden for this information collection is insignificant, Office of Management and Budget (OMB) clearance is not required. The existing information collections are covered by the requirements of 10 CFR Part 50, which the Office of Management and Budget (OMB) approved under OMB control number 3150-0011. The NRC may neither conduct nor sponsor, and a personis not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.
RG 1.147, Rev. 14, Page 3B. DISCUSSIONFor Revision 14 to Regulatory Guide 1.147, the NRC staff reviewed the Section XI Code Caseslisted in Supplement 12 to the 1998 Edition of the ASME B&PV Code through Supplement 6 to the 2001 Edition. Appendix A to this guide lists the supplements reviewed, the edition, supplement number, and the date on which each supplement was approved by the ASME's Board on Nuclear Codes and Standards. Appendix B is a list of the Section III Code Cases addressed in the seven supplements.
Finally, Appendix C is a current list of all Section XI Code Cases. The Code Cases addressed by this regulatory guide are listed in five tables:(1)Table 1, "Acceptable Section XI Code Cases," lists the Code Cases that are acceptable to theNRC for implementation in the ISI of light-water-cooled nuclear power plants.(2)Table 2, "Conditionally Acceptable Section XI Code Cases," lists the Code Cases that areacceptable provided that they are used with the identified limitations or modifications (i.e., the Code Case is generally acceptable, but the NRC has determined that the alternative requirements must be supplemented in order to provide an acceptable level of quality and safety).(3)Table 3, "Annulled Unconditionally Approved Section XI Code Cases," lists Code Casesannulled by the ASME that the NRC previously determined to be fully acceptable.(4)Table 4, "Annulled Conditionally Acceptable Section XI Code Cases," lists the Code Cases thatthe NRC determined to be acceptable, provided that they were used with the identified limitations or modifications, but that the ASME subsequently annulled.(5)Table 5, "Section XI Code Cases That Have Been Superseded by Revised Code Cases," listsCode Cases that have been superseded through revision. Code Cases that the NRC determined to be unacceptable are listed in Regulatory Guide 1.193, "ASME Code Cases Not Approved for Use."When a licensee initially implements a Code Case, 10 CFR 50.55a requires that the most recentversion of that Code Case as listed in Tables 1 and 2 of this guide be implemented. If a Code Case is implemented by a licensee and a later version of the Code Case is approved by the NRC and listed in Tables 1 and 2 during the licensee's present 120-month ISI program interval, that licensee may use either the later version or the previous version. An exception to this provision would be the inclusion of a limitation or condition on the use of the Code Case that is necessary, for example, to enhance safety.
Licensees who choose to continue use of the Code Case during the subsequent 120-month ISI programinterval will be required to implement the latest version incorporated by reference into 10 CFR 50.55a and listed in Tables 1 and 2.Code Cases may expire or be annulled because the provisions have been incorporated into theCode, the application for which it was specifically developed no longer exists, or experience has shown that an examination or testing method is no longer adequate. After the ASME annuls a Code Case and the NRC amends 10 CFR 50.55a and this guide, licensees may not implement that Code Case for the first time. However, a licensee who implemented the Code Case prior to annulment may continue to use that Code Case through the end of the present ISI interval. An annulled Code Case cannot be used in the subsequent ISI interval unless implemented as an approved alternative under 10 CFR 50.55a(a)(3). If a Code Case is incorporated by reference into 10 CFR 50.55a and later annulled by the ASME because experience has shown that an examination or testing method is inadequate, the NRC will amend 10 CFR 50.55a and this guide to remove the approval of the annulled Code Case. Licensees should not begin to implement such annulled Code Cases in advance of the rulemaking. Notwithstanding these requirements, the Commission may impose new or revised Code requirements, including implementation schedules, that it determines are consistent with the backfit rule (10 CFR 50.109).
RG 1.147, Rev. 14, Page 4With regard to the use of any Code Case, it is the responsibility of the user to make certain thatthe provisions of the Code Case do not conflict with regulatory requirements or licensee commitments.C. REGULATORY POSITION1. Acceptable Section XI Code CasesThe Code Cases listed in Table 1 are acceptable to the NRC for application in licensees'Section XI inservice inspection programs. The ASME issues a new edition of Section XI every 3 years.
Code Cases are published quarterly in supplements to each edition. Hence, there are 12 supplements to each edition. Column 3 of Table 1 lists the date of ASME approval or the supplement and edition in which each Code Case was published (e.g., 3/01E means Code Case Supplement 3 to the 2001 Edition).Table 1. Acceptable Section XI Code CasesCode CaseNumberTable 1. Acceptable Section XI Code CasesDate orSupplement/EditionN-307-3Revised Ultrasonic Examination Volume for Class 1 Bolting, TableIWB-2500-1, Examination Category B-G-1, When theExaminations Are Conducted from the End of the Bolt or Stud orfrom the Center-Drilled Hole,Section XI, Division 11/01EN-311Alternative Examination of Outlet Nozzle on Secondary Side ofSteam Generators,Section XI, Division 14/19/02N-322Examination Requirements for Integrally Welded or ForgedAttachments to Class 1 Piping at Containment Penetrations,Section XI, Division 13/28/02N-323-1Alternative Examination for Welded Attachments to PressureVessels,Section XI, Division 14/8/02N-334Examination Requirements for Integrally Welded or ForgedAttachments to Class 2 Piping at Containment Penetrations,Section XI, Division 13/28/00N-416-3Alternative Pressure Test Requirement for Welded Repairs orInstallation of Replacement Items by Welding, Class 1, 2, and 3,Section XI, Division 12/01EN-432-1Repair Welding Using Automatic or Machine Gas Tungsten-ArcWelding (GTAW) Temper Bead Technique,Section XI,Division 1 12/98EN-435-1Alternative Examination Requirements for Vessels With WallThickness 2 in. or Less,Section XI, Division 1R3/28/01N-460Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 13/28/00N-471Acoustic Emission for Successive Inspections,Section XI, Division 14/19/02 Code CaseNumberTable 1. Acceptable Section XI Code CasesDate orSupplement/EditionRG 1.147, Rev. 14, Page 5N-481Alternative Examination Requirements for Cast Austenitic PumpCasings,Section XI, Division 15/20/98N-485-1Eddy Current Examination of Coated Ferritic Surfaces as anAlternative to Surface Examination,Section XI, Division 13/28/00N-490-1Alternative Vision Test Requirements for NondestructiveExaminers,Section XI, Divisions 1, 2, and 33/28/00N-491-2Rules for Examination of Class 1, 2, 3, and MC ComponentSupports of Light-Water Cooled Power Plants,Section XI, Division 13/28/00N-494-3Pipe Specific Evaluation Procedures and Acceptance Criteria forFlaws in Class 1 Ferritic Piping that Exceed the AcceptanceStandards of IWB-3514.2 and in Class 1 Austenitic Piping thatExceed the Acceptance Standards of IWB-3514.3,Section XI,Division 14/19/02N-496-2Helical-Coil Threaded Inserts,Section XI, Division 13/01E(Reinstated)N-503Limited Certification of Nondestructive Examination Personnel,Section XI, Division 1(Note: Because of the statistical screening criteria used forAppendix VIII to Section XI qualifications, this Code Case is notapplicable to Appendix VIII, "Performance Demonstration forUltrasonic Examination Systems.")10/2/00N-508-2Rotation of Serviced Snubbers and Pressure Relief Valves for thePurpose of Testing,Section XI, Division 11/01EN-522Pressure Testing of Containment Penetration Piping,Section XI, Division 14/8/02N-523-2Mechanical Clamping Devices for Class 2 and 3 Piping,Section XI, Division 13/28/01N-526Alternative Requirements for Successive Inspections ofClass 1 and 2 Vessels,Section XI, Division 18/20/02N-534Alternative Requirements for Pneumatic Pressure Testing,Section XI, Division 110/2/00N-537Location of Ultrasonic Depth-Sizing Flaws,Section XI, Division 13/28/01N-545Alternative Requirements for Conduct of PerformanceDemonstration Detection Test of Reactor Vessel,Section XI,Division 15/20/98N-553-1Inservice Eddy Current Surface Examination of Pressure RetainingPipe Welds and Nozzle-to-Safe End Welds,Section XI, Division 112/98EN-566-2Corrective Action for Leakage Identified at Bolted Connections,Section XI, Division 112/98E Code CaseNumberTable 1. Acceptable Section XI Code CasesDate orSupplement/EditionRG 1.147, Rev. 14, Page 6N-573Transfer of Procedure Qualification Records Between Owners,Section XI, Division 13/12/97N-588Attenuation to Reference Flaw Orientation of Appendix G forCircumferential Welds in Reactor Vessels,Section XI, Division 13/28/01N-592ASNT Central Certification Program,Section XI, Division 13/28/01N-598Alternative Requirements to Required Percentages ofExaminations,Section XI, Division 13/28/01N-600Transfer of Welder, Welding Operator, Brazer, and BrazingOperator Qualifications Between Owners,Section XI, Division 12/01EN-601Extent and Frequency of VT-3 Visual Examination for InserviceInspection of Metal Containments,Section XI, Division 13/2/01N-603Alternative to the Requirements of IWL-2421, Sites with TwoPlants,Section XI, Division 13/2/01N-604Alternative to Bolt Torque or Tension Test Requirements of TableIWE-2500-1, Category E-G, Item E8.20,Section XI, Division 17/30/98N-605Alternative to the Requirements of IWE-2500(c) [sic, should stateIWE-2500(b)] for Augmented Examination of Surface Areas,Section XI, Division 1(Note: Draft Regulatory Guide DG-1070, "Sampling Plans Usedfor Dedicating Simple Metallic Commercial Grade Items for Use inNuclear Power Plants," is being developed to provide acceptableguidelines for sampling criteria.)3/2/01N-609Alternative Requirements to Stress-Based Selection Criteria forCategory B-J Welds,Section XI, Division 17/30/98N-613-1Ultrasonic Examination of Penetration Nozzles in Vessels,Examination Category B-D, Item Nos. B3.10 and B3.90, ReactorNozzle-to-Vessel Welds, Figs. IWB-2500-7(a), (b), and (c),Section XI, Division 16/01EN-617Alternative Examination Distribution Requirements for Table IWC-2500-1, Examination Category C-G, Pressure Retaining Welds inPumps and Valves,Section XI, Division 14/19/02N-623Deferral of Inspections of Shell-to-Flange and Head-to-FlangeWelds of a Reactor Vessel,Section XI, Division 14/19/02N-624Successive Inspections,Section XI, Division 14/19/02N-629Use of Fracture Toughness Test Data to Establish ReferenceTemperature for Pressure Retaining Materials,Section XI, Division 18/20/02N-640Alternative Reference Fracture Toughness for Development of P-TLimit Curves,Section XI, Division 14/19/02 Code CaseNumberTable 1. Acceptable Section XI Code CasesDate orSupplement/EditionRG 1.147, Rev. 14, Page 7N-641Alternative Pressure-Temperature Relationship and LowTemperature Overpressure Protection System Requirements,Section XI, Division 11/17/00N-643Fatigue Crack Growth Rate Curves for Ferritic Steels in PWRWater Environment,Section XI, Division 110/2/00N-649Alternative Requirements for IWE-5240 Visual Examination,Section XI, Division 112/98EN-651Ferritic and Dissimilar Metal Welding Using SMAW Temper BeadTechnique Without Removing the Weld Bead Crown for the FirstLayer,Section XI, Division 11/01EN-652Alternative Requirements to Categorize B-G-1, B-G-2, and C-DBolting Examination Methods and Selection Criteria,Section XI,Division 11/01EN-658Qualification Requirements for Ultrasonic Examination ofWrought Austenitic Piping Welds,Section XI, Division 14/01EN-663Alternative Requirements for Classes 1 and 2 SurfaceExaminations,Section XI, Division 16/01EN-664Performance Demonstration Requirements for Examination ofUnclad Reactor Pressure Vessel Welds, Excluding Flange Welds,Section XI, Division 16/01EN-695Qualification Requirements for Dissimilar Metal Piping Welds,Section XI, Division 110/01E RG 1.147, Rev. 14, Page 82. Conditionally Acceptable Section XI Code CasesThe Code Cases listed in Table 2 are acceptable to the NRC for application in licensees' Section XIinservice inspection programs within the limitations imposed by the NRC staff. Unless otherwise stated, limitations imposed by the NRC are in addition to the conditions specified in the Code Case. A new edition of Section XI is published every 3 years, and the ASME issuesSection XI Code Cases quarterly in supplements to a specific edition. Hence, there are 12 supplements to each edition. Column 3 of Table 1 lists the date of ASME approval or the supplement and edition in which each Code Case was published (e.g., 3/01E means Code Case Supplement 3 to the 2001 Edition).Table 2. Conditionally Acceptable Section XI Code CasesCode CaseNumberTable 2. Conditionally Acceptable Section XI Code CasesSupplement/EditionConditionN-498-4Alternative Requirements for 10-Year System Hydrostatic Testingfor Class 1, 2, and 3 Systems,Section XI, Division 14/8/02Prior to conducting the VT-2 examination of Class 2 and Class 3components not required to operate during normal plant operation,a 10 minute holding time is required after attaining test pressure. Prior to conducting the VT-2 examination of Class 2 and Class 3components required to operate during normal plant operation, noholding time is required, provided the system has been in operationfor at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated components or 10 minutes fornon-insulated components.N-504-2Alternative Rules for Repair of Class 1, 2, and 3 AusteniticStainless Steel Piping,Section XI, Division 13/28/00The provisions of Section XI, Nonmandatory Appendix Q, "WeldOverlay Repair of Class 1, 2, and 3 Austenitic Stainless Steel PipingWeldments," must also be met. The appendix is available on theASME Board on Nuclear Codes and Standards web site at:http://cstools.asme.org/csconnect/CommitteePages.cfm?Committee=O10000000 N-513-1Evaluation Criteria for Temporary Acceptance of Flaws inModerate Energy Class 2 or 3 Piping,Section XI, Division 112/98E(1)Specific safety factors in paragraph 4.0 must be satisfied.(2)Code Case N-513 may not be applied to:(a)Components other than pipe and tube.(b)Leakage through a gasket.(c)Threaded connections employing nonstructural seal weldsfor leakage prevention (through seal weld leakage is not astructural flaw; thread integrity must be maintained).(d)Degraded socket welds.N-516-3Underwater Welding,Section XI, Division 15/01E Code CaseNumberTable 2. Conditionally Acceptable Section XI Code CasesSupplement/EditionConditionRG 1.147, Rev. 14, Page 9Licensees must obtain NRC approval in accordance with10 CFR 50.55a(a)(3) regarding the technique to be used in the weldrepair or replacement of irradiated material underwater.N-517-1Quality Assurance Program Requirements for Owners,Section XI, Division 13/28/01The Owner's Quality Assurance (QA) Program that is approvedunder Appendix B to 10 CFR Part 50 must address the use of thisCode Case and any unique QA requirements identified by the CodeCase that are not contained in the owner's QA Program description. This would include the activities performed in accordance with thisCode Case that are subject to monitoring by the Authorized NuclearInspector.N-528-1Purchase, Exchange, or Transfer of Material Between NuclearPlant Sites,Section XI, Division 14/19/02The requirements of 10 CFR Part 21 are to be applied to the nuclearplant site supplying the material as well as to the nuclear plant sitereceiving the material that has been purchased, exchanged, ortransferred between sites.N-532-1Alternative Requirements to Repair and ReplacementDocumentation Requirements and Inservice Summary ReportPreparation and Submission as Required by IWA-4000 andIWA-6000,Section XI, Division 13/28/01Code Case N-532-1 requires an Owner's Activity Report FormOAR-1 to be prepared and certified upon completion of eachrefueling outage. The OAR-1 forms must be submitted to the NRCwithin 90 days of the completion of the refueling outage.N-533-1Alternative Requirements for VT-2 Visual Examination of Class 1,2, and 3 Insulated Pressure-Retaining Bolted Connections,Section XI, Division 14/8/02Prior to conducting the VT-2 examination of Class 2 and Class 3components not required to operate during normal plant operation,a 10 minute holding time is required after attaining test pressure. Prior to conducting the VT-2 examination of Class 2 and Class 3components required to operate during normal plant operation, noholding time is required, provided the system has been in operationfor at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for insulated components or 10 minutes fornon-insulated components.N-546Alternative Requirements for Qualification of VT-2 ExaminationPersonnel,Section XI, Division 19/18/01This Code Case is applicable only to the performance of VT-2examinations and may not be applied to other VT-2 functions suchas verifying the adequacy of procedures and training VT-2 personnel.
Code CaseNumberTable 2. Conditionally Acceptable Section XI Code CasesSupplement/EditionConditionRG 1.147, Rev. 14, Page 10N-552Alternative Methods - Qualification for Nozzle Inside RadiusSection from the Outside Surface,Section XI, Division 14/19/02To achieve consistency with the 10 CFR 50.55a rule changepublished September 22, 1999 (64 FR 51370), incorporatingAppendix VIII, "Performance Demonstration for UltrasonicExamination Systems," to Section XI, add the following to thespecimen requirements:"At least 50 percent of the flaws in the demonstration test set mustbe cracks and the maximum misorientation must be demonstratedwith cracks. Flaws in nozzles with bore diameters equal to or lessthan 4 inches may be notches."Add to detection criteria, "The number of false calls must notexceed three." N-554-2Alternative Requirements for Reconciliation of Replacement Itemsand Addition of New Systems,Section XI, Division 13/28/00The component used for repair/replacement must be manufactured,procured, and controlled as a safety-related component under anNRC-approved Quality Assurance program meeting therequirements of Appendix B to 10 CFR Part 50.N-557-1In-Place Dry Annealing of a PWR Nuclear Reactor Vessel,Section XI, Division 18/20/02The secondary stress allowable of 3S m, shown in Figure 1 of theCode Case, must be applied to the entire primary plus secondarystress range during the anneal.N-567-1Alternative Requirements for Class 1, 2, and 3 ReplacementComponents,Section XI, Division 14/19/02The component used for repair/replacement must have beenmanufactured, procured, and controlled as a safety-relatedcomponent under an NRC-approved Quality Assurance programmeeting the requirements of Appendix B to 10 CFR Part 50.N-568Alternative Examination Requirements for Welded Attachments,Section XI, Division 11/17/00This Code Case may only be used for examination of the accessibleportions of lugs on piping where riser clamps (i.e., clampson vertical runs of pipe) obstruct access to welded surfaces.
Code CaseNumberTable 2. Conditionally Acceptable Section XI Code CasesSupplement/EditionConditionRG 1.147, Rev. 14, Page 11N-569-1Alternative Rules for Repair by Electrochemical Deposition ofClass 1 and 2 Steam Generator Tubing,Section XI, Division 14/19/02NOTES: Steam generator tube repair methods require prior NRCapproval through the Technical Specifications. This Code Casedoes not address certain aspects of this repair (e.g., the qualificationof the inspection and plugging criteria necessary for staff approvalof the repair method). In addition, if the user plans to "reconcile,"as described in Footnote 2, the reconciliation is to be performed inaccordance with IWA-4200 in the 1995 Edition, 1996 Addenda ofASME Section XI.N-576-1Repair of Class 1 and 2 SB-163, UNS N06600 Steam GeneratorTubing,Section XI, Division 14/19/02NOTES: Steam generator tube repair methods require prior NRCapproval through the Technical Specifications. This Code Casedoes not address certain aspects of this repair (e.g., the qualificationof inspection and plugging criteria necessary for staff approvalof the repair method). In addition, if the user plans to "reconcile,"as described in the footnote, the reconciliation is to be performedin accordance with IWA-4200 in the 1995 Edition, 1996 Addendaof ASME Section XI.N-583Annual Training Alternative,Section XI, Division 110/2/00(1)Supplemental practice shall be performed on material or weldsthat contain cracks, or by analyzing prerecorded data frommaterial or welds that contain cracks.(2)The training must be completed no earlier than 6 months priorto performing ultrasonic examinations at a licensee's facility.N-586Alternative Additional Examination Requirements for Class 1, 2,and 3 Piping, Components, and Supports,Section XI, Division 14/8/02The engineering evaluations addressed under Item (a) and theadditional examinations addressed under Item (b) shall beperformed during this outage. If the additional examinationsperformed under Item (b) reveal indications exceeding theapplicable acceptance criteria of Section XI, the engineeringevaluations and the examinations shall be further extended toinclude additional evaluations and examinations at this outage.N-593Alternative Examination Requirements for Steam Generator Nozzleto Vessel Welds,Section XI, Division 112/8/00Essentially 100 percent (not less than 90 percent) of theexamination volume A-B-C-D-E-F-G-H must be inspected.
Code CaseNumberTable 2. Conditionally Acceptable Section XI Code CasesSupplement/EditionConditionRG 1.147, Rev. 14, Page 12N-597-1Requirements for Analytical Evaluation of Pipe Wall Thinning,Section XI, Division 13/28/01(1)Code Case must be supplemented by the provisions of EPRINuclear Safety Analysis Center Report 202L-R2, April 1999,"Recommendations for an Effective Flow AcceleratedCorrosion Program," for developing the inspectionrequirements, the method of predicting the rate of wallthickness loss, and the value of the predicted remaining wallthickness. As used in NSAC-202L-R2, the terms "should" and"shall" have the same expectation of being completed.(2)Components affected by flow-accelerated corrosion to whichthis Code Case are applied must be repaired or replaced inaccordance with the construction code of record and Owner'srequirements or a later NRC-approved edition of Section III ofthe ASME Code prior to the value of t p reaching the allowableminimum wall thickness, tmin, as specified in -3622.1(a)(1) ofthis Code Case. Alternatively, use of the Code Case is subjectto NRC review and approval.(3)For Class 1 piping not meeting the criteria of -3221, the use ofevaluation methods and criteria is subject to NRC review andapproval.(4)For those components that do not require immediate repair orreplacement, the rate of wall thickness loss is to be used todetermine a suitable inspection frequency so that repair orreplacement occurs prior to reaching allowable minimum wallthickness, tmin.(5)For corrosion phenomena other than flow-acceleratedcorrosion, use of the Code Case is subject to NRC review andapproval. Inspection plans and wall thinning rates may bedifficult to justify for certain degradation mechanisms such asMIC and pitting.N-599Alternatives to Qualification of Nondestructive ExaminationPersonnel for Inservice Inspection of Metal (Class MC) andConcrete (Class CC) Containments,Section XI, Division 19/18/01This Code Case may not be used when a licensee updates to the1992 or later Edition of Section XI that requires the use ofANSI/ASNT CP-189, "Standard for Qualification and Certificationof Nondestructive Testing Personnel."
Code CaseNumberTable 2. Conditionally Acceptable Section XI Code CasesSupplement/EditionConditionRG 1.147, Rev. 14, Page 13N-606-1Similar and Dissimilar Metal Welding Using Ambient TemperatureMachine GTAW Temper Bead Technique for BWR CRDHousing/Stub Tube Repairs,Section XI, Division 18/20/02Prior to welding, an examination or verification must be performedto ensure proper preparation of the base metal, and that the surfaceis properly contoured so that an acceptable weld can be produced. The surfaces to be welded, and surfaces adjacent to the weld, are tobe free from contaminants, such as, rust, moisture, grease, and otherforeign material or any other condition that would prevent properwelding and adversely affect the quality or strength of the weld. This verification is to be required in the welding procedures.N-616Alternative Requirements for VT-2 Visual Examination of Classes1, 2, 3 Insulated Pressure Retaining Bolted Connections,Section XI, Division 14/8/02(1)Insulation must be removed for VT-2 examination duringthe system pressure test for any 17-4 Precipitation Hardeningstainless steel stud or bolt aged at a temperature below 1100F, or 410 stainless steel stud or bolt aged at atemperature below 1100F or with hardness above R c 30.(2)For A-286 stainless steel studs or bolts, the preload must beverified to be below 100 Ksi or the thermal insulation must beremoved and the joint visually examined.(3)Prior to conducting the VT-2 examination of Class 2 andClass 3 components not required to operate during normalplant operation, a 10 minute holding time is required afterattaining test pressure. Prior to conducting the VT-2examination of Class 2 and Class 3 components required tooperate during normal plant operation, no holding time isrequired, provided the system has been in operation for at least4 hours for insulated components or 10 minutes fornon-insulated components.N-619Alternative Requirements for Nozzle Inner Radius Inspections forClass 1 Pressurizer and Steam Generator Nozzles,Section XI,Division 14/8/02In lieu of a UT examination, licensees may perform a visualexamination with enhanced magnification that has a resolutionsensitivity to detect a 1-mil width wire or crack, utilizing theallowable flaw length criteria of Table IWB-3512-1 with limitingassumptions on the flaw aspect ratio. The provisions of TableIWB-2500-1, Examination Category B-D, continue to apply exceptthat, in place of examination volumes, the surfaces to be examinedare the external surfaces shown in the figures applicable to thistable.
Code CaseNumberTable 2. Conditionally Acceptable Section XI Code CasesSupplement/EditionConditionRG 1.147, Rev. 14, Page 14N-638-1Similar and Dissimilar Metal Welding Using Ambient TemperatureMachine GTAW Temper Bead Technique,Section XI, Division 18-9/01EUT examinations shall be demonstrated for the repaired volumeusing representative samples which contain construction type flaws. The acceptance criteria of NB-5330 of Section III edition andaddenda approved in 10 CFR 50.55a apply to all flaws identifiedwithin the repaired volume.N-639Alternative Calibration Block Material,Section XI, Division 18/20/02Chemical ranges of the calibration block may vary from thematerials specification if (1) it is within the chemical range of thecomponent specification to be inspected, and (2) the phase andgrain shape are maintained in the same ranges produced by thethermal process required by the material specification.N-647Alternative to Augmented Examination Requirements ofIWE-2500,Section XI, Division 112/8/00A VT-1 examination is to be used in lieu of the "detailed visualexamination." (Note: Draft Regulatory Guide DG-1070, "SamplingPlans Used for Dedicating Simple Metallic Commercial GradeItems for Use in Nuclear Power Plants," is being developed toprovide acceptable guidelines for sampling criteria.)N-648-1Alternative Requirements for Inner Radius Examination ofClass 1 Reactor Vessel Nozzles,Section XI Division 19/18/01In place of a UT examination, licensees may perform a visualexamination with enhanced magnification that has a resolutionsensitivity to detect a 1-mil width wire or crack, utilizing theallowable flaw length criteria of Table IWB-3512-1 with limitingassumptions on the flaw aspect ratio. The provisions of TableIWB-2500-1, Examination Category B-D, continue to apply exceptthat, in place of examination volumes, the surfaces to be examinedare the external surfaces shown in the figures applicable to thistable.N-660Risk-Informed Safety Classification for Use in Risk-InformedRepair/Replacement Activities,Section XI, Division 15/01EThe Code Case must be applied only to ASME Code Classes 2 and 3,and non-Code Class pressure retaining components and theirassociated supports.
Code CaseNumberTable 2. Conditionally Acceptable Section XI Code CasesSupplement/EditionConditionRG 1.147, Rev. 14, Page 15N-661Alternative Requirements for Wall Thickness Restoration of Classes2 and 3 Carbon Steel Piping for Raw Water Service,Section XI,Division 15/01E(a) If the root cause of the degradation has not been determined, therepair is only acceptable for one cycle.(b) Weld overlay repair of an area can only be performed once in thesame location.(c) When through-wall repairs are made by welding on surfaces thatare wet or exposed to water, the weld overlay repair is only acceptableuntil the next refueling outage.N-662Alternative Repair/Replacement Requirements for Items Classifiedin Accordance with Risk-Informed Processes,Section XI, Division 16/01EThe Code Case must be applied only to ASME Code Classes 2 and 3,and non-Code Class pressure retaining components and theirassociated supports.
RG 1.147, Rev. 14, Page 163. Annulled Unconditionally Approved Section XI Code CasesThe Code Cases listed in Table 3 were previously unconditionally approved by the NRC and havebeen annulled by the ASME. The third column of the table lists the date that the Code Case was annulled by the ASME, and the Supplement and Edition if the Code Case was annulled in Supplement 12 to the 1998 Edition through Supplement 6 to the 2001 Edition (e.g., 3/01E means Supplement 3 to the 2001 Edition).Table 3. Annulled Unconditionally Approved Section XI Code CasesCode CaseNumberTable 3. Annulled Unconditionally Approved Section XICode CasesAnnulment Date;Supplement/EditionN-34 (1551)Inservice Inspection of Welds of Nuclear Components,Section XI11/20/81N-72 (1646)Partial Postponement of Category B-C Examination for Class 1Components, Section XI1/1/81N-73 (1647)Partial Postponement of Category B-D Examination for Class 1Components, Section XI1/1/81N-98 (1705-1)Ultrasonic Examination - Calibration Block Tolerances,Section XI, Division 18/9/96N-112 (1730)Acceptance Standards for Class 2 and 3 Components,Section XI, Division 17/1/79N-113-1Basic Calibration Block for Ultrasonic Examination of Weld10 in. to 14 in. Thick,Section XI, Division 18/9/96N-167 (1804)Minimum Section Thickness Requirements for Repair ofNozzles,Section XI, Division 11/14/80N-198-1Exemption from Examination for ASME Class 1 and 2 PipingLocated at Containment Penetrations,Section XI, Division 13/28/01;1/01EN-211Recalibration of Ultrasonic Equipment Upon Change ofPersonnel,Section XI, Division 1(The Code Case was annulled on 3/20/81 and reinstated on7/13/81. There was no change in the Code Case, and the NRCconsiders that the Code Case was in effect during the period3/20/81 through 7/13/81)4/30/93N-216Alternative Rules for Reactor Vessel Closure Stud Examination,Section XI, Division 15/7/90N-234Time Between Ultrasonic Calibration Checks,Section XI,Division 112/3/90N-235Ultrasonic Calibration Checks per Section V,Section XI,Division 18/9/96N-236-1Repair and Replacement of Class MC Vessels,Section XI, Division 18/5/97N-288Hydrostatic Test Requirements for Class 1 and Class 2Components,Section XI, Division 15/25/83 Code CaseNumberTable 3. Annulled Unconditionally Approved Section XICode CasesAnnulment Date;Supplement/EditionRG 1.147, Rev. 14, Page 17N-306Calibration Block Material Selection, Appendix 1, 1-3121,Section XI, Division 15/7/90N-308Documentation of Repairs and Replacements of Components inNuclear Power Plants,Section XI, Division 19/30/90N-335-1Rules for Ultrasonic Examination of Similar and DissimilarMetal Piping Welds,Section XI, Division 15/11/97N-343Alternative Scope of Examination of Attachment Welds forExamination Categories B-H, B-K-1, and C-C,Section XI,Division 112/3/90N-355Calibration Block for Angle Beam Ultrasonic Examination ofLarge Fittings in Accordance with Appendix III-3410,Section XI, Division 18/9/96N-356Certification Period for Level III NDE Personnel,Section XI, Division 1(July 1, 1988, is the date that the provisions of the Code Casewere acceptable to the NRC)8/5/97N-375-2Rules for Ultrasonic Examination of Bolds and Studs,Section XI, Division 15/7/90N-389-1Alternative Rules for Repairs, Replacements, or Modifications,Section XI, Division 1 4/19/02;4/01EN-401-1Eddy Current Examination,Section XI, Division 15/11/97N-402-1Eddy Current Calibration Standards,Section XI,Division 15/11/97N-406Alternative Rules for Replacement,Section XI,Division 15/7/90N-408-3Alternative Rules for Examination of Class 2 Piping,Section XI,Division 1 4/19/02;4/01EN-409-3Procedure and Personnel Qualification Requirements forUltrasonic Detection and Sizing of Flaws in Piping Welds,Section XI, Division 14/30/96N-415Alternative Rules for Testing Pressure Relief,Section XI,Division 18/14/94N-419Extent of VT-1 Examinations, Category B-G-1 of Table IWB-2500-1,Section XI, Division 15/13/94N-424Qualification of Visual Examination Personnel,Section XI,Division 17/18/88N-426Extent of VT-1 Examinations, Category B-G-2 of TableIWB-2500-1,Section XI, Division 15/13/94N-427Code Cases in Inspection Plans,Section XI, Division 112/16/94 Code CaseNumberTable 3. Annulled Unconditionally Approved Section XICode CasesAnnulment Date;Supplement/EditionRG 1.147, Rev. 14, Page 18N-429-2Alternative Rules for Ultrasonic Instrument Calibration,Section XI, Division 17/27/95N-436-1Alternative Methods for Evaluation of Flaws in AusteniticPiping,Section XI, Division 112/3/90N-437Use of Digital Readout and Digital Measurement Devices forPerforming Pressure Tests,Section XI, Division 17/27/95N-444Preparation of Inspection Plans,Section XI, Division 1(Valve stroke times may be documented outside of the ISTprogram. However, if included within the IST program and itbecomes necessary to revise the maximum stroke time requiredby "Supplement 4-Content of IWV Valve Test Tables," it isnot necessary to submit a revised IST program to the NRCsolely to document a revision in valve stroke time)12/30/90N-445Use of Later Editions of SNT-TC-1A for Qualification ofNondestructive Examination Personnel,Section XI, Division 1,2, and 35/7/90N-446Recertification of Visual Examination Personnel,Section XI,Division 15/7/90N-448Qualification of VT-2 and VT-3 Visual Examination Personnel,Section XI, Division 14/30/96N-449Qualification of VT-4 Visual Examination Personnel,Section XI, Division 14/30/96N-457Qualification Specimen Notch Location for UltrasonicExamination of Bolts and Studs,Section XI, Division 14/19/02;4/01EN-458-1Magnetic Particle Examination of Coated Materials,Section XI,Division 13/38/01;12/98EN-461-1Alternative Rules for Piping Calibration Block Thickness,Section XI, Division 13/28/01;12/98EN-463-1Evaluation Procedures and Acceptance Criteria for Flaws inClass 1 Ferritic Piping That Exceed the Acceptance Standardsof IWB-3514.2,Section XI, Division 13/28/0112/98EN-465Alternative Rules for Pump Testing,Section XI, Division 18/14/94N-472Use of Digital Readout and Digital Measurement Devices forPerforming Pump Vibration Testing,Section XI, Division 18/14/97N-473Alternative Rules for Valve Testing,Section XI, Division 112/16/94N-478Inservice Inspection for Class CC Concrete Components ofLight-Water Cooled Power Plants,Section XI, Division 13/2/98N-479-1Boiling Water Reactor (BWR) Main Steam Hydrostatic Test,Section XI, Division 14/19/02;4/01E Code CaseNumberTable 3. Annulled Unconditionally Approved Section XICode CasesAnnulment Date;Supplement/EditionRG 1.147, Rev. 14, Page 19N-489Alternative Rules for Level III NDE Qualification Examinations,Section XI, Divisions 1, 2, and 34/19/02;4/01EN-495Hydrostatic Testing of Relief Valves,Section XI, Division 14/19/02;4/01EN-496-1Helical-Coil Threaded Inserts,Section XI, Division 15/11/97N-514Low Temperature Overpressure Protection,Section XI, Division 14/19/02;4/01EN-515Class 1 Mechanical Joint Pressure Tests,Section XI, Division 14/19/02;4/01EN-521Alternative Rules for Deferral of Inspections of Nozzle-to-VesselWelds, Inside Radius Sections, and Nozzle-to-Safe End Welds ofa Pressurized Water Reactor (PWR) Vessel,Section XI,Division 14/19/02;4/01EN-524Alternative Examination Requirements for Longitudinal Weldsin Class 1 and 2 Piping,Section XI, Division 14/19/02;4/01EN-535Alternative Requirements for Inservice Inspection Intervals,Section XI, Division 13/28/01;12/98EN-538Alternative Requirements for Length Sizing PerformanceDemonstration in Accordance with Appendix VIII,Supplements 2, 3, 10, 11, and 12,Section XI, Division 14/19/02;4/01EN-541Alternative Requirements for Performance Demonstration inAccordance with Appendix VIII, Supplements 4 and 6,Section XI, Division 13/28/01;12/98EN-543Alternative to Performing Periodic Calibration Checks,Section XI, Division 19/18/01;2/01EN-544Repair/Replacement of Small Items,Section XI, Division 13/28/01N-555Use of Section II, V, and IX Code Cases,Section XI, Division 14/8/02;5/05EN-556Alternative Requirements for Verification of Acceptability ofReplacements,Section XI, Division 14/19/02;4/01EN-563Grading of Examinations, IWA-2320,Section XI, Division 14/19/02;4/01EN-627VT-1 Visual Examination in Lieu of Surface Examination forRPV Closure Nuts,Section XI, Division 15/7/02;4/01E RG 1.147, Rev. 14, Page 204. Annulled Conditionally Acceptable Section XI Code CasesThe Code Cases listed in Table 4 were conditionally approved by the NRC but were subsequentlyannulled by the ASME. The third column of the table lists the date that the Code Case was annulled by the ASME, and the Supplement and Edition if the Code Case was annulled in Supplement 12 to the 1998 Edition through Supplement 6 to the 2001 Edition (e.g., 3/01E means Supplement 3 to the 2001 Edition).Table 4. Annulled Conditionally Section XI Code CasesCode CaseNumberTable 4. Annulled Conditionally Acceptable Section XI Code CasesAnnulment Date;Supplement/ EditionN-118 (1738)Examination-Acceptance Standards for Surface Indicationsin Cladding, Section XI12/3/90The last sentence of the "Reply" is to be replaced with thefollowing: "The provisions of this Code Case may not beapplied for the examination of clad surfaces of nozzles,including the inner surface of the nozzle-to-vessel insert welds."N-210Exemption to Hydrostatic Tests After Repairs,Section XI,Division 13/20/81Paragraph (3) of the "Reply" is to be replaced with thefollowing: "Repairs to piping, pumps, and valves where thedepth of the repaired cavity does not exceed 25 percent of thewall thickness."N-252Low Energy Capacitive Discharge We lding Method forTemporary or Permanent Attachments to Components andSupports,Section III, Division 1, and Section XI7/16/82The applicant should indicate in the Safety Analysis Report theapplication, the material, and the thickness of the material towhich the strain gage or thermocouple will be attached by CDwelding.N-278Alternative Ultrasonic Calibration Block Configuration I-3131and T-434.3,Section XI, Division 1(Code Case N-278 was inadvertently allowed to expire becauseof an ASME administrative error on 3/17/83. The Code Casewas reinstated without technical change on 5/25/93. Thus, theNRC considered the Code Case to be in effect during the period3/17/83 through 5/25/93.)2/19/92When a universal calibration block is used and some or all ofthe reference holes are larger than the reflector holes atcomparable depths recommended by Article IV,Section V,1980 Edition of the ASME Code, a correction factor should beused to adjust the DAC level to compensate for the largerreflector holes. Also, if the reactor pressure vessel waspreviously examined by using a conventional black, a rationbetween the DAC curves obtained from the two blocks shouldbe note (for reference) with the significant indication data.
Code CaseNumberTable 4. Annulled Conditionally Acceptable Section XI Code CasesAnnulment Date;Supplement/ EditionRG 1.147, Rev. 14, Page 21N-509Alternative Rules for the Selection and Examination of Class 1,2, and 3 Integrally Welded Attachments,Section XI, Division 15/20/01;1/01EA minimum 10% sample of integrally welded attachments foreach item in each Code class per interval should be examined.N-512-1Assessment of Reactor Vessels With Low Upper Shelf CharpyImpact Energy Levels,Section XI, Division 15/20/01;1/01EThe material properties and transient selection must follow theguidance in Regulatory Guide 1.161, "Evaluation of ReactorPressure Vessels with Charpy Upper-Shelf Energy Less Than 50ft-lb," or an equivalent method approved by the NRC staff.N-630Alternatives to VT-1C and VT-3C Visual Examination forInservice Inspection of Concrete and VT-1 Visual Examinationfor Inservice Inspection of Anchorage Hardware andSurrounding Concrete for Concrete Containments,Section XI,Division 14/8/025/01EThe Responsible Engineer's written practice must definequalification requirements for concrete and tendon hardwareexamination personnel in accordance with IWA-2300 in lieu ofthe Owner defined qualification requirements specified inParagraph (c) of the Code Case. However, limited certificationin accordance with IWA-2350 is permitted.
RG 1.147, Rev. 14, Page 225. Code Cases That Have Been SupersededTable 5 lists Code Cases that have been superseded by revision. The third column of the tableindicates the date on which each Code Case was superseded. Note: Some of these Code Cases were not approved for use by the NRC in previous versions of Regulatory Guide 1.147.Table 5.Section XI Code Cases That Have Been SupersededCode CaseNumberTable 5.Section XI Code CasesThat Have Been SupersededDateN-113 (1731)Basic Calibration Block for Ultrasonic Examination of Weld 10 in.To 14 in. Thick,Section XI, Division 1N-113-1 Published on12/31/82N-236Repair and Replacement of Class MC Vessels,Section XI, Division 1N-236-1 Published on9/5/85(a)In paragraph 1.0(a), second sentence, the phrase, "while theplant is not in service," refers to a refueling outage.(b)In paragraph 1.0(a), third sentence, the phrase, "the nextscheduled plant outage," refers to the next schedule refuelingoutage.For clarification, "Repair and Replacement of Class MC Vessels"means Repair and Replacement of Class MC Vessels andComponents (systems). Acceptance of this Code Case in no wayprovides/constitutes NRC approval to violate the technicalspecification or any NRC requirements with regard to breach ofcontainment during repair and replacement procedures while theplant is in operation.Where a numbered Code paragraph is not identified by a particularedition of the Code, the Code in effect at the time of the ASMEmeeting (11/3/78) that approved the Code Case should begoverning.N-307N-307-1N-307-2Revised Ultrasonic Examination Volume for Class 1 Bolting,Table IWB-2500-1, Examination Category B-G-1, When theExaminations Are Conducted from the Center-Drilled Hole,Section XI, Division 1N-307-1 Published on12/5/84N-307-2 Published on9/24/99N-307-3 Published on3/28/01N-335Rules for Ultrasonic Examination of Similar and Dissimilar MetalPiping Welds,Section XI, Division 1N-335-1 Published on6/20/85N-375N-375-1Rules for Ultrasonic Examination of Bolds and Studs,Section XI,Division 1N-375-1 Published on4/14/83;N-375-2 Published on4/5/84 Code CaseNumberTable 5.Section XI Code CasesThat Have Been SupersededDateRG 1.147, Rev. 14, Page 23N-389Alternative Rules for Repairs, Replacements, or Modifications,Section XI, Division 1 N-389-1 Published on12/9/93The applicant should submit for approval the appropriate editionand addenda of the Code that is to be used for the repair,replacement, or modification before the start of the work.N-401Eddy Current Examination,Section XI, Division 1N-401-1 Published on5/4/88N-402Eddy Current Calibration Standards,Section XI,Division 1N-402-1 Published on3/14/91N-408Alternative Rules for Examination of Class 2 Piping,Section XI,Division 1N-408-1 Published on3/8/89N-408-1N-408-2Alternative Rules for Examination of Class 2 Piping,Section XI,Division 1N-408-2 Published on7/24/89N-408-3 Published on8/9/93The applicant for an operating license should define the Class 2piping subject to volumetric and surface examination in thepreservice inspection for determination of acceptability by theNRC staff.N-409Procedure and Personnel Qualification Requirements forUltrasonic Detection and Sizing of Flaws in Piping Welds,Section XI, Division 1N-409-1 Published on12/7/87N-409-1N-409-2Procedure and Personnel Qualification Requirements forUltrasonic Detection and Sizing of Flaws in Piping Welds,Section XI, Division 1N-409-2 Published on7/27/88;N-409-3 Published on4/30/93The applicant should give prior notification to the NRC of theintention to use the Code Case.N-416N-416-1N-416-2Alternative Pressure Test Requirements for Welded Repairs orInstallation of Replacement Items by Welding, Class 1, 2, and 3,Section XI, Division 1N-416-1 Published on2/15/94N-416-2 Published on5/5/00N-416-3 Published on7/7/01N-429N-429-1Alternative Rules for Ultrasonic Instrument Calibration,Section XI, Division 1N-429-1 Published on2/23/87;N-429-2 Published on7/27/92N-432Repair Welding Using Automatic or Machine Gas Tungsten-ArcWelding (GTAW) Temper Bead Technique,Section XI, Division 1 N-432-1 Published on3/28/01N-435Alternative Examination Requirements for Vessels With WallThickness 2 in. Or Less,Section XI, Division 1N-435-1 Published on7/30/86 Code CaseNumberTable 5.Section XI Code CasesThat Have Been SupersededDateRG 1.147, Rev. 14, Page 24N-436Alternative Methods for Evaluation of Flaws in Austenitic Piping,Section XI, Division 1N-436-1 Published on12/7/87N-458Magnetic Particle Examination of Coated Materials,Section XI,Division 1N-458-1 Published on3/14/95N-461Alternative Rules for Piping Calibration Block Thickness,Section XI, Division 1N-461-1 Published on3/14/95N-463Evaluation Procedures and Acceptance Criteria for Flaws inClass 1 Ferritic Piping That Exceed the A cceptance Standards ofIWB-3514.2,Section XI, Division 1N-463-1 Published on3/5/90N-479Boiling Water Reactor (BWR) Main Steam Hydrostatic Test,Section XI, Division 1N-479-1 Published on12/3/90N-485Eddy Current Examination of Coated Ferritic Surfaces as anAlternative to Surface Examination,Section XI, Division 1N-485 Published on8/14/91N-490Alternative Vision Test Requirements for NondestructiveExaminers,Section XI, Divisions 1, 2, and 3N-490-1 Published on5/13/91N-491N-491-1Alternative Rules for Examination of Class 1, 2, 3, and MCComponent Supports of Light-Water Cooled Power Plants,Section XI, Division 1N-491-1 Published on4/30/93;N-491-2 Published on3/12/97N-494N-494-1N-494-2Pipe Specific Evaluation Procedures and Acceptance Criteria forFlaws in Class 1 Ferritic Piping that Exceed the AcceptanceStandards of IWB-3514.2,Section XI, Division 1N-494-1 Published on7/27/92;N-494-2 Published on12/9/93N-494-3 Published on8/9/96N-496N-496-1Helical-Coil Threaded Inserts,Section XI, Division 1N-496-1 Published on5/11/94;N-496-1 Annulled on5/11/97N-496-2 Published on9/18/01N-498N-498-1N-498-2N-498-3Alternative Rules for 10-Year System Hydrostatic Testing forClass 1, 2, and 3 Systems,Section XI, Division 1N-498-1 Published on5/11/94N-498-2 Published on6/9/95N-498-3 Published on5/20/98N-498-4 Published on2/15/99N-504N-504-1Alternative Rules for Repair of Class 1, 2, and 3 AusteniticStainless Steel Piping,Section XI,Division 1N-504-1 Published on8/9/93N-504-2 Published on3/12/97 Code CaseNumberTable 5.Section XI Code CasesThat Have Been SupersededDateRG 1.147, Rev. 14, Page 25N-508N-508-1Rotation of Serviced Snubbers and Pressure Relief Valves for thePurpose of Testing,Section XI, Division 1N-508-1 Published on5/11/94N-508-2 Published on3/28/01N-512Assessment of Reactor Vessels With Low Upper Shelf CharpyImpact Energy Levels,Section XI, Division 1N-512-1 Published on8/24/95N-513Evaluation Criteria for Temporary Acceptance of Flaws in Class 3Piping,Section XI, Division 1N-513-1 Published on3/28/01N-516N-516-1Underwater Welding,Section XI, Division 1N-516-1 Published on12/31/96;N-516-2 Published on1/17/00When welding is to be performed on high neutron fluence Class 1material, then a mockup, using material with similar fluence levels,should be welded to verify that adequate crack preventionmeasures were used.N-516-2Underwater Welding,Section XI, Division 1N-516-3 Published on4/8/02Licensees must obtain NRC approval in accordance with10 CFR 50.55a(a)(3) regarding the method to be used in the weldrepair or replacement of irradiated material underwater.N-517Quality Assurance Program Requirements for Owners,Section XI,Division 1N-517-1 Published on7/30/98N-523N-523-1Mechanical Clamping Devices for Class 2 and 3 Piping,Section XI, Division 1N-523-1 Published on8/24/95N-523-2 Published on10/2/00N-528Purchase, Exchange, or Transfer of Material Between NuclearPlant Sites,Section XI, Division 1N-528-1 Published on5/7/99N-532Alternative Requirements to Repair and ReplacementDocumentation Requirements and Inservice Summary ReportPreparation and Submission as Required by IWA-4000 andIWA-6000,Section XI, Division 1N-532-1 Published on3/28/01N-533Alternative Requirements for VT-2 Visual Examination of Class 1Insulated Pressure-Retaining Bolted Connections,Section XI,Division 1N-533-1 Published2/26/99N-553Inservice Eddy Current Surface Examination of PressureRetaining Pipe Welds and Nozzle-to-Safe End Welds,Section XI,Division 1N-553-1 Published on3/28/01N-554N-554-1Alternative Requirements for Reconciliation of Replacement Items,Section XI, Division 1N-554-1 Published on7/98E;N-554-2 Published on2/25/00 Code CaseNumberTable 5.Section XI Code CasesThat Have Been SupersededDateRG 1.147, Rev. 14, Page 26N-557In-Place Dry Annealing of a PWR Nuclear Reactor Vessel,Section XI, Division 1N-557-1 Published on12/31/96N-560N-560-1Alternative Examination Requirements for Class 1, Category B-JPiping Welds,Section XI, Division 1N-560-1 Published on8/9/96;N-560-2 Published on3/28/00N-561Alternative Requirements for Wall Thickness Restoration ofClass 2 and High Energy Class 3 Carbon Steel Piping,Section XI,Division 1N-561-1 Published on7/30/98N-562Alternative Requirements for Wall Thickness Restoration ofClass 3 Moderate Energy Carbon Steel Piping,Section XI,Division 1N-562-1 Published on7/30/98N-566N-566-1Corrective Action for Leakage Identified at Bolted Connections,Section XI, Division 1N-566-1 Published on2/15/99N-566-2 Published on3/28/01N-567Alternative Requirements for Class 1, 2, and 3 ReplacementComponents,Section XI, Division 1N-567-1 Published on2/26/99N-569Alternative Rules for Repair by Electrochemical Deposition ofClass 1 and 2 Steam Generator Tubing,Section XI, Division 1N-569-1 Published on5/7/99N-576Repair of Class 1 and 2 SB-163, UNS N06600 Steam GeneratorTubing,Section XI, Division 1N-576-1 Published on5/7/99N-577Risk-Informed Requirements for Class 1, 2, and 3 Piping,Method A,Section XI, Division 1N-577-1 Published on3/28/00N-578Risk-Informed Requirements for Class 1, 2, and 3 Piping,Method B,Section XI, Division 1N-578-1 Published on3/28/00N-597Requirements for Analytical Evaluation of Pipe Wall Thinning,Section XI, Division 1N-597-1 Published on7/7/01N-606Similar and Dissimilar Metal Welding Using AmbientTemperature Machine GTAW Temper Bead Technique,Section XI,Division 1N-606-1 Published on9/24/99N-638Similar and Dissimilar Metal Welding Using AmbientTemperature Machine GTAW Temper Bead Technique,Section XI,Division 1N-638-1 Published on5/9/03The Construction Code of Record acceptance criteria must be usedfor volumetric examinations.N-648Alternative Requirements for Inner Radius Examination of Class 1Reactor Vessel Nozzles,Section XI, Division 1N-648-1 Published on7/7/01 RG 1.147, Rev. 14, Page 27D. IMPLEMENTATIONThe purpose of this section is to provide information to applicants and licensees regardingthe NRC staff's plans for using this guide. No backfitting is intended or approved in connectionwith the issuance of this guide.Except when an applicant or licensee proposes or has previously established an acceptablealternative method for complying with specified portions of the NRC's regulations, the methods described in this guide will be used in evaluating (1) submittals in connection with applications for construction permits, design certifications, operating licenses, and combined licenses, and (2) submittals from operating reactor licensees who voluntarily propose to initiate system modifications that have a clear nexus with this guidance.E. REGULATORY ANALYSISA separate regulatory analysis was not prepared for this regulatory guide. The regulatory basis forthis guide is the regulatory analysis prepared for the amendment to 10 CFR 50.55a, "Codes and Standards,"
that incorporates by reference this regulatory guide.A copy of the regulatory analysis for the amendment to 10 CFR 50.55a is available for inspectionand copying for a fee at the NRC's Public Document Room (PDR), which is located at 11555 Rockv illePike, Rockville, Maryland; the PDR's mailing address is USNRC PDR, Washington, DC 20555-0001. The PDR can also be reached by telephone at (301) 415-4737 or (800) 397-4205, by fax at (301) 415-3548,and by email to PDR@nrc.gov. In addition, the regulatory analysis is available electronicallythrough the NRC's Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML043640544.
Appendix A to RG 1.147, Rev. 14, Page A-1APPENDIX ASUPPLEMENTS ADDRESSED IN PROPOSED REVISION 14TO REGULATORY GUIDE 1.147EditionSupplement NumberBNCS 1 Approval Date of Code Cases in Supplement 2199812March 28, 200120011August 14, 200120012September 18, 200120013September 18, 200120014April 19, 200220015July 23, 200220016September 17, 2002 1BNCS = ASME Board on Nuclear Codes and Standards 2Publication in supplement was between 5 and 8 months after BNCS approval.
Appendix B to RG 1.147, Rev. 14, Page B-1APPENDIX BNUMERICAL LISTING OF SECTION XI CODE CASES IN SUPPLEMENT 12, 1998 EDITION, THROUGH SUPPLEMENT 6, 2001 EDITIONN-198-1N-307-3 N-323-1 N-389-1 N-408-3 N-416-3 N-432-1 N-435-1 N-457 N-458-1 N-461-1 N-463-1 N-471 N-479-1 N-480 1N-489 N-494-3 N-495 N-496-2 N-498-4 N-508-2 N-509 N-512-1 N-513-1 N-514 N-515 N-516-3 N-517-1 N-521 N-522 N-523-2 N-524 N-526 N-528-1N-532-1N-532-2 1N-533-1 N-535 N-537 N-538 N-541 N-542 1N-543 N-544 N-546 N-547 1N-552 N-553-1 N-555 N-556 N-557-1 N-561-1 N-562-1 N-563 N-566-2 N-567-1 N-569-1 N-576-1 N-586 N-588 N-589 1N-589-1 1N-590 N-591 N-592 N-597 N-597-1N-598N-599 N-600 N-601 N-603 N-605 N-606-1 N-613-1 N-615 1N-616 N-617 N-619 N-622 1N-623 N-624 N-627 N-629 N-630 N-638 N-639 N-640 N-648-1 N-649 N-651 N-652 N-653 1N-654 N-658 N-660 N-661 N-662 N-663 N-664________________________
1Code case is unacceptable for use. See Revision 1 to Regulatory Guide 1.
193.
______________________
1Code case is unacceptable for use. See Revision 1 to Regulatory Guide 1.
193.2 Code case approved February 13, 2003, published in Supplements 8 and 9, 2001 Edition.
3 Code case approved May 21, 2003, published in Supplement 11, 2001 Edition.Appendix C to RG 1.147, Rev. 14, Page C-1APPENDIX CNUMERICAL LISTING OF SECTION XI CODE CASESAND TABLE WHERE EACH CODE CASE IS LISTEDN-34 [T3]N-72 [T3]
N-73 [T3]
N-98 [T3]
N-112 [T3]
N-113 [T5]
N-113-1 [T3]
N-118 [T4]
N-167 [T3]
N-198-1 [T3]
N-210 [T4]
N-211 [T3]
N-216 [T3]
N-234 [T3]
N-235 [T3]
N-236 [T5]
N-236-1 [T3]
N-252 [T4]
N-278 [T4]
N-288 [T3]
N-306 [T3]
N-307 [T5]
N-307-1 [T5]
N-307-2 [T5]
N-307-3 [T1]
N-308 [T3]
N-311 [T1]
N-322 [T1]
N-323-1 [T1]
N-334 [T1]
N-335 [T5]
N-335-1 [T3]
N-343 [T3]
N-355 [T3]
N-356 [T3]
N-375 [T5]
N-375-1 [T5]
N-375-2 [T3]N-389 [T5]N-389-1 [T3]
N-401 [T5]
N-401-1 [T3]
N-402 [T5]
N-402-1 [T3]
N-406 [T3]
N-408 [T5]
N-408-1 [T5]
N-408-2 [T5]
N-408-3 [T3]
N-409 [T5]
N-409-1 [T5]
N-409-2 [T5]
N-409-3 [T3]
N-415 [T3]
N-416 [T5]
N-416-1 [T5]
N-416-2 [T5]
N-416-3 [T1]
N-419 [T3]
N-424 [T3]
N-426 [T3]
N-427 [T3]
N-429 [T5]
N-429-1 [T5]
N-429-2 [T3]
N-432 [T5]
N-432-1 [T1]
N-435 [T5]
N-435-1 [T1]
N-436 [T5]
N-436-1 [T3]
N-437 [T3]
N-444 [T3]
N-445 [T3]
N-446 [T3]
N-448 [T3]N-449 [T3]N-457 [T3]
N-458 [T5]
N-458-1 [T3]
N-460 [T1]
N-461 [T5]
N-461-1 [T3]
N-463 [T5]
N-463-1 [T3]
N-465 1 [T3]N-465-1 1N-471 [T1]
N-472 [T3]
N-473 1 [T3]N-473-1 1N-478 [T3]
N-479 [T5]
N-479-1 [T3]
N-480 1N-481 [T1]
N-485 [T5]
N-485-1 [T1]
N-489 [T3]
N-490 [T5]
N-490-1 [T1]
N-491 [T5]
N-491-1 [T5]
N-491-2 [T1]
N-494 [T5]
N-494-1 [T5]
N-494-2 [T5]
N-494-3 [T1]
N-495 [T3]
N-496 [T5]
N-496-1 [T3] [T5]
N-496-2 [T1]
N-498 [T5]
N-498-1 1 [T5]N-498-2 1 [T5]N-498-3 1 [T5]N-498-4 [T2]
N-503 [T1]
N-504 [T5]
N-504-1 [T5]
N-504-2 [T2]
N-508 [T5]
N-508-1 [T5]
N-508-2 [T1]
N-509 [T4]
N-512 [T5]
N-512-1 [T4]
N-513 [T5]
N-513-1 [T2]
N-514 [T3]
N-515 [T3]
N-516 [T5]
N-516-1 [T5]
N-516-2 [T5]
N-516-3 [T2]
N-517 [T5]
N-517-1 [T2]
N-521 [T3]
N-522 [T1]
N-523 [T5]
N-523-1 [T5]
N-523-2 [T1]
N-524 [T3]
N-526 [T1]
N-528 [T5]
N-528-1 [T2]
N-532 [T5]
N-532-1 [T2]
N-532-2 1N-533 [T5]
N-533-1 [T2]
N-534 [T1]
______________________
1Code case is unacceptable for use. See Revision 1 to Regulatory Guide 1.
193.2 Code case approved February 13, 2003, published in Supplements 8 and 9, 2001 Edition.
3 Code case approved May 21, 2003, published in Supplement 11, 2001 Edition.Appendix C to RG 1.147, Rev. 14, Page C-2N-535 [T3]N-537 [T1]
N-538 [T3]
N-541 [T3]
N-542 1N-543 [T3]
N-544 [T3]
N-545 [T1]
N-546 [T2]
N-547 1N-552 [T2]
N-553 [T5]
N-553-1 [T1]
N-554 [T5]
N-554-1 [T5]
N-554-2 [T2]
N-555 [T3]
N-556 [T3]
N-557 [T5]
N-557-1 [T2]
N-560 [T5]
N-560-1 1 [T5]N-560-2 1N-561 1 [T5]N-561-1 1N-562 1 [T5]N-562-1 1N-563 [T3]
N-566 [T5]
N-566-1 [T5]
N-566-2 [T1]
N-567 [T5]
N-567-1 [T2]
N-568 [T2]
N-569 [T5]
N-569-1 [T2]
N-573 [T1]
N-574 1N-575 1N-576 [T5]
N-576-1 [T2]
N-577 1 [T5]N-577-1 1N-578 1 [T5]N-578-1 1N-583 [T2]
N-586 [T1]
N-587 1N-588 [T1]
N-589 1N-589-1 1N-590 1N-591 1N-592 [T1]
N-593 [T2]
N-597 [T5]
N-597-1 [T2]
N-598 [T1]
N-599 [T2]
N-600 [T1]
N-601 [T1]
N-603 [T1]
N-604 [T1]
N-605 [T1]
N-606 [T5]
N-606-1 [T2]
N-609 [T1]
N-613 1N-613-1 [T1]
N-615 1N-616 [T2]
N-617 [T1]
N-619 [T2]
N-622 1N-623 [T1]
N-624 [T1]
N-627 [T3]
N-629 [T1]
N-630 [T4]
N-638 [T5]
N-638-1 [T2]
2N-639 [T2]
N-640 [T1]
N-641 [T1]
N-643 [T1]
N-647 [T2]
N-648 [T5]
N-648-1 [T2]
N-649 [T1]
N-651 [T1]N-652 [T1]N-653 1N-654 1N-658 [T1]
N-660 [T2]
N-661 [T2]
N-662 [T2]
N-663 [T1]
N-664 [T1]
N-695 3 [T1]