Regulatory Guide 1.147: Difference between revisions

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{{Adams
{{Adams
| number = ML040230509
| number = ML13350A192
| issue date = 01/31/2004
| issue date = 09/30/1985
| title = 3, Inservice Inspection Code Case Acceptability, ASME Section Xi, Division 1 (DG-1091)
| title = Inservice Inspection Code Case Acceptability ASME Section Xi Division 1
| author name =  
| author name =  
| author affiliation = NRC/RES
| author affiliation = NRC/RES
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| license number =  
| license number =  
| contact person =  
| contact person =  
| case reference number = DG-1091
| document report number = RG-1.147, Rev. 4
| document report number = RG-1.147
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 24
| page count = 5
}}
}}
{{#Wiki_filter:1 Copies 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.This guide was issued after consideration of comments received from the public.  Comments and suggestions for improvements in these guides areencouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new information or experience. Writtencomments may be submitted to the Rules and Directives Branch, ADM, U.S. Nuclear Regulatory Commission, DC 20555-0001.Regulatory guides are issued in ten 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.Single copies of regulatory guides (which may be reproduced) may be obtained free of charge by writing the Distribution Services Section, U.S. NuclearRegulatory Commission, Washington, DC 20555-0001, or by fax to (301)415-2289; or by email to DISTRIBUTION@NRC.GOV.  Electronic copies of thisguide are also available on the interent at NRC's web site at <WWW.NRC.GOV> in the Reference Library under Regulatory Guides.  This guide is alsoin the Electronic Reading Room at NRC's home page, along with other recently issued guides, Accession Number ML040230509.  U.S. NUCLEAR REGULATORY COMMISSION
{{#Wiki_filter:SRi.es1on498 September
Revision 13    January 2004 REGULATORY GUIDE   OFFICE OF NUCLEAR REGULATORY RESEARCHREGULATORY GUIDE 1.147Reprinted to(Draft was issued as DG-1091)correct page 14.INSERVICE INSPECTION CODE CASE ACCEPTABILITY,ASME SECTION XI, DIVISION 1
1985 .U.S. NUCLEAR REGULATORY  
COMMISSION'
REG ULATORY GUIDE OFFICE OF NUCLEAR REGULATORY  
RESEARCH REGULATORY
GUIDE 1.147 INSERVICE  
INSPECTION  
CODE CASE ACCEPTABILITY
ASME SECTION Xl DIVISION 1  


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion (GDC) 1, "Quality Standards and Records, " of Appendix A,"General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing ofProduction 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 andPressure Vessel (BPV) 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.  ASME standards committees develop, among other things, 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 participate in the ASME process, which helps to ensure that the various interests are considered.Section 50.55a(g), "Inservice Inspection Requirements," requires, in part, that Classes1, 2, 3, MC, and CC Components and their supports meet the requirements of Section XI,
Section50.55a, "Codes and Standards," of 10CFR Part 50, "Dom-stic licensing of Production and Utilization Facilities," requires, in part, that each operating license for a boiling or pressurized water-cooled nuclear power facility and each construction permit for a utilization facility be subject to the conditions in paragraph (g), "Inservice Inspec-tion Requirements," of &sect;50.55a. Paragraph (g) requires, in part, that Classes 1, 2, and 3 components and their supports meet the requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code or equivalent quality standards.
"Rules for Inservice Inspection of Nuclear Power Plant Components,"1 of the ASME BPV Codeor equivalent quality standards.  Every three years the ASME publishes a new edition of the
1.147-2BPV Code, including Section XI, and new addenda are published every year.  The latesteditions and addenda of Section XI that have been approved for use by the NRC are referenced in 10 CFR 50.55a(b).  The ASME also publishes Code Cases quarterly.  Code Cases provide alternatives to existing Code requirements that were developed and approved by the ASME.  This regulatory guide identifies the Code Cases that have been determined by the NRC to be acceptable alternatives to applicable parts of Section XI.  These Code Cases may be used by licensees without a request for authorization from the NRC, provided that they are used with any identified limitations or modifications.  Section XI Code Cases not yet endorsed by the NRC 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 Office of Nuclear Reactor Regulation.The ASME Code is incorporated by reference into 10 CFR 50.55a.  Code Casesapproved by the NRC provide an acceptable voluntary alternative to the mandatory ASME
Code provisions.  10 CFR 50.55a has been amended to incorporate this guide by reference and states the requirements governing the use of Code Cases.  Because of the continuing change in the status of Code Cases, periodic updates to 10 CFR 50.55a and this guide are planned to accommodate new Code Cases and any revisions of existing Code Cases.This regulatory guide would decrease the burden on licensees who choose to useASME Code Cases N-532-1 and N-573.  The public burden reduction for this information collection is estimated to average 32 hours per request.  Because the burden for this information collection is insignificant, Office of Management and Budget (OMB) clearance is not required.  Existing requirements were approved by OMB, approval number 3150-0011.  If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.


==B. DISCUSSION==
Paragraph
For Revision 13 to Regulatory Guide 1.147, the NRC staff reviewed the Section XICode Cases listed in Supplement 4 to the 1992 Edition through Supplement 11 to the 1998 Edition.  It should be noted that, in response to public comments, several later revisions to Code Cases contained in Supplement 12 to the 1998 Edition and Supplements 2 and 3 to the
50.SSa(b), in part, references the latest editions and addenda in effect of Section XI of the Code and any supplementary requirements to that section of the Code.Footnote 6 to &sect;50.55a states that the use of specific Code Cases may be authorized by the Commission upon request pursuant to paragraph
2001 Edition were adopted. Appendix A to this guide lists the supplements reviewed, the edition, supplement number, and the ASME
50.S5a(aX2)(ii), which requires that proposed alternatives to the described requirements or portions thereof provide an acceptable level of quality and safety.General Design Criterion I, "Quality Standards and Re-cords," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 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 function to be performed.
's Board on Nuclear Codes and Standardsapproval date.  Appendix B is a numerical list of the codes cases in these supplements. The guide lists Code Cases in four tables: Table 1, "Acceptable Section XI Code Cases," containsthe Code Cases that are acceptable to the NRC for implementation in the ISI of light-water- cooled nuclear power plants; Table 2, "Conditionally Acceptable Section XI Code Cases,"contains the Code Cases that are acceptable 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; Table 3, "Annulled Section XI Code Cases," contains theCode Cases that have been annulled by the ASME and may no longer be used once an ISI
program is updated; and Table 4, "Section XI Code Cases That Have Been Superseded," listsCode Cases that have been superseded through revision.  ASME Code Cases that the NRC
has determined to be unacceptable are listed in new Regulatory Guide 1.193, "ASME CodeCases Not Approved for Use.


"
Where generally recognized codes and standards are used, Criterion
1.147-3Code Cases provide alternatives to existing Code requirements that were developedand approved by the ASME.  The Code Cases listed as approved in Tables 1 and 2 of this guide have been incorporated by reference into 10 CFR 50.55a the.  These Code Cases may be used voluntarily by licensees as an alternative to compliance with ASME Code provisions incorporated by reference into 10 CFR 50.55a.10 CFR 50.55a requires that when a licensee initially implements a Code Case, themost recent version of that Code Case as listed in Tables 1 and 2 be implemented. If a Code Case is implemented by a licensee and a later version of the Code Case is incorporated by reference into 10 CFR 50.55a and listed in Tables 1 and 2 during the licensee
1 requires that they be identi-fied and evaluated to determine their applicability, adequacy, and sufficiency and be supplemented or modified as neces-sary to ensure a quality product in keeping with the required safety function.This regulatory guide lists those Section XI ASME Code.Cases that are generally acceptable to the NRC staff for Co t plu nay be obtained hom the American Society of Mechanical Enaimenr, United Englimeuing Center, 345 East 47th Street, New York, N.V. 10017.implementation in the inservice inspection of light-water- cooled nuclear power plants.Any information collection activities mentioned in this regu-latory guide are contained as requirements in 10 CFR Part 50, which provides the regulatory basis for this guide. The informa-tion collection requirements in 10 CFR Part 50 have been cleared under OMB Clearance No. 3150-0011.
's present120-month ISI program interval, that licensee could 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 which is necessary, for example, to enhance safety.  Licensees who choose to continue use of the Code Case during the subsequent 120-month ISI program interval 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 incorporatedinto the Code, the application for which it was specifically developed no longer exists, or experience has shown that an examination or testing method is no longer inadequate. After a Code Case is annulled and 10 CFR 50.55a and this guide are amended, 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 (i.e., 10 CFR 50.109).With regard to the use of any Code Case, it is the responsibility of the user to makecertain that the provisions of the Code Case do not conflict with regulatory requirements or licensee commitments.
==B. DISCUSSION==
 
The ASME Boiler and Pressure Vessel Committee pub-lishes a document entitled "Code Cases."' Generally, the individual Code Cases that make up this document explain the intent of Code rules or provide for alternative requirements under special circumstances.
==C. REGULATORY POSITION==
1. ACCEPTABLE SECTION XI CODE CASESThe Code Cases listed in the table below are acceptable to the NRC for application in licensees' Section XI inservice inspection programs.  The ASME issues a new edition ofSection XI every three years, and supplements to the edition containing Section XI Code Cases are published quarterly.  Hence, there are 12 supplements to each edition.  Column 3 of Table 1 lists the supplement and edition in which each Code Case was published (e.g., 7/95E
means Code Case Supplement 7 to the 1995 Edition).
1.147-4TABLE 1 - ACCEPTABLE SECTION XI CODE CASESCODE CASENUMBERTABLE 1, ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITIONN-198-1Exemption from Examination for ASME Class 1 and 2 PipingLocated at Containment Penetrations, Section XI, Division 112/95EN-307-2Revised Ultrasonic Examination Volume for Class 1 Bolting,Table IWB-2500-1, Examination Category B-G-1, When the Examinations Are Conducted from the End of the Bolt or Stud or from the Center-Drilled Hole, Section XI, Division 16/98EN-311Alternative Examination of Outlet Nozzle on Secondary Side ofSteam Generators, Section XI, Division 13/98EN-322Examination Requirements for Integrally Welded orForged Attachments to Class 1 Piping at Containment Penetrations, Section XI, Division 110/98EN-334Examination Requirements for Integrally Welded or ForgedAttachments to Class 2 Piping at Containment Penetrations, Section XI, Division 110/98EN-389-1Alternative Rules for Repairs, Replacements, or Modifications,Section XI, Division 1
3/98EN-408-3Alternative Rules for Examination of Class 2 Piping, Section XI, Division 1
4/98EN-432Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding (GTAW) Temper Bead Technique, Section XI,
Division 1
10/98EN-435-1Alternative Examination Requirements for Vessels With Wall Thickness 2 in. Or Less, Section XI, Division 112/95EN-457Qualification Specimen Notch Location for UltrasonicExamination of Bolts and Studs, Section XI, Division 14/98EN-458-1Magnetic Particle Examination of Coated Materials, Section XI, Division 111/95EN-460Alternative Examination Coverage for Class 1 and Class 2Welds, Section XI, Division 19/98EN-461-1Alternative Rules for Piping Calibration Block Thickness,Section XI, Division 111/95EN-463-1Evaluation Procedures and Acceptance Criteria for Flaws inClass 1 Ferritic Piping That Exceed the Acceptance Standards of IWB-3514.2, Section XI, Division 112/95EN-471 Acoustic Emission for Successive Inspections,Section XI, Division 13/98E
CODE CASENUMBERTABLE 1, ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITION 1.147-5N-479-1Boiling Water Reactor (BWR) Main Steam Hydrostatic Test,Section XI, Division 13/98EN-481Alternative Examination Requirements for Cast AusteniticPump Casings, Section XI, Division 11/98EN-485-1Eddy Current Examination of Coated Ferritic Surfaces as anAlternative to Surface Examination, Section XI, Division 19/98EN-489Alternative Rules for Level III NDE Qualification Examinations,Section XI, Divisions 1, 2, and 34/98EN-490-1Alternative Vision Test Requirements for NondestructiveExaminers, Section XI, Divisions 1, 2, and 39/98EN-491-2Rules for Examination of Class 1, 2, 3, and MC ComponentSupports of Light-Water Cooled Power Plants, Section XI,
Division 19/98EN-494-3Pipe Specific Evaluation Procedures and Acceptance Criteriafor Flaws in Class 1 Ferritic Piping that Exceed the Acceptance Standards of IWB-3514.2 and in Class 1 Austenitic Piping that Exceed the Acceptance Standards of IWB-3514.3, Section XI,
Division 14/98EN-495Hydrostatic Testing of Relief Valves, Section XI, Division 13/98EN-503Limited Certification of Nondestructive Examination Personnel,Section XI, Division 1 Note: Because of the statistical screening criteria used for Appendix VIII to Section XI qualifications, this Code Case is not applicable to Appendix VIII, "Performance Demonstrationfor Ultrasonic Examination Systems.
 
"10/98EN-504-2Alternative Rules for Repair of Class 1, 2, and 3 AusteniticStainless Steel Piping, Section XI, Division 19/98EN-508-1Rotation of Serviced Snubbers and Pressure Relief Valves forthe Purpose of Testing, Section XI, Division 19/98EN-514Low Temperature Overpressure Protection,Section XI, Division 13/98EN-515Class 1 Mechanical Joint Pressure Tests, Section XI, Division 13/98EN-521Alternative Rules for Deferral of Inspections of Nozzle-to-Vessel Welds, Inside Radius Sections, and Nozzle-to-Safe End Welds of a Pressurized Water Reactor (PWR) Vessel, Section XI, Division 14/98EN-522Pressure Testing of Containment Penetration Piping,Section XI, Division 13/98E
CODE CASENUMBERTABLE 1, ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITION 1.147-6N-523-2Mechanical Clamping Devices for Class 2 and 3 Piping,Section XI, Division 111/98EN-524Alternative Examination Requirements for Longitudinal Weldsin Class 1 and 2 Piping, Section XI, Division 14/98EN-526Alternative Requirements for Successive Inspections ofClass 1 and 2 Vessels, Section XI, Division 16/98EN-534Alternative Requirements for Pneumatic Pressure Testing,Section XI, Division 110/98EN-535Alternative Requirements for Inservice Inspection Intervals,Section XI, Division 111/95EN-537Location of Ultrasonic Depth-Sizing Flaws, Section XI, Division 111/95EN-538Alternative Requirements for Length Sizing PerformanceDemonstration in Accordance with Appendix VIII,
Supplements 2, 3, 10, 11, and 12, Section XI, Division 16/98EN-541Alternative Requirements for Performance Demonstration inAccordance with Appendix VIII, Supplements 4 and 6, Section XI, Division 112/95EN-543 Alternative to Performing Periodic Calibration Checks,Section XI, Division 11/98EN-544Repair/Replacement of Small Items, Section XI, Division 11/98EN-545Alternative Requirements for Conduct of PerformanceDemonstration Detection Test of Reactor Vessel, Section XI,
Division 11/98EN-553Inservice Eddy Current Surface Examination of PressureRetaining Pipe Welds and Nozzle-to-Safe End Welds, Section XI, Division 13/98EN-555Use of Section II, V, and IX Code Cases, Section XI, Division 13/95EN-556Alternative Requirements for Verification of Acceptability ofReplacements, Section XI, Division 14/98EN-563Grading of Examinations, IWA-2320, Section XI, Division 14/98EN-566-1Corrective Action for Leakage Identified at Bolted Connections,Section XI, Division 13/98EN-573Transfer of Procedure Qualification Records Between Owners,Section XI, Division 18/95EN-588Attenuation to Reference Flaw Orientation of Appendix G forCircumferential Welds in Reactor Vessels, Section XI,
Division 19/98E
CODE CASENUMBERTABLE 1, ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITION 1.147-7N-592ASNT Central Certification Program, Section XI, Division 111/95EN-598Alternative Requirements to Required Percentages ofExaminations, Section XI, Division 112/95EN-601Extent and Frequency of VT-3 Visual Examination for InserviceInspection of Metal Containments, Section XI, Division 112/95EN-603Alternative to the Requirements of IWL-2421, Sites with TwoPlants, Section XI, Division 112/95EN-604Alternative to Bolt Torque or Tension Test Requirements ofTable IWE-2500-1, Category E-G, Item E8.20, Section XI,
Division 12/98EN-605Alternative to the Requirements of IWE-2500(c) [sic, shouldstate WE-2500(b)] for Augmented Examination of Surface Areas, Section XI, Division 1
[Note: Draft Regulatory Guide DG-1070, 
"Sampling PlansUsed for Dedicating Simple Metallic Commercial Grade Items for Use in Nuclear Power Plants," is being developed toprovide acceptable guidelines for sampling criteria.]12/95EN-609Alternative Requirements to Stress-Based Selection Criteria forCategory B-J Welds, Section XI, Division 12/98EN-617Alternative Examination Distribution Requirements for TableIWC-2500-1, Examination Category C-G, Pressure Retaining Welds in Pumps and Valves, Section XI, Division 13/98EN-623Deferral of Inspections of Shell-to-Flange and Head-to-FlangeWelds of a Reactor Vessel, Section XI, Division 14/98EN-624Successive Inspections, Section XI, Division 18/98EN-627VT-1 Visual Examination in Lieu of Surface Examination forRPV Closure Nuts, Section XI, Division 15/98EN-629Use of Fracture Toughness Test Data to Establish ReferenceTemperature for Pressure Retaining Materials, Section XI,
Division 15/98EN-638Similar and Dissimilar Metal Welding Using AmbientTemperature Machine GTAW Temper Bead Technique, Section XI, Division 16/98EN-640Alternative Reference Fracture Toughness for Development ofP-T Limit Curves, Section XI, Division 14/98EN-641Alternative Pressure-Temperature Relationship and LowTemperature Overpressure Protection System Requirements, Section XI, Division 18/98E
CODE CASENUMBERTABLE 1, ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITION 1.147-8N-643Fatigue Crack Growth Rate Curves for Ferritic Steels in PWRWater Environment, Section XI, Division 110/98E2. CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESThe Code Cases listed in Table 2 below are acceptable to the NRC for application in licensees' Section XI inservice inspection programs within the limitations imposed by the NRCstaff.  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 three years, and the ASME issues Section XI Code Cases quarterly in supplements to a specific edition.  Hence, there are 12 supplements to each edition.  Column 3 of the table lists the supplement and edition in which each Code Case was published (e.g., 7/95E means Code Case Supplement 7 to the 1995 Edition).TABLE 2, CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESCODE CASENUMBERTABLE 2, CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITIONCONDITIONN-416-2Alternative Pressure Test Requirement for Welded Repairs orInstallation of Replacement Items by Welding, Class 1, 2, and 3, Section XI, Division 19/98EThe provisions of IWA-5213, "Test Condition Holding Times,"1989 Edition, are to be used.
 
CODE CASENUMBERTABLE 2, CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITIONCONDITION 1.147-9N-498-4Alternative Requirements for 10-Year System HydrostaticTesting for Class 1, 2, and 3 Systems, Section XI, Division 13/98EThe provisions of IWA-5213, "Test Condition Holding Times,"1989 Edition, are to be used.N-512-1Assessment of Reactor Vessels With Low Upper Shelf CharpyImpact Energy Levels, Section XI, Division 11/98EThe material properties and transient selection must follow theguidance in Regulatory Guide 1.161, "Evaluation of ReactorPressure Vessels with Charpy Upper-Shelf Energy Less Than
50 Ft-lb," or an equivalent method approved by the NRC staff.N-513Evaluation Criteria for Temporary Acceptance of Flaws in Class3 Piping, Section XI, Division 110/98E(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 welds for leakage prevention (through seal weld leakage is not a structural flaw; thread integrity must be maintained).
(d) Degraded socket welds.N-516-2Underwater Welding, Section XI, Division 18/98ELicensees must obtain NRC approval in accordance with 10CFR 50.55a(a)(3) regarding the technique to be used in the weld repair or replacement of irradiated material underwater.N-517-1Quality Assurance Program Requirements for Owners,Section XI, Division 12/98EThe Owner's Quality Assurance (QA) Program that is approvedunder Appendix B to 10 CFR Part 50 must address the use of this Code Case and any unique QA requirements identified by the Code Case that are not contained in the owner
's QAProgram description.  This would include the activities performed in accordance with this Code Case that are subject to monitoring by the Authorized Nuclear Inspector.
 
CODE CASENUMBERTABLE 2, CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITIONCONDITION 1.147-10N-528-1Purchase, Exchange, or Transfer of Material Between NuclearPlant Sites, Section XI, Division 15/98EThe requirements of 10 CFR Part 21 are to be applied to thenuclear plant site supplying the material as well as to the nuclear plant site receiving the material that has been purchased, exchanged, or transferred between sites.N-532-1Alternative Requirements to Repair and ReplacementDocumentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000, Section XI, Division 112/98ECode Case N-532-1 requires an Owner
's Activity Report FormOAR-1 to be prepared and certified upon completion of each refueling outage.  The OAR-1 forms must be submitted to the NRC within 90 days of the completion of the refueling outage.N-533-1Alternative Requirements for VT-2 Visual Examination of Class1, 2, and 3 Insulated Pressure-Retaining Bolted Connections, Section XI, Division 14/98EPrior to conducting the VT-2 examination, the provisions ofIWA-5213, "Test Condition Holding Times," 1989 Edition, are tobe followed.N-546Alternative Requirements for Qualification of VT-2 ExaminationPersonnel, Section XI, Division 11/98E(1) Qualify examination personnel by test to demonstrateknowledge of Section XI and plant specific procedures for VT-2 visual examination.
 
(2) Requalify examination personnel by examination every three years.


(3)  This code case is applicable only to the performance of VT-2 examinations and may not be applied to other VT-2 functions such as verifying the adequacy of procedures and training VT-2 personnel.
Most Code Cases are eventually superseded by revision of the Code and tben are annulled by action of the ASME Council.In such instances, the intent of the annulled Code Case becomes part of the revised Code, and therefore continued use of the Code Case intent is sanctioned under the rules of the Code. In other instances, the Code Case is annulled because it is no longer acceptable or there is no further requirement for it. A Code Case that was approved for a particular situation and not for a generic application shuld be used only for the approved situation because annulment of such a Code Case could result in situations that would not meet Code requirements.


CODE CASENUMBERTABLE 2, CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITIONCONDITION 1.147-11N-552Alternative Methods - Qualification for Nozzle Inside RadiusSection from the Outside Surface, Section XI, Division 13/98ETo achieve consistency with the 10 CFR 50.55a rule changepublished September 22, 1999 (64 FR 51370), incorporating Appendix 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 setmust be cracks and the maximum misorientation must be demonstrated with cracks.  Flaws in nozzles with bore diameters equal to or less than 4 inches may be notches.Add to detection criteria, "The number of false calls must notexceed three.
The ASME considers the use of Code Cases to be optional for the user and not a mandatory requirement.


"  N-554-2Alternative Requirements for Reconciliation of ReplacementItems and Addition of New Systems, Section XI, Division 19/98EThe component used for repair/replacement must bemanufactured, procured, and controlled as a safety-related component under an NRC-approved Quality Assurance program meeting the requirements of Appendix B to 10 CFR Part 50.N-557-1In-Place Dry Annealing of a PWR Nuclear Reactor Vessel,Section XI, Division 14/98EThe secondary stress allowable of 3S
The Code Cases listed in this guide are limited to those cases applicable to Section XI of the Code.All published Code Cases that are applicable to Section XI of the Code and were in effect on July 12, 1984, were reviewed for inclusion in this guide. Code Cases that are not listed herein are either not endorsed or will require supple-.mentary provisions on an individual plant basis to attain endorselnent status.*Lines indicate substanilve changes from Revision
m, shown in Figure 1 of theCode Case, must be applied to the entire primary plus secondary stress range during the anneal.N-567-1Alternative Requirements for Class 1, 2, and 3 ReplacementComponents, Section XI, Division 14/98EThe component used for repair/replacement must have beenmanufactured, procured, and controlled as a safety-related component under an NRC-approved Quality Assurance program meeting the requirements of Appendix B to 10 CFR Part 50.


CODE CASENUMBERTABLE 2, CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITIONCONDITION 1.147-12N-568Alternative Examination Requirements for Welded Attachments,Section XI, Division 18/98EThis Code Case may only be used for examination of theaccessible portions of lugs on piping where riser clamps (i.e.,
===3. USNRC REGULATORV ===
clamps on vertical runs of pipe) obstruct access to welded surfaces.N-569-1Alternative Rules for Repair by Electrochemical Deposition ofClass 1 and 2 Steam Generator Tubing, Section XI, Division 15/98ENOTES:  Steam generator tube repair methods require priorNRC approval through the Technical Specifications.  This Code Case does not address certain aspects of this repair, e.g., the qualification of the inspection and plugging criteria necessary for staff approval of the repair method.  In addition, if the user plans to "reconcile," as described in Footnote 2,  the reconciliation is to be performed in accordance with IWA-4200 in the 1995 Edition,
GUIDES Regulatory Guides are Issued to describe and make available to the public methods acceptable to the NRC staff of Implementing specfic -parts of the Commission's regulations, to delineate tech.niques ue by the staff In evaluating
1996 Addenda of ASME Section XI.N-576-1Repair of Class 1 and 2 SB-163, UNS N06600 Steam GeneratorTubing, Section XI, Division 15/98ENOTES:  Steam generator tube repair methods require priorNRC approval through the Technical Specifications.  This Code Case does not address certain aspects of this repair, e.g., the qualification of inspection and plugging criteria necessary for staff approval of the repair method.  In addition, if the user plans to "reconcile," as described in the footnote, the reconciliation is to be performed in accordance with  IWA-4200 in the 1995 Edition, 1996 Addenda of ASME Section XI.N-583Annual Training Alternative, Section XI, Division 110/98E(1) Supplemental practice shall be performed on material orwelds that contain cracks, or by analyzing prerecorded data from material or welds that contain cracks.
$Pecific problems or postu-lated aUcidents, or to provide guidance to applicants.


(2) The training must be completed no earlier than 6 months prior to performing ultrasonic examinations at a licensee
Regulatory
'sfacility.
-Guides are not substitutes for regulations, and compliance.


CODE CASENUMBERTABLE 2, CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITIONCONDITION 1.147-13N-586Alternative Additional Examination Requirements for Class 1, 2,and 3 Piping, Components, and Supports, Section XI, Division 15/98EThe engineering evaluations addressed under Item (a) and theadditional examinations addressed under Item (b) shall be performed during this outage.  If the additional examinations performed under Item (b) reveal indications exceeding the applicable acceptance criteria of Section XI, the engineering evaluations and the examinations shall be further extended to included additional evaluations and examinations at this outage.N-593Alternative Examination Requirements for Steam GeneratorNozzle to Vessel Welds, Section XI, Division 111/98EEssentially 100 percent (not less than 90 percent) of theexamination volume A-B-C-D-E-F-G-H must be inspected.N-597-1Requirements for Analytical Evaluation of Pipe Wall Thinning,Section XI, Division 12/01E(1) Code Case must be supplemented by the provisions of EPRINuclear Safety Analysis Center Report 202L-R2, April 1999,
with the'l Is not required.
"Recommendations for an Effective Flow Accelerated Corrosion Program," for developing the inspection requirements, the method of predicting the rate of wall thickness loss, and the value of the predicted remaining wall thickness.  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 which this Code Case are applied must be repaired or replaced in accordance with the construction code of record and Owner
Methods and solutions different from those set*out, n the guid~es will! be acceptable If they. provide a basis for the findings.'requisite to the issuance or continuance of a permit or..license by the Commission.
'srequirements or a later NRC approved edition of Section III of the ASME Code prior to the value of t p reaching the allowableminimum wall thickness, tmin, as specified in -3622.1(a)(1) of thisCode Case. Alternatively, use of the Code Case is subject to NRC review and approval.


(3)  For Class 1 piping not meeting the criteria of  -3221, the use of evaluation methods and criteria is subject to NRC review and approval.
This guide was Issued after consideration of comments received from the public. Comments and suggestions for Improvements In these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect now Informo-tio0n1or experience.


(4)  For those components that do not require immediate repair or replacement, the rate of wall thickness loss is to be used to determine a suitable inspection frequency so that repair or replacement occurs prior to reaching allowable minimum wall thickness, tmin.
l .e Comments should be sent-to the Secretary of the Commission, U.S. Nuclear Regulatory Commissionn, DC 20555,-Attontlons Docketing and Service 8rancnr--..I
The guides are Issued In the following ten broad dl&#xa5;visonsi..
1. Power Reactors 6. Products 2. Research and Test Reactors


CODE CASENUMBERTABLE 2, CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITIONCONDITION 1.147-14N-597-1(continued)Requirements for Analytical Evaluation of Pipe Wall Thinning,Section XI, Division 12/01E(5) For corrosion phenomenon other than flow acceleratedcorrosion, use of the Code Case is subject to NRC review and approval. Inspection plans and wall thinning rates may be difficult to justify for certain degradation mechanisms such as MIC and pitting.N-599Alternatives to Qualification of Nondestructive ExaminationPersonnel for Inservice Inspection of Metal (Class MC) and Concrete (Class CC) Containments, Section XI, Division 12/98EThis Code Case may not be used when a licensee updates tothe 1992 or later Edition of Section XI that requires the use of ANSI/ASNT CP-189, "Standard for Qualification and Certificationof Nondestructive Testing Personnel.
===7. Transportation===
3. Fuels and Materials Facilities
8. Occupational Health.4. Environmental end Siting 9. Antitrust and Flnanclal Review 5.. Materials and Plant Protection
10. General -.............
Copies of Issued guides may be purchaseda t thecurrent Goverpment Prlntlna Office price. A subscription service for future uldes In wr.cific d vislons Is available through the Government PKnting Of C&information on the subscription servIce and current 0POrices mae be obtained by writing the Superintendent of ?ocument=
Un, Government Printing Office, Post Off0 e Box '3702, shlngton, DC 20013-7082.


"N-606-1Similar and Dissimilar Metal Welding Using AmbientTemperature Machine GTAW Temper Bead Technique for BWR
F2 '.'~
CRD Housing/Stub Tube Repairs, Section XI, Division 16/98EPrior to welding, an examination or verification must beperformed to ensure proper preparation of the base metal, and that the surface is properly contoured so that an acceptable weld can be produced. The surfaces to be welded, and surfaces adjacent to the weld, are to be free from contaminants, such as, rust, moisture, grease, and other foreign material or any other condition that would prevent proper welding 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 ofClasses 1, 2, 3 Insulated Pressure Retaining Bolted Connections, Section XI, Division 16/98E(1) Insulation must be removed for VT-2 examination during thesystem pressure test for any 17-4 PH stainless steel of 410
The endorsement of a Code Case by this guide constitutes acceptance of its technical position for applications not precluded by regulatory or other requirements or by the recommendations in this or other regulatory guides. Con-tingent endorsement if applicable is indicated in regulatory position I for specific cases. However, it is the responsibil- ity of the user to make certain that no regulatory requirements are violated and that there are no conflicts with other recom-mended limitations resulting from Code Case usage.Acceptance or endorsement by the NRC staff applies only to those Code Cases or Code Case revisions with the date of "Council Approval" as shown in the regulatory position of this guide. Earlier or later revisions of a Code Case are not endorsed by this guide. New Code Cases will require evaluation by the NRC staff to determine if they qualify for inclusion in the approved list. Because of the con-tinuing change in the status of Code Cases, it is planned that this guide will require periodic updating to accommodate new Code Cases and any revision of existing Code Cases.C. REGULATORY
stainless steel stud or bolt aged at a temperature below 1100For with hardness above R
POSITION 1. The Section XI ASME Code Cases 2 listed below (by number, date of Council approval, 3 and title) are accept-able to the NRC staff for application in the inservice inspection of components and their supports for water-cooled nuclear power plants. Their use is acceptable within the limitations stated in the "Inquiry" and "Reply" sec-tions of each individual Code Case, within the limitations of such NRC or other requirements as may exist, and within the additional limitations recommended by the NRC staff and given with the individual Code Case in the list.1551 11/6/72 Inservice Inspection of Welds on N-34 11/20/78 Nuclear Components, Section X;the examination of clad surfaces of nozzles, including the inner surface of the nozzle-to-vessel insert welds.N-211 4  7/13/81 Recalibration of Ukrasonic Equip-ment Upon Change of Personnel, Section XI, Division I N-216 3/10/78 Alternate Rules for Reactor Vessel 7/13/81 Closure Stud Examination, Sco-Lion XI, Division 1 N-234 1/8/79 Time Between Ultrasonic Calibra-1/21/82 tion Checks, Section XI, Divi-sion I N-235 1/8/79 Ultrasonic Calibration Checks per 4/2/82 Section V, Section Xl, Division I N-236 1/8/79 Repair and Replacement of Class 1/21/82 MC Vessels, Section XI, Division I Code Case N-236 is acceptable subject to the following conditions in addition to those conditions specified in the Code Case:
c 30.(2) For A-286 stainless steel studs or bolts, the preload must be verified to be below 100 Ksi or the thermal insulation must be removed and the joint visually examined.


(3) For nuts conforming to SA-194, removal of the insulation for visual inspection is not necessary.
====a. In paragraph ====
1.0(a), second sentence -the phrase,"while the plant is not in service," refers to a refueling outage.


(4) Prior to conducting the VT-2 examination, the provisions of IWA-5213, "Test Condition Holding Times," 1989 Edition, are tobe followed.
====b. In paragraph ====
1.0(a), third sentence -the phrase,"the next scheduled plant outage," refers to the next scheduled refueling outage.For clarification, Repair and Replacement of Class MC Vessels means Repair and Replacement of Class MC Vessels and Components (systems).
Acceptance of this Code Case in no way infers NRC approval to violate the technical specification or any NRC require-ments with regard to breach of containment during repair and replacement procedures while the plant is in operation.


CODE CASENUMBERTABLE 2, CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITIONCONDITION 1.147-15N-619Alternative Requirements for Nozzle Inner Radius Inspections forClass 1 Pressurizer and Steam Generator Nozzles, Section XI,
Where a numbered Code paragraph is not identified by a particular edition of the Code, the Code in effect at the time of the ASME meeting (11/3/78)  
Division 13/98EIn lieu of a UT examination, licensees may perform a visualexamination with enhanced magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio.  The provisions of Table IWB-2500-1, Examination Category B-D, continue to apply except that, in place of examination volumes, the surfaces to be examined are the external surfaces shown in the figures applicable to this table.N-630Alternatives to VT-1C and VT-3C Visual Examination forInservice Inspection of Concrete and VT-1 Visual Examination for Inservice Inspection of Anchorage Hardware and Surrounding Concrete for Concrete Containments, Section XI,
that approved the Code Case should be governing.
Division 15/98EThe Responsible Engineer
's written practice must definequalification requirements for concrete and tendon hardware examination personnel in accordance with IWA-2300 in lieu of the Owner defined qualification requirements specified in Paragraph (c) of the Code Case.  However, limited certification in accordance with IWA-2350 is permitted.N-639Alternative Calibration Block Material, Section XI, Division 16/98EChemical ranges of the calibration block may vary from thematerials specification if: (1) the calibration block material is produced under an accepted industry specification or standard, and (2) the phase and grain shape are maintained in the same ranges produced by the thermal process required by the material specification.N-647Alternative to Augmented Examination Requirements ofIWE-2500, Section XI, Division 111/98EA VT-1 examination is to be used in lieu of the
"detailed visualexamination.


"  [Note: Draft Regulatory Guide DG-1070,"Sampling Plans Used for Dedicating Simple MetallicCommercial Grade Items for Use in Nuclear Power Plants," isbeing developed to provide acceptable guidelines for sampling criteria.]
N-278 3/17/80 Alternative Ultrasonic Calibration
CODE CASENUMBERTABLE 2, CONDITIONALLY ACCEPTABLE SECTION XI CODE CASESSUPPLEMENT/EDITIONCONDITION 1.147-16N-648-1Alternative Requirements for Inner Radius Examination ofClass 1 Reactor Vessel Nozzles, Section XI Division 103/01In place of a UT examination, licensees may perform a visualexamination with enhanced magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio.  The provisions of Table IWB-2500-1, Examination Category B-D, continue to apply except that, in place of examination volumes, the surfaces to be examined are the external surfaces shown in the figures applicable to this table.3. ANNULLED CODE CASESTable 3 lists the Section XI Code Cases contained in Supplement 4 to the 1992 Editionthrough Supplement 11 to the 1998 Edition that were annulled by the ASME.TABLE 3, ANNULLED SECTION XI CODE CASESCODE CASENUMBERTABLE 3,ANNULLED SECTION XI CODE CASESANNULMENTDATE(SUPPLEMENT/EDITION)N-98Ultrasonic Examination - Calibration Block Tolerances,Section XI, Division 18/9/96(6/95E)N-113-1Basic Calibration Block for Ultrasonic Examination ofWeld 10 in. To 14 in. Thick, Section XI, Division 18/9/96(6/95E)N-211Recalibration of Ultrasonic Equipment Upon Change ofPersonnel, Section XI, Division 14/30/96(5/95E)N-235 Ultrasonic Calibration Checks per Section V, Section XI, Division 18/9/96(6/95E)N-236-1Repair and Replacement of Class MC Vessels,Section XI, Division 18/5/97(9/95E)N-335-1Rules for Ultrasonic Examination of Similar and DissimilarMetal Piping Welds, Section XI, Division 15/11/97(9/95E)N-355Calibration Block for Angle Beam Ultrasonic Examinationof Large Fittings in Accordance with Appendix III-3410,
3/17/835 Block Configuration
Section XI, Division 18/9/96(6/95E)N-356Certification Period for Level III NDE Personnel,Section XI, Division 18/5/97(9/95E)
1-3131 and 5/25/83' T-434.3I Section XI, Division I Code Case N-278 is acceptable subject to the following conditions in addition to those conditions specified in the Code Case: When a universal calibration block is 4 The Code Case was annulled on no081 (ASME mandatory annulment date). It was reinstated on 1/13151. Because there was no change In the Code Case, the NRC considers that the Case was in effect during the period 3120/81 through 7/13/81.SCode Case N-278 was inadvertently allowed to expire because of an ASME administrative error on 3/17/83, Its mandatory amendment date. The Code Case without any technical changes was reinstated on 5/25183. Because of these circumstances, the Code Case Is considered to be in effect during that period of time.1705-1 3/1/76 N-98 11/20/78 1/21/82 Ultrasonic Examination- Calibra-tion Block Tolerances, Section XI N-I 13-1 12/13/82 Basic Calibration Block for Ultra-sonic Examination of Welds 10 in. to 14 in. Thick, Section XI, Diviwsin I 1738 12/22/75 N-118 11/20/78 1/21/82 Examination  
CODE CASENUMBERTABLE 3,ANNULLED SECTION XI CODE CASESANNULMENTDATE(SUPPLEMENT/EDITION)1.147-17N-401-1Eddy Current Examination, Section XI, Division 15/11/97(8/95E)N-402-1Eddy Current Calibration Standards, Section XI, Division 15/11/97(8/95E)N-409-3Procedure and Personnel Qualification Requirements forUltrasonic Detection and Sizing of Flaws in Piping Welds, Section XI, Division 14/30/96(5/95E)N-415Alternative Rules for Testing Pressure Relief, Section XI, Division 18/14/94(10/92E)N-419Extent of VT-1 Examinations, Category B-G-1 of TableIWB-2500-1, Section XI, Division 15/13/94(9/92E)N-426Extent of VT-1 Examinations, Category B-G-2 of TableIWB-2500-1, Section XI, Division 15/13/94(9/92E)N-427Code Cases in Inspection Plans, Section XI, Division 112/16/94(11/92E)N-429-1Alternative Rules for Ultrasonic Instrument Calibration,Section XI, Division 17/27/95(1/95E)N-437Use of Digital Readout and Digital Measurement Devicesfor Performing Pressure Tests, Section XI, Division 17/27/95(1/95E)N-448Qualification of VT-2 and VT-3 Visual ExaminationPersonnel, Section XI, Division 14/30/96(5/95E)N-449Qualification of VT-4 Visual Examination Personnel,Section XI, Division 14/30/96(5/95E)N-472Use of Digital Readout and Digital Measurement Devicesfor Performing Pump Vibration Testing, Section XI,
-Acceptance Stand-ards for Surface Indications in Cladding, Section XI Code Case 1738 (N-118) is acceptable subject to the following condition in addition to those conditions specified in the Code Case. The last sentence of the"Reply" should be replaced with the following:
Division 18/14/97(10/95E)N-473Alternative Rules for Valve Testing, Section XI, Division 112/16/94(11/92E)N-478Inservice Inspection for Class CC Concrete Componentsof Light-Water Cooled Power Plants, Section XI,
The provisions of this Code Case may not be applied for 2A numerical listing of the Code Cases appears In the appendix.3When more than one date Is given, the earlier date Is that on which the Code Case was approved by the ASME Council, and the later date (or dates) Is that on which the Code Case was reaffirmed by the ASME Council.1.147-2 used and some or all of the reference holes are larger than the reflector holes at comparable depths recom-mended by Article IV,'Section V, 1980 edition of the ASM. Code, a correction factor should be used to adjust the DAC level to compensate for the larger reflector holes. Also, if the reactor pressure vessel was previously examined by using a conventional block, a ratio between the DAC curves obtained from the two blocks should be noted (for reference)
Division 13/2/98(12/95E)N-496-1Helical-Coil Threaded Inserts, Section XI, Division 15/11/97(8/95E)N-509Alternative Rules for the Selection and Examination ofClass 1, 2, and 3 Integrally Welded Attachments, Section XI, Division 15/20/01(1/98E)
with the significant indication data.N-306 1/15/81 Calibration Block Material Selec-* 4/5/84 tion, Appendix 1, 1-3121, Sec-tion XlI Division 1 N-307 1/15/81 Revised Ultrasonic Examination
1.147-184. CODE CASES THAT HAVE BEEN SUPERSEDEDTable 4 lists Code Cases that have been superseded by revised Code Cases. Column 3indicates the date on which each Code Case was superseded as well as whether it was approved in a previous version of this guide, the supplement in which the Code Case was reaffirmed, and the date that the ASME approved the revised Code Case. Note:  Some of these Code Cases were not approved for use by the NRC in previous versions of Regulatory Guide 1.147.TABLE 4 - SECTION XI CODE CASES THAT HAVE BEEN SUPERSEDEDCODE CASENUMBERTABLE 4, SECTION XI CODE CASESTHAT HAVE BEEN SUPERSEDEDDATEN-307-1Revised Ultrasonic Examination Volume for Class1 Bolting, Table IWB-2500-1, Examination Category B-G-1, When the Examinations Are Conducted from the Center-Drilled Hole, Section XI, Division 1Approved Rev. 12;Reaffirmed 4/98E;
4/5/84 Volume for Class I Bolting, Examination Category B-G-I, Division i, When the Examina-tions Are Conducted from the Center-Drilled Hole N-308 9/30/81 Documentation of Repairs and Replacements of Components in Nuclear Power Plants,.Section Xl, Division I N-311 5/11/81 Alternate Examination of Outlet* I 4/5/84 Nozzle on Secondary Side of Steam Generators, Section XI, Division 1 Code Case N-311 is acceptable subject to the following condition in addition to those conditions specified in the Code Case: The applicant should indicate in the Safety Analysis Report that the stress analysis of the nozzle inside-comer region meets the Code Case stipulations for the state of stress in this region.N-335 4/2/82 Rules for Ultrasonic
N-307-2 Published on9/24/99N-408-2Alternative Rules for Examination of Class 2Piping, Section XI, Division 1Approved Rev. 11;Reaffirmed 8/95E;
)-Iamina-tion of Similar and Dissimilar Metal Piping Welds, Section XI, Division I N-343 4/2/82 Alternate Scope of Examination of Attachment Welds for Exami-nation Categories B-H, B-K-I, and C-C, Section Xl, Division I N-355 7/16/82 Calibration Block for Angi Beam Ultrasonic Examin, of Large Fittings in Accorda, with .Appendix iii-3410, Sec.tion XI, Division 1'N-375-2 4/5/84 Rules for UltrasonicExamination of Bolts and Studs, Section Xl, Division I Code Case N-389 is acceptable subject to the following condition in addition to those conditions specified in the Code Case: Theapplicant should submit for approv-al the appropriate'edition and addenda of the Code that is to. be used for the repair, replacement, or modification before start of the work.N-401 2120/84 Eddy Current Examination, Sec-tion Xl, Division I N-402 2/20/84 'Eddy Current Calibration Stan-dard Material, Section XI, Divi-sion I N-406 4/5/84 Alternate Rules for Replace-ment, Section XI, Division .1 N-408 7/12184 Alternate Rules for Examination of Class 2 Piping,. Section -XI, Division 1 Code Case N-408 is acceptable subject to the following condition in addition to those conditions specified in the Code Case: The applicant for an operating license should define the Class 2 piping subject to volumetric and surface examination in the Preservice Inspection for determination of acceptability by the NRC staff.2. Code Cases that were endorsed by the NRC in a prior version of this guide and were later annulled by action of the ASME Council should be considered as deleted from the list of acceptable Code Cases as of the date of the AS4E Council.action that approved the annulment.
N-408-3 Published on8/9/93N-416-1Alternative Pressure Test Requirements forWelded Repairs or Installation of Replacement Items by Welding, Class 1, 2, and 3, Section XI,
Division 1Approved Rev. 12;Reaffirmed 8/92E;
N-416-2 Published on5/5/00N-458Magnetic Particle Examination of CoatedMaterials, Section XI, Division 1Approved Rev. 12;Reaffirmed 4/30/93 N-458-1 Published on3/14/95N-461Alternative Rules for Piping Calibration BlockThickness, Section XI, Division 1Approved Rev. 12;Reaffirmed 4/30/93 N-461-1 Published on3/14/95N-465Alternative Rules for Pump Testing, Section XI, Division 1Approved Rev. 12;Annulled 10/92E;
N-465-1 Published on8/14/97N-491-1Alternative Rules for Examination of Class 1, 2, 3,and MC Component Supports of Light-Water Cooled Power Plants, Section XI, Division 1Approved Rev. 12;Reaffirmed 5/95E;
N-491-2 Published on3/12/97N-494-2Pipe Specific Evaluation Procedures andAcceptance Criteria for Flaws in Class 1 Ferritic Piping that Exceed the Acceptance Standards of IWB-3514.2, Section XI, Division 1Approved Rev. 12;Published 7/92E;
N-494-3 Published on8/9/96 CODE CASENUMBERTABLE 4, SECTION XI CODE CASESTHAT HAVE BEEN SUPERSEDEDDATE 1.147-19N-496Helical-Coil Threaded Inserts, Section XI, Division 1Approved Rev. 11;Reaffirmed 7/92E;
N-496-1 Published on5/11/94;N-496-1 Annulled on5/11/97N-498N-498-1 N-498-2 N-498-3Alternative Rules for 10-Year System HydrostaticTesting for Class 1, 2, and 3 Systems, Section XI,
Division 1Reaffirmed on 5/13/91Published 5/11/94Published 1/95E
Published 1/98EN-504-1Alternative Rules for Repair of Class 1, 2, and 3Austenitic Stainless Steel Piping, Section XI,
Division 1Approved Rev. 12;Published 6/92E;
N-504-2 Published on3/12/97N-508Rotation of Serviced Snubbers and PressureRelief Valves for the Purpose of Testing, Section XI, Division 1Published in 4/92E;
N-508-1 Published on5/11/94N-512Assessment of Reactor Vessels With Low UpperShelf Charpy Impact Energy Levels, Section XI,
Division 1Published in 4/92E;
N-512-1 Published on8/24/95N-516N-516-1Underwater Welding, Section XI, Division 1N-516 Approved Rev.  12;Reaffirmed 6/95E;
N-516-1 Published on12/31/96;N-516-2 Published on1/17/00N-517Quality Assurance Program Requirements forOwners, Section XI, Division 1Approved Rev. 12:Reaffirmed 8/95E;
N-517-1 Published on7/30/98N-523N-523-1Mechanical Clamping Devices for Class 2 and 3Piping, Section XI, Division 1Published 10/92E;
N-523-1 Published on8/24/95 N-523-2 Published on10/2/00N-528Purchase, Exchange, or Transfer of MaterialBetween Nuclear Plant Sites, Section XI,
Division 1Reaffirmed 10/95E;
N-528-1 Published on5/7/99N-532Alternative Requirements to Repair andReplacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-
6000, Section XI, Division 1Published 12/98E
CODE CASENUMBERTABLE 4, SECTION XI CODE CASESTHAT HAVE BEEN SUPERSEDEDDATE 1.147-20N-533Alternative Requirements for VT-2 VisualExamination of Class 1 Insulated Pressure- Retaining Bolted Connections, Section XI,
Division 1Reaffirmed 11/95E;
N-533-1 Published2/26/99N-554N-554-1Alternative Requirements for Reconciliation ofReplacement Items, Section XI, Division 1N-554 Reaffirmed 3/98E;
N-554-1 Published7/98E;N-554-2 Published on2/25/00N-557In-Place Dry Annealing of a PWR Nuclear ReactorVessel, Section XI, Division 1Published 4/95E;
N-557-1 Published on12/31/96N-560N-560-1Alternative Examination Requirements for Class 1,Category B-J Piping Welds, Section XI, Division 1N-560 Published 6/98E;N-560-1 Published 7/98E;
N-560-2 Published on3/28/00N-561Alternative Requirements for Wall ThicknessRestoration of Class 2 and High Energy Class 3 Carbon Steel Piping, Section XI, Division 1Published 7/95E;
N-561-1 Published on7/30/98N-562Alternative Requirements for Wall ThicknessRestoration of Class 3 Moderate Energy Carbon Steel Piping, Section XI, Division 1Published 7/95E;
N-562-1 Published on7/30/98N-566Corrective Action for Leakage Identified at BoltedConnections, Section XI, Division 1Published 6/98E;
N-566-1 Published on2/15/99N-567Alternative Requirements for Class 1, 2, and 3Replacement Components, Section XI, Division 1Published 10/95E;
N-567-1 Published on2/26/99N-569Alternative Rules for Repair by ElectrochemicalDeposition of Class 1 and 2 Steam Generator Tubing, Section XI, Division 1Published 6/95E;
N-569-1 Published on5/7/99N-576Repair of Class 1 and 2 SB-163, UNS N06600Steam Generator Tubing, Section XI, Division 1Published 8/95E;
N-576-1 Published on5/7/99N-577Risk-Informed Requirements for Class 1, 2, and 3Piping, Method A, Section XI, Division 1Published 10/95E;
N-577-1 Published on3/28/00N-578Risk-Informed Requirements for Class 1, 2, and 3Piping, Method B, Section XI, Division 1Published 10/95E;
N-578-1 Published on3/28/00N-606Similar and Dissimilar Metal Welding UsingAmbient Temperature Machine GTAW Temper Bead Technique, Section XI, Division 1Published 12/95E;
N-606-1 Published on9/24/99 CODE CASENUMBERTABLE 4, SECTION XI CODE CASESTHAT HAVE BEEN SUPERSEDEDDATE 1.147-21N-648Alternative Requirements for Inner RadiusExamination of Class 1 Reactor Vessel Nozzles, Section XI Division 1Published 11/98E
1.147-22APPENDIX ASUPPLEMENTS ADDRESSED IN PROPOSED REVISION 13TO REGULATORY GUIDE 1.147EDITIONSUPPLEMENTNUMBER BNCS a APPROVAL DATEOF CODE CASES INSUPPLEMENT
b19924February 12, 199319925April 27, 1993
19926August 9, 1993
19927December 9, 1993
19928February 15, 1994
19929May 11, 1994
199210August 5, 1994
199211December 12, 1994
199212March 14, 1995
19951June 9, 1995
19952August 24, 1995
19953December 12, 1995
19954March 19, 1996
19955May 24, 1996
19956August 9, 1996
19957December 31, 1996
19958March 12, 1997
19959May 26, 1997
199510August 14, 1997
199511December 12, 1997
199512March 2, 1998
19981May 20, 1998
19982July 30, 1998
19983February 15, 1999
19984February 26, 1999
19985May 7, 1999 EDITIONSUPPLEMENTNUMBER BNCS a APPROVAL DATEOF CODE CASES INSUPPLEMENT
b 1.147-2319986September 24, 199919987November 11, 1999
19988January 17, 2000
19989March 28, 2000
199810October 2, 2000
199811December 8, 2000
a   BNCS - ASME Board on Nuclear Codes and Standards b  Publication generally is 3 months after BNCS approval.


______________________
Such Code Cases that were annulled on or after November 1, 1978, are listed below by number, effective dates, 6 and title.1646 8/12/74 N-72 11/20/78 1/1181 1647 8/12/74 N-73 11/20178/l1/81 Partial Postponement of Category B-C Examination for Class I Com-ponents, Section XI Partial Postponement of Category B-D Examination for Class: I Components, Section XU 1730 11/3/75 Acceptance Standards for Class 2 N-112 7/1/79 and 3 Components, Section XI, Division I 1804 1/14/77 N-167 1/14/80 Minimum. Section Thickness Requirements for 'Repair -of: Nozzles, Section XI, Division 1 N-210 3/20/78 Exemption to Hydrostatic Tests 3/20/81, After Repairs; Section Xl, Divi-sion I N-389 7/25/83 Alternative Rules .for 1 Replacements, or Modiflc Oection XI, Division I: Repairs,' "Earle date-date Coda Came.was roved by -ASME Cowute"l ..cations, later date"d Code Coswa aweuned.l
1 Code Case is not acceptable for use.  See Regulatory Guide 1.193.
.mia than two dst__:a-.sr. the lat te date thaante Code n. = u. e. The n~iddle data (or dt) was thei te of reaffirma.tion of the Coe .Cas:.1.147-3! : ::'k I Code Case N-210 was acceptable subject to the follow.ing condition in addition to those conditions specified in the Code Cas


2 Code Case N-532-1 is listed in Supplement 12 to the 1998 Edition.
====e. Paragraph ====
(3) of the "Reply"should be replaced with the following:
Repairs to piping, pumps, and valves where the depth of the repaired cavity does not exceed 25 percent of the wall thickness.


3 Code Case N-597-1 is listed in Supplement 2 to the 2001 Edition.
N-21 1 3/20/78 Recalibration of Ultrasonic Equip-3/20/81 ment Upon Change of Personnel, Section XI, Division I N-2S2 11/19/79 Low Energy Capacitive Discharge 7/16/82 Welding Method for Temporary or Permanent Attachments to Components and Supports, Sec-tion III, Division 1, and XI Code Case N-252 was acceptable subject to the following condition in addition to those conditions specified in the Code Case: The applicant should indicate in the Safety Analysis Report the application, the material, and the thickness of the material to which the strain gage or thermocouple will be attached by CD welding.N-288 8/25/80 Hyrostatic lbst Requirements for 5/25/83 Class I and Class 2 Components, Section XI, Division I 3. Code Cases that were endorsed by the NRC in a prior version of this guide and were superseded by revised Code Cases on or after November 1, 1978, should be considered as not endorsed as of the date of the Council action that approv-ed the revised version of the Code Cases. These Code Cases that are no longer endorsed are listed in the following by number, effective dates, 7 and title.1731 11/3/75 Basic Calibration Block for Ultra-N- 113 11/20/78 sonic Examination of Welds 10in.1/21/82 to 13 in. Thick, Section XI, Divi-12/13/82 sion I 7 Earfler date-date Code Case was approved by ASME Council: later date-date revision of Code Case was appioved by ASMECouncil.


4 Code Case N-648-1 is listed in Supplement 3 to the 2001 Edition.
Where more than two dates atar, the tlat date Is the date on which the Code Case was revised.sTh middle date (or dates) was the date of reaffirmation of the Code Case.N-375s 8  2/14/83 Rules for Ultrasonic Examination
4/14/83 of Bolts and Studs, Section XI, Division I N-375-1 4/14/83 Rules for Ultrasonic Examina-4/5/84 tion of Bolts and Studs, Sec-tion XI, Division 1 4. Code Cases that are not on the approved list of this guide (paragraph C.I) or other regulatory guides, or for which authorization by the Commission has not been granted, are not acceptable on a generic basis.


25Appendix BNumerical Listing of Section XI Code Cases in Supplement 4, 1992 Edition, through Supplement 11, 1998 EditionN-98N-113-1 N-198-1 N-211 N-235 N-236-1 N-307-1 N-307-2 N-311 N-322 N-323-1 1N-334 N-335-1 N-356 N-389-1 N-401-1 N-402-1 N-408-2 N-408-3 N-409-3 N-415 N-416-1 N-416-2 N-419 N-426 N-427 N-429-1 N-432 N-435-1 N-437 N-448 N-449 N-457 N-458-1 N-460
==D. IMPLEMENTATION==
N-461-1 N-463-1 N-465 1N-465-1 1N-471 N-472 N-473 1N-473-1 1N-478N-479-1N-480 1N-481 N-485-1 N-489 N-490-1 N-491-1 N-491-2 N-494-2 N-494-3 N-495 N-496 N-496-1 N-498-1 N-498-2 1N-498-3 1N-498-4 N-503 N-504-1 N-504-2 N-508 N-508-1 N-509 N-512 N-512-1 N-513 N-514 N-515 N-516 N-516-1 N-516-2 N-517 N-517-1 N-521 N-522 N-523 N-523-1 N-523-2 N-524 N-526 N-528 N-528-1 N-532-1 2N-533N-533-1N-534 N-535 N-537 N-538 N-541 N-542 1N-543 N-544 N-545 N-546 N-547 1N-552 N-553 N-554 N-554-1 N-554-2 N-555 N-556 N-557 N-557-1 N-560
The purpose of this section is to provide information to applicants regarding the use of this regulatory guide.I. Except for those Code Cases that have been annulled by action of the ASME Council, the NRC staff will authorize appropriate use of the Code Cases listed in this guide under regulatory position 1 upon specific request by the applicant in accordance with footnote 6 to &sect;50.55a, the Codes and Standards rule. Code Cases that are actually used are to be identified in the Inservice Inspection Program.2. Code Cases to be applied during an inspection interval or Code Cases for a preservice inspection need not be changed because a subsequent revision of the Code Case is listed as the approved version in this guide.3. Code Cases to be applied during an inspection interval or Code Cases fora preservice inspection that were previously approved for use need not be changed because the Code Case has been subsequently annulled.4. Code Cases on the approved list may be applied to procedures for an inspection interval and procedures for the inservice inspection that were established prior to the effective date of the Code Case within the limits specified in the Code Case and applicable regulations or recommended in other regulatory guides.8 Code Case N-375 was not liated in prior versions of this regulatory guide.0 1.147-4 APPENDIX Numerical Listing of Code Cases 1551 (N-34)1705-1 (N-98)N-1 13-1 1738 (N-118)N-211 N-216 N-234 N-235 N-236 N-278 N-306 N-307 1.147-5 N-308 N-3 11 N-335 N-343 N-355 N-375-2 N-389 N-40 1 N402 N-406 N-408}}
N-560-1 1N-560-2 1N-561 1N-561-1 1N-562 1N-562-1 1N-563 N-566 N-566-1 N-567 N-567-1 N-568 N-569 N-569-1 N-573 N-574 1N-575 1N-576 N-576-1 N-577 1N-577-1 1N-578 1N-578-1 1N-583 N-586 N-587 1N-588 N-589 1N-590 1N-591 1N-592 N-593 N-597-1 3N-598 N-599 N-601 N-603 N-604 N-605 N-606 N-606-1 N-609 N-613 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-641 N-643 N-647 N-648-1 4
1.147-26REGULATORY ANALYSISA separate regulatory analysis was not prepared for this regulatory guide.  The regulatorybasis for this guide is the regulatory analysis prepared for the amendment to 10 CFR 50.55a,
"Codes and Standards," that incorporates this regulatory guide by reference.A copy of the regulatory analysis is available for inspection and/or copying for a fee in the NRC's Public Document Room at 11555 Rockville Pike, Public File Area (O-1F21), Rockville, MD. The PDR's mailing address is USNRC PDR, Washington, DC 20555-0001; telephone(301)415-4737 or 1-(800)397-4209; fax (301)415-3548; e-mail <PDR@NRC.GOV>.  Theregulatory analysis is also available through the NRC
's Electronic Reading Room under accessionnumber ML031490533.}}


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Revision as of 23:49, 19 October 2018

Inservice Inspection Code Case Acceptability ASME Section Xi Division 1
ML13350A192
Person / Time
Issue date: 09/30/1985
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.147, Rev. 4
Download: ML13350A192 (5)
v • d • e


SRi.es1on498 September

1985 .U.S. NUCLEAR REGULATORY

COMMISSION'

REG ULATORY GUIDE OFFICE OF NUCLEAR REGULATORY

RESEARCH REGULATORY

GUIDE 1.147 INSERVICE

INSPECTION

CODE CASE ACCEPTABILITY

ASME SECTION Xl DIVISION 1

A. INTRODUCTION

Section50.55a, "Codes and Standards," of 10CFR Part 50, "Dom-stic licensing of Production and Utilization Facilities," requires, in part, that each operating license for a boiling or pressurized water-cooled nuclear power facility and each construction permit for a utilization facility be subject to the conditions in paragraph (g), "Inservice Inspec-tion Requirements," of §50.55a. Paragraph (g) requires, in part, that Classes 1, 2, and 3 components and their supports meet the requirements of Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1 of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code or equivalent quality standards.

Paragraph

50.SSa(b), in part, references the latest editions and addenda in effect of Section XI of the Code and any supplementary requirements to that section of the Code.Footnote 6 to §50.55a states that the use of specific Code Cases may be authorized by the Commission upon request pursuant to paragraph

50.S5a(aX2)(ii), which requires that proposed alternatives to the described requirements or portions thereof provide an acceptable level of quality and safety.General Design Criterion I, "Quality Standards and Re-cords," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50 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 function to be performed.

Where generally recognized codes and standards are used, Criterion

1 requires that they be identi-fied and evaluated to determine their applicability, adequacy, and sufficiency and be supplemented or modified as neces-sary to ensure a quality product in keeping with the required safety function.This regulatory guide lists those Section XI ASME Code.Cases that are generally acceptable to the NRC staff for Co t plu nay be obtained hom the American Society of Mechanical Enaimenr, United Englimeuing Center, 345 East 47th Street, New York, N.V. 10017.implementation in the inservice inspection of light-water- cooled nuclear power plants.Any information collection activities mentioned in this regu-latory guide are contained as requirements in 10 CFR Part 50, which provides the regulatory basis for this guide. The informa-tion collection requirements in 10 CFR Part 50 have been cleared under OMB Clearance No. 3150-0011.

B. DISCUSSION

The ASME Boiler and Pressure Vessel Committee pub-lishes a document entitled "Code Cases."' Generally, the individual Code Cases that make up this document explain the intent of Code rules or provide for alternative requirements under special circumstances.

Most Code Cases are eventually superseded by revision of the Code and tben are annulled by action of the ASME Council.In such instances, the intent of the annulled Code Case becomes part of the revised Code, and therefore continued use of the Code Case intent is sanctioned under the rules of the Code. In other instances, the Code Case is annulled because it is no longer acceptable or there is no further requirement for it. A Code Case that was approved for a particular situation and not for a generic application shuld be used only for the approved situation because annulment of such a Code Case could result in situations that would not meet Code requirements.

The ASME considers the use of Code Cases to be optional for the user and not a mandatory requirement.

The Code Cases listed in this guide are limited to those cases applicable to Section XI of the Code.All published Code Cases that are applicable to Section XI of the Code and were in effect on July 12, 1984, were reviewed for inclusion in this guide. Code Cases that are not listed herein are either not endorsed or will require supple-.mentary provisions on an individual plant basis to attain endorselnent status.*Lines indicate substanilve changes from Revision

3. USNRC REGULATORV

GUIDES Regulatory Guides are Issued to describe and make available to the public methods acceptable to the NRC staff of Implementing specfic -parts of the Commission's regulations, to delineate tech.niques ue by the staff In evaluating

$Pecific problems or postu-lated aUcidents, or to provide guidance to applicants.

Regulatory

-Guides are not substitutes for regulations, and compliance.

with the'l Is not required.

Methods and solutions different from those set*out, n the guid~es will! be acceptable If they. provide a basis for the findings.'requisite to the issuance or continuance of a permit or..license by the Commission.

This guide was Issued after consideration of comments received from the public. Comments and suggestions for Improvements In these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect now Informo-tio0n1or experience.

l .e Comments should be sent-to the Secretary of the Commission, U.S. Nuclear Regulatory Commissionn, DC 20555,-Attontlons Docketing and Service 8rancnr--..I

The guides are Issued In the following ten broad dl¥visonsi..

1. Power Reactors 6. Products 2. Research and Test Reactors

7. Transportation

3. Fuels and Materials Facilities

8. Occupational Health.4. Environmental end Siting 9. Antitrust and Flnanclal Review 5.. Materials and Plant Protection

10. General -.............

Copies of Issued guides may be purchaseda t thecurrent Goverpment Prlntlna Office price. A subscription service for future uldes In wr.cific d vislons Is available through the Government PKnting Of C&information on the subscription servIce and current 0POrices mae be obtained by writing the Superintendent of ?ocument=

Un, Government Printing Office, Post Off0 e Box '3702, shlngton, DC 20013-7082.

F2 '.'~

The endorsement of a Code Case by this guide constitutes acceptance of its technical position for applications not precluded by regulatory or other requirements or by the recommendations in this or other regulatory guides. Con-tingent endorsement if applicable is indicated in regulatory position I for specific cases. However, it is the responsibil- ity of the user to make certain that no regulatory requirements are violated and that there are no conflicts with other recom-mended limitations resulting from Code Case usage.Acceptance or endorsement by the NRC staff applies only to those Code Cases or Code Case revisions with the date of "Council Approval" as shown in the regulatory position of this guide. Earlier or later revisions of a Code Case are not endorsed by this guide. New Code Cases will require evaluation by the NRC staff to determine if they qualify for inclusion in the approved list. Because of the con-tinuing change in the status of Code Cases, it is planned that this guide will require periodic updating to accommodate new Code Cases and any revision of existing Code Cases.C. REGULATORY

POSITION 1. The Section XI ASME Code Cases 2 listed below (by number, date of Council approval, 3 and title) are accept-able to the NRC staff for application in the inservice inspection of components and their supports for water-cooled nuclear power plants. Their use is acceptable within the limitations stated in the "Inquiry" and "Reply" sec-tions of each individual Code Case, within the limitations of such NRC or other requirements as may exist, and within the additional limitations recommended by the NRC staff and given with the individual Code Case in the list.1551 11/6/72 Inservice Inspection of Welds on N-34 11/20/78 Nuclear Components,Section X;the examination of clad surfaces of nozzles, including the inner surface of the nozzle-to-vessel insert welds.N-211 4 7/13/81 Recalibration of Ukrasonic Equip-ment Upon Change of Personnel,Section XI, Division I N-216 3/10/78 Alternate Rules for Reactor Vessel 7/13/81 Closure Stud Examination, Sco-Lion XI, Division 1 N-234 1/8/79 Time Between Ultrasonic Calibra-1/21/82 tion Checks,Section XI, Divi-sion I N-235 1/8/79 Ultrasonic Calibration Checks per 4/2/82 Section V, Section Xl, Division I N-236 1/8/79 Repair and Replacement of Class 1/21/82 MC Vessels,Section XI, Division I Code Case N-236 is acceptable subject to the following conditions in addition to those conditions specified in the Code Case:

a. In paragraph

1.0(a), second sentence -the phrase,"while the plant is not in service," refers to a refueling outage.

b. In paragraph

1.0(a), third sentence -the phrase,"the next scheduled plant outage," refers to the next scheduled refueling outage.For clarification, Repair and Replacement of Class MC Vessels means Repair and Replacement of Class MC Vessels and Components (systems).

Acceptance of this Code Case in no way infers NRC approval to violate the technical specification or any NRC require-ments with regard to breach of containment during repair and replacement procedures while the plant is in operation.

Where a numbered Code paragraph is not identified by a particular edition of the Code, the Code in effect at the time of the ASME meeting (11/3/78)

that approved the Code Case should be governing.

N-278 3/17/80 Alternative Ultrasonic Calibration

3/17/835 Block Configuration

1-3131 and 5/25/83' T-434.3I Section XI, Division I Code Case N-278 is acceptable subject to the following conditions in addition to those conditions specified in the Code Case: When a universal calibration block is 4 The Code Case was annulled on no081 (ASME mandatory annulment date). It was reinstated on 1/13151. Because there was no change In the Code Case, the NRC considers that the Case was in effect during the period 3120/81 through 7/13/81.SCode Case N-278 was inadvertently allowed to expire because of an ASME administrative error on 3/17/83, Its mandatory amendment date. The Code Case without any technical changes was reinstated on 5/25183. Because of these circumstances, the Code Case Is considered to be in effect during that period of time.1705-1 3/1/76 N-98 11/20/78 1/21/82 Ultrasonic Examination- Calibra-tion Block Tolerances,Section XI N-I 13-1 12/13/82 Basic Calibration Block for Ultra-sonic Examination of Welds 10 in. to 14 in. Thick,Section XI, Diviwsin I 1738 12/22/75 N-118 11/20/78 1/21/82 Examination

-Acceptance Stand-ards for Surface Indications in Cladding,Section XI Code Case 1738 (N-118) is acceptable subject to the following condition in addition to those conditions specified in the Code Case. The last sentence of the"Reply" should be replaced with the following:

The provisions of this Code Case may not be applied for 2A numerical listing of the Code Cases appears In the appendix.3When more than one date Is given, the earlier date Is that on which the Code Case was approved by the ASME Council, and the later date (or dates) Is that on which the Code Case was reaffirmed by the ASME Council.1.147-2 used and some or all of the reference holes are larger than the reflector holes at comparable depths recom-mended by Article IV,'Section V, 1980 edition of the ASM. Code, a correction factor should be used to adjust the DAC level to compensate for the larger reflector holes. Also, if the reactor pressure vessel was previously examined by using a conventional block, a ratio between the DAC curves obtained from the two blocks should be noted (for reference)

with the significant indication data.N-306 1/15/81 Calibration Block Material Selec-* 4/5/84 tion, Appendix 1, 1-3121, Sec-tion XlI Division 1 N-307 1/15/81 Revised Ultrasonic Examination

4/5/84 Volume for Class I Bolting, Examination Category B-G-I, Division i, When the Examina-tions Are Conducted from the Center-Drilled Hole N-308 9/30/81 Documentation of Repairs and Replacements of Components in Nuclear Power Plants,.Section Xl, Division I N-311 5/11/81 Alternate Examination of Outlet* I 4/5/84 Nozzle on Secondary Side of Steam Generators,Section XI, Division 1 Code Case N-311 is acceptable subject to the following condition in addition to those conditions specified in the Code Case: The applicant should indicate in the Safety Analysis Report that the stress analysis of the nozzle inside-comer region meets the Code Case stipulations for the state of stress in this region.N-335 4/2/82 Rules for Ultrasonic

)-Iamina-tion of Similar and Dissimilar Metal Piping Welds,Section XI, Division I N-343 4/2/82 Alternate Scope of Examination of Attachment Welds for Exami-nation Categories B-H, B-K-I, and C-C, Section Xl, Division I N-355 7/16/82 Calibration Block for Angi Beam Ultrasonic Examin, of Large Fittings in Accorda, with .Appendix iii-3410, Sec.tion XI, Division 1'N-375-2 4/5/84 Rules for UltrasonicExamination of Bolts and Studs, Section Xl, Division I Code Case N-389 is acceptable subject to the following condition in addition to those conditions specified in the Code Case: Theapplicant should submit for approv-al the appropriate'edition and addenda of the Code that is to. be used for the repair, replacement, or modification before start of the work.N-401 2120/84 Eddy Current Examination, Sec-tion Xl, Division I N-402 2/20/84 'Eddy Current Calibration Stan-dard Material,Section XI, Divi-sion I N-406 4/5/84 Alternate Rules for Replace-ment,Section XI, Division .1 N-408 7/12184 Alternate Rules for Examination of Class 2 Piping,. Section -XI, Division 1 Code Case N-408 is acceptable subject to the following condition in addition to those conditions specified in the Code Case: The applicant for an operating license should define the Class 2 piping subject to volumetric and surface examination in the Preservice Inspection for determination of acceptability by the NRC staff.2. Code Cases that were endorsed by the NRC in a prior version of this guide and were later annulled by action of the ASME Council should be considered as deleted from the list of acceptable Code Cases as of the date of the AS4E Council.action that approved the annulment.

Such Code Cases that were annulled on or after November 1, 1978, are listed below by number, effective dates, 6 and title.1646 8/12/74 N-72 11/20/78 1/1181 1647 8/12/74 N-73 11/20178/l1/81 Partial Postponement of Category B-C Examination for Class I Com-ponents,Section XI Partial Postponement of Category B-D Examination for Class: I Components, Section XU 1730 11/3/75 Acceptance Standards for Class 2 N-112 7/1/79 and 3 Components,Section XI, Division I 1804 1/14/77 N-167 1/14/80 Minimum. Section Thickness Requirements for 'Repair -of: Nozzles,Section XI, Division 1 N-210 3/20/78 Exemption to Hydrostatic Tests 3/20/81, After Repairs; Section Xl, Divi-sion I N-389 7/25/83 Alternative Rules .for 1 Replacements, or Modiflc Oection XI, Division I: Repairs,' "Earle date-date Coda Came.was roved by -ASME Cowute"l ..cations, later date"d Code Coswa aweuned.l

.mia than two dst__:a-.sr. the lat te date thaante Code n. = u. e. The n~iddle data (or dt) was thei te of reaffirma.tion of the Coe .Cas:.1.147-3! : ::'k I Code Case N-210 was acceptable subject to the follow.ing condition in addition to those conditions specified in the Code Cas

e. Paragraph

(3) of the "Reply"should be replaced with the following:

Repairs to piping, pumps, and valves where the depth of the repaired cavity does not exceed 25 percent of the wall thickness.

N-21 1 3/20/78 Recalibration of Ultrasonic Equip-3/20/81 ment Upon Change of Personnel,Section XI, Division I N-2S2 11/19/79 Low Energy Capacitive Discharge 7/16/82 Welding Method for Temporary or Permanent Attachments to Components and Supports, Sec-tion III, Division 1, and XI Code Case N-252 was acceptable subject to the following condition in addition to those conditions specified in the Code Case: The applicant should indicate in the Safety Analysis Report the application, the material, and the thickness of the material to which the strain gage or thermocouple will be attached by CD welding.N-288 8/25/80 Hyrostatic lbst Requirements for 5/25/83 Class I and Class 2 Components,Section XI, Division I 3. Code Cases that were endorsed by the NRC in a prior version of this guide and were superseded by revised Code Cases on or after November 1, 1978, should be considered as not endorsed as of the date of the Council action that approv-ed the revised version of the Code Cases. These Code Cases that are no longer endorsed are listed in the following by number, effective dates, 7 and title.1731 11/3/75 Basic Calibration Block for Ultra-N- 113 11/20/78 sonic Examination of Welds 10in.1/21/82 to 13 in. Thick,Section XI, Divi-12/13/82 sion I 7 Earfler date-date Code Case was approved by ASME Council: later date-date revision of Code Case was appioved by ASMECouncil.

Where more than two dates atar, the tlat date Is the date on which the Code Case was revised.sTh middle date (or dates) was the date of reaffirmation of the Code Case.N-375s 8 2/14/83 Rules for Ultrasonic Examination

4/14/83 of Bolts and Studs,Section XI, Division I N-375-1 4/14/83 Rules for Ultrasonic Examina-4/5/84 tion of Bolts and Studs, Sec-tion XI, Division 1 4. Code Cases that are not on the approved list of this guide (paragraph C.I) or other regulatory guides, or for which authorization by the Commission has not been granted, are not acceptable on a generic basis.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants regarding the use of this regulatory guide.I. Except for those Code Cases that have been annulled by action of the ASME Council, the NRC staff will authorize appropriate use of the Code Cases listed in this guide under regulatory position 1 upon specific request by the applicant in accordance with footnote 6 to §50.55a, the Codes and Standards rule. Code Cases that are actually used are to be identified in the Inservice Inspection Program.2. Code Cases to be applied during an inspection interval or Code Cases for a preservice inspection need not be changed because a subsequent revision of the Code Case is listed as the approved version in this guide.3. Code Cases to be applied during an inspection interval or Code Cases fora preservice inspection that were previously approved for use need not be changed because the Code Case has been subsequently annulled.4. Code Cases on the approved list may be applied to procedures for an inspection interval and procedures for the inservice inspection that were established prior to the effective date of the Code Case within the limits specified in the Code Case and applicable regulations or recommended in other regulatory guides.8 Code Case N-375 was not liated in prior versions of this regulatory guide.0 1.147-4 APPENDIX Numerical Listing of Code Cases 1551 (N-34)1705-1 (N-98)N-1 13-1 1738 (N-118)N-211 N-216 N-234 N-235 N-236 N-278 N-306 N-307 1.147-5 N-308 N-3 11 N-335 N-343 N-355 N-375-2 N-389 N-40 1 N402 N-406 N-408


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