|
|
(7 intermediate revisions by the same user not shown) |
Line 1: |
Line 1: |
| {{Adams | | {{Adams |
| | number = ML102230344 | | | number = ML003740187 |
| | issue date = 10/31/2010 | | | issue date = 06/30/1973 |
| | title = Service Level I, Ii, and Iii Protective Coatings Applied to Nuclear Power Plants | | | title = Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants |
| | author name = | | | author name = |
| | author affiliation = NRC/RES | | | author affiliation = NRC/RES |
Line 9: |
Line 9: |
| | docket = | | | docket = |
| | license number = | | | license number = |
| | contact person = Bayssie Mekonen/RES 251-7489 | | | contact person = |
| | case reference number = DG-1242, FOIA/PA-2011-0011
| | | document report number = RG-1.54 |
| | document report number = RG-1.054, Rev. 2 | | | document type = Regulatory Guide |
| | package number = ML102230336
| | | page count = 2 |
| | document type = Regulatory Guide, Draft | |
| | page count = 13 | |
| }} | | }} |
| {{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION October 2010 Revision 2 REGULATORY GUIDE OFFICE OF NUCLEAR REGULATORY RESEARCH REGULATORY GUIDE 1.54 (Draft was issued as DG-1242, dated March 2010) SERVICE LEVEL I, II, AND III PROTECTIVE COATINGS APPLIED TO NUCLEAR POWER PLANTS A. INTRODUCTION This guide describes a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for the selection, application, qualification, inspection, and maintenance of protective coatings applied to Nuclear Power Plants. Title 10, of the Code of Federal Regulations, Part 50, "Domestic Licensing of Production and Utilization Facilities" (10 CFR Part 50) (Ref. 1), Appendix A, "General Design Criteria for Nuclear Power Plants," General Design Criterion (GDC) 1, "Quality Standards and Records," requires, in part, that structures, systems, and components (SSCs) important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed GDC 1 also requires licensees to establish and implement a quality assurance (QA) program to provide adequate assurance that these SSCs will satisfactorily perform their safety function GDC 4, "Environmental and Dynamic Effects Design Bases," requires, in part, that SSCs important to safety be designed for compatibility with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including loss-of-coolant accident Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 establishes overall QA program requirements for the design, fabrication, The NRC issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable for use in implementing specific parts of the agency's regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in reviewing applications for permits and licenses. Regulatory guides are not substitutes for regulations, and compliance with them is not required. Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commissio This guide was issued after consideration of comments received from the publi 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, Genera Electronic copies of this guide and other 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) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML102230344. The regulatory analysis may be found in ADAMS under Accession No. ML10223035 Rev. 2 of RG 1.54, Page 2 construction, and 10 CFR Part 50 establishes overall QA program requirements for the design, fabrication, construction, and testing of safety-related SSCs in nuclear power plants (NPPs).The U.S. Nuclear Regulatory Commission (NRC) maintenance rule, 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," includes in its scope safety-related SSCs that are relied on to remain functional during and following design-basis events with respect to specified functions and nonsafety-related SSCs (1) that are relied on to mitigate accidents or transients or are used in plant emergency operating procedures, (2) whose failure could prevent safety-related SSCs from fulfilling their safety-related functions, and (3) whose failure could cause a reactor scram or an actuation of a safety-related syste To the extent that protective coatings meet these criteria, these coatings are within the scope of the maintenance rul The maintenance rule requires the licensee to monitor the effectiveness of maintenance for protective coatings within its scope (as discrete systems or components or as part of any SSC) or to demonstrate that their performance or condition of these coatings is being effectively controlled through the performance of appropriate preventive maintenance, in accordance with 10 CFR 50.65(a)(1) or 10 CFR 50.65(a)(2), as appropriat Regulatory Guide (RG) 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," Revision 2, issued March 1997 (Ref. 2), provides further guidanc This regulatory guide contains information collection requirements covered by 10 CFR Part 50 that the Office of Management and Budget (OMB) approved under OMB control number 3150-001 The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control numbe B. DISCUSSION NPPs have used protective coatings extensively to protect the surfaces of facilities and equipment against corrosion and contamination from radionuclides and for wear protection during plant operation and maintenance activitie For plants that have a design basis that includes a commitment to RG 1.54, "Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants," Revision 0, issued June 1973 (Ref. 3), the regulations cited above require that protective coatings be qualified and capable of surviving a design-basis accident (DBA) without adversely affecting the safety-related SSCs needed to mitigate the acciden The NRC issued RG 1.54 to describe an acceptable method for complying with NRC QA requirements for protective coatings applied to ferritic steels, stainless steel, zinc-coated (galvanized) steel, concrete, or masonry surfaces of water-cooled NPP Protective coatings that met these guidelines would presumably not degrade over the design life of the plan However, operating history has shown that undesirable degradation, detachment, and other types of failures of coatings have occurred, as described in Generic Letter (GL) 98-04, "Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System after a Loss-of-Coolant Accident because of Construction and Protective Coating Deficiencies and Foreign Material in Containment," dated July 14, 1998 (Ref. 4). Detached coatings from a substrate that are subsequently transported to the intake structures of emergency core cooling systems (ECCSs) may make those systems unable to satisfy the requirement in 10 CFR 50.46(b)(5) to provide long-term coolin Revision 0 to RG 1.54 conditionally endorses American National Standards Institute (ANSI) N101.4-1972, "Quality Assurance for Protective Coatings Applied to Nuclear Facilities" (Ref. 5), and indirectly endorses guidance provided in ANSI N101.2-1972, "Protective Coatings (Paints) for Light-Water Nuclear Reactor Containment Facilities" (Ref. 6). ANSI formally withdrew ANSI N101.4-1972 and ANSI N101.2-1972 in 1988 and transferred the responsibility for updating, rewriting, and issuing appropriate replacement standards to the American Society for Testing and Materials (ASTM), | | {{#Wiki_filter:June 1973 U.S. ATOMIC ENERGY COMMISSION |
| Rev. 2 of RG 1.54, Page 3 specifically ASTM Committee D-33 on Protective Coating and Lining Work for Power Generation Facilitie ASTM has developed appropriate standards to replace ANSI N101.4-1972 and ANSI N101.2-197 The NRC issued RG 1.54, "Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants," Revision 1, in July 2000 (Ref. 7), to provide the agency's endorsement and regulatory positions on ASTM standards relevant to NPP protective coating Since the issuance of Revision 1 to RG 1.54, ASTM has updated many of the standards that RG 1.54 endorses to reflect the current industry practic The NRC is revising RG 1.54 to provide the agency's regulatory positions on the updated ASTM standards relevant to NPP protective coating The NRC has reviewed the ASTM standards cited in Section C of this guide for the selection, qualification, application, and maintenance of protective coatings applied to NPPs and considers them acceptable with the exceptions noted belo ASTM approved and issued ASTM D 3843-00, "Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities," (Ref. 8) as a partial replacement for ANSI N101.4-197 ASTM D 3843-00 was reapproved in 2008 with no changes as ASTM D 3843-00 (reapproved 2008) (Ref. 9). ASTM has approved and issued ASTM D 3911-95, "Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design-Basis Accident (DBA) Conditions," (Ref. 10) to replace the DBA test standard referenced in ANSI N101.4-1972 and RG 1.5 ASTM then revised ASTM D 3911-95 as ASTM D 3911-08 (Ref. 11). Nonmandatory Appendix X2 to this standard discusses witness coupons in primary containmen These test coupons, if properly placed, provide a realistic mechanism to test and evaluate the aging of coating Selected coupons could be periodically removed and tested to identify changes in various physical properties and could be DBA-tested to provide much better and more realistic predictions of coating lif New NPPs should consider the installation of coated test coupons at various locations in the primary containmen The coated test coupons would be representative of the aged condition of similar coatings within the primary containmen The licensee could use the test coupons for coating condition analysis and aging studies during the commercial life of the NPP. ASTM developed and issued ASTM D 5144-08, "Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants" (Ref. 12), to provide a common basis on which protective coatings for the surfaces of nuclear power generating facilities may be qualified and selected through reproducible evaluation test This ASTM standard provides guidance for the application and maintenance of protective coatings under the expected environmental, operating, and postulated accident conditions for pressurized-water reactors and boiling-water reactor ASTM D 5144-08 addresses, by reference, the preparation of test specimens, radiation tolerance testing, the decontaminability of coatings, physical properties, chemical resistance tests, fire evaluation tests, DBA testing, surface preparation, coating application and inspection, and thermal conductivity testin Therefore, ASTM D 5144-08 can be viewed as a top-level ASTM standard that provides detailed requirements through reference to other key ASTM standard Figure 1 shows the additional ASTM standards that provide application-specific guidance; these standards are discussed belo Rev. 2 of RG 1.54, Page 4 Figure 1 ASTM standards relevant to NPP Service Level I, II, and III protective coatings The NRC developed this RG using definitions and insights from operating reactor New reactor designs may use design features that are different from the operating reactors that formed the basis for this RG, and, therefore, adjustments may be necessar For example, a plant with passive containment cooling features may have different requirements for protective coatings on containment surfaces, or a plant might rely on the density of failed protective coating particles inside containment that limits their transport to the ECC Therefore, this RG provides guidance for new reactor designs with the recognition that the licensee or applicant may need to adjust some features based on the particular plant desig ASTM D 5144-08 Protective Coating Standards in NPPs ASTM D 3843-00 reapproved 2008 QA Practices for NPP ASTM D 4537-04a Procedures To Qualify and Certify Inspection Personnel in NPPsASTM D 5163-08/ ASTM D 7167-05 Condition Assessment of Coatings in NPPs ASTM D 4538-05 Protective Coating Terminology ASTM D 3911-08 Simulated DBA Coating Testing ASTM D 4082-10 Irradiation of Test Samples ASTM D 5139-10 Sample Preparation for Coating Tests ASTM D 7108-05 Specialist Qualification NPP Coatings ASTM D 3912-10 Chemical Resistance of Coatings ASTM D 7234-05 Coating Adhesion Testing-Concrete ASTM D 6677-07 Knife Adhesion Coating Tests ASTM D 4541-09 Coating Adhesion Testing ASTM D 4286-08 Contractor Qualification NPP Coatings ASTM D 4227-05 Applicator Qualification Concrete Surfaces ASTM D 7491-08 Management of Nonconforming Coatings ASTM D 5498-09 Development of a Training Program for Coating Work InspectorsASTM D 4228-05 Applicator Qualification Steel Surfaces Rev. 2 of RG 1.54, Page 5 C. REGULATORY POSITION 1. Guidance in American Society for Testing and Materials Standards ASTM D 5144-08 and the other ASTM standards discussed below provide guidance on practices and programs that the NRC staff finds acceptable for the selection, application, qualification, inspection, and maintenance of protective coatings applied to NPP ASTM Committee D-33 has defined Service Level I, II, and III coating locations to include both safety-related and nonsafety-related regions as set forth belo Service Level I, II, and III coatings are defined as follows: a. Service Level I coatings are used in areas inside the reactor containment where coating failure could adversely affect the operation of postaccident fluid systems and thereby impair safe shutdow b. Service Level II coatings are used in areas where coating failure could impair, but not prevent, normal operating performanc The functions of Service Level II coatings are to provide corrosion protection and decontaminability1 in those areas outside the reactor containment that are subject to radiation exposure and radionuclide contaminatio Service Level II coatings are not safety relate c. Service Level III coatings are used in areas outside the reactor containment where failure could adversely affect the safety function of a safety-related SS (Note that a coating on the external surface of a reactor containment may be designated Service Level III, although no plants licensed under 10 CFR Part 50 have applied this designation.) The QA provisions and guidance contained in the standards in this regulatory position are generally acceptable and provide methods that the NRC staff finds acceptable for complying with the pertinent QA requirements in Appendix B to 10 CFR Part 50, subject to the following two exceptions:
| | N REGULATORYDIRECTORATE OF REGULATORY STANDARDS |
| a. When using this RG, NRC licensees should meet the QA provisions and guidance contained in the standards in this RG and must also meet the commitments and provisions contained in their QA program description b. Applicants for design certifications and combined licenses under 10 CFR Part 52, "Licenses, Certifications, and Approvals for Nuclear Power Plants," (Ref. 14) may propose to use coatings in ways that do not conform to the service level definitions abov For example, an applicant could propose to designate coatings in certain areas of containment as Service Level II based on an evaluation that demonstrates that these coatings cannot be transported to the ECC Such exceptions may be acceptable to the NRC staff if the applicant provides a technical justification and corresponding technical and quality requirements in a licensing-basis document such as the final safety analysis repor ASTM withdrew ASTM D 4256-94, "Test Method for Determination of the Decontaminability of Coatings Used in Light-Water Nuclear Power Plants," issued in 1994 (Ref. 13). U.S. plants found that this test method is faulty in that almost any coating system will pass the tes In addition, this test method generates mixed hazardous waste and does not comply with occupational dose as low as reasonably achievable practice Rev. 2 of RG 1.54, Page 6 2. Quality Assurance ASTM D 3843-00 (reapproved 2008) provides QA practices that are acceptable to the NRC staff and are applicable to safety-related protective coating work in coating Service Level I areas of nuclear facilitie Licensees may use applicable portions of the QA practices described in ASTM D 3843-00 (reapproved 2008) as the basis for limited QA for protective coating work in coating Service Level II areas of nuclear facilitie ASTM D 5139-10, "Standard Specification for Sample Preparation for Qualification Testing of Coatings To Be Used in Nuclear Power Plants" (Ref. 15), provides guidance that the NRC staff finds acceptable on the size, composition, and surface preparation for test samples of protective coatings for use in the qualification testing of coatings that will be applied to NPPs, as described in ASTM D 3911-08 and in ASTM D 4082-10, "Standard Test Method for Effects of Gamma Radiation on Coatings for Use in Nuclear Power Plants" (Ref. 16). ASTM D 3911-08 provides guidance that the NRC staff finds acceptable on procedures for evaluating test specimens for protective coating systems under simulated DBA condition ASTM D 3911-08 also provides guidance on conditions and test apparatus for temperature-pressure testing; on conditions for radiation testing; and on procedures for preparing, examining, and evaluating sample ASTM D 3911-08 does not specify minimum acceptance criteri For Service Level I coatings, licensees or applicants shall meet the following minimum acceptance criteria: a. Peeling and delamination shall not be permitte b. Cracking is not considered a failure unless it is accompanied by delamination or loss of adhesio c. Blisters shall be limited to intact blisters that are completely surrounded by sound coating bonded to the surfac The licensee may establish more stringent acceptance criteria; the above criteria are meant to establish minimum standards only. ASTM D 4082-10 provides a standard test method that the NRC staff finds acceptable for evaluating the effects of gamma radiation on the lifetime radiation tolerance of Service Level I and II coating ASTM D 3912-10, "Standard Test Method for Chemical Resistance of Coatings and Linings for Use in Nuclear Power Plants" (Ref. 17), provides guidance that the NRC staff finds acceptable for evaluating the chemical resistance of coatings applied to light-water NPP . Training and Qualification of Nuclear Coating Specialists, Protective Coating Inspectors, and Coating Applicators ASTM D 4537-04a, "Standard Guide for Establishing Procedures To Qualify and Certify Personnel Performing Coating Work Inspection in Nuclear Facilities" (Ref. 18), provides guidance that the NRC staff finds acceptable on the qualification and certification of personnel who inspect protective coatings in nuclear facilitie This standard provides guidance on the inspection of the education, training, experience, qualifications, and certification of Service Level I, II, and III coatings inspector ASTM D 5498-09, "Standard Guide for Developing a Training Program for Personnel Performing Coating Work Inspection for Nuclear Facilities" (Ref. 19), provides guidance that the NRC staff finds acceptable for developing a training program for personnel who perform coating work inspection at nuclear facilitie Rev. 2 of RG 1.54, Page 7 ASTM D 7108-05, "Standard Guide for Establishing Qualifications for a Nuclear Coatings Specialist" (Ref. 20), provides guidance that the NRC staff finds acceptable for establishing qualifications for a nuclear coatings specialis A nuclear coatings specialist must meet one of the combinations of qualification attributes provided in Table 2 of ASTM D 7108-05. ASTM D 4227-05, "Standard Practice for Qualification of Coating Applicators for Application of Coatings to Concrete Surfaces" (Ref. 21), provides guidance that the NRC staff finds acceptable for the qualification of coating applicators to verify that they are proficient and can attain the quality required for the application of specified coatings to concrete surfaces, including those in a nuclear facilit ASTM D 4228-05, "Standard Practice for Qualification of Coating Applicators for Application of Coatings to Steel Surfaces" (Ref. 22), provides guidance that the NRC staff finds acceptable for the qualification of coating applicators to verify that they are proficient and can attain the quality required for applying specified coatings to steel surfaces, including those in a nuclear facilit ASTM D 4286-08, "Standard Practice for Determining Coating Contractor Qualifications for Nuclear Powered Electric Generation Facilities" (Ref. 23), provides criteria and methods that the NRC staff finds acceptable to assist utility owners, architects, engineers, and contractors in determining the overall qualifications of a coating contractor to perform coating work for the primary containment and other safety-related facilities of NPP The criteria and requirements for coating contractors address their capabilities to perform nuclear coating wor . Maintenance of Coatings ASTM D 5163-08, "Standard Guide for Establishing a Program for Condition Assessment of Coating Service Level I Coating Systems in Nuclear Power Plants" (Ref. 24), provides guidelines that the NRC staff finds acceptable for establishing an in-service coating monitoring program for Service Level I coating systems in operating NPPs and for Service Level II and other areas outside containment (as applicable) with the following conditions: a. Licensees should establish an acceptable condition assessment program using qualified personnel and should perform condition assessments at a periodicity that would allow them to detect potential coating degradation and to implement repairs before such degradation would adversely impact postaccident safety system b. Licensees should perform condition assessments under the direction of a nuclear coating specialist, as defined in ASTM D 7108-0 c. Licensees should evaluate degraded coatings identified during condition assessments for their impact on the ECCS postaccident function consistent with the guidance in RG 1.82 "Water Sources for Long-Term Recirculation Cooling Following a Loss-Of-Coolant Accident," (Ref. 25) and in accordance with applicable licensing-basis document d. Although the ASTM D 5163-08 standard provides reasonable assurance that qualified coatings left in service after a visual inspection will remain adhered to their substrates under accident conditions, it does not guarantee that visual inspection will detect all degraded coating Therefore, the NRC recommends that licensees account for the potential that visual inspections may not identify some degraded coatings by using margin in debris-generation calculations for ECCS strainer performance or by using a debris transport analysis to show that the debris will not reach the straine Rev. 2 of RG 1.54, Page 8 ASTM D 7167-05, "Standard Guide for Establishing Procedures To Monitor the Performance of Safety-Related Coating Service Level III Lining Systems in an Operating Nuclear Power Plant" (Ref. 26), provides guidelines that the NRC staff finds acceptable for establishing procedures to monitor the performance of Service Level III lining systems in an operating NPP. ASTM D 4541-09, "Standard Test Method for Pull-Off Strength of Coatings Using Portable Adhesion Testers" (Ref. 27), provides guidance that the NRC staff finds acceptable for a test method used to evaluate the pull-off strength of coatings on metal substrates using fixed-alignment adhesion tester ASTM D 6677-07, "Standard Test Method for Evaluating Adhesion by Knife" (Ref. 28), provides guidance that the NRC staff finds acceptable for a test method used to evaluate adhesion using a knife. ASTM D 7234-05, "Standard Test Method for Pull-Off Adhesion Strength of Coatings on Concrete Using Portable Pull-Off Adhesion Testers" (Ref. 29), provides guidance that the NRC staff finds acceptable for a test method used to evaluate the pull-off strength of coatings on concrete using portable pull-off adhesion testers.3 ASTM D 7491-08, "Standard Guide for Management of Non-Conforming Coatings in Coating Service Level I Areas of Nuclear Power Plants" (Ref. 30), provides guidance that the NRC staff finds acceptable for managing nonconforming coatings within the Service Level I areas of a NP . American Society for Testing and Materials Standard Terminology ASTM D 4538-05, "Standard Terminology Relating to Protective Coating and Lining Work for Power Generation Facilities" (Ref. 31), defines standard terms related to protective coating and lining work for power generation facilities that the NRC staff finds acceptable and that are also relevant to protective coatings applied to NPP . Additional Information Electric Power Research Institute (EPRI) Topical Report No. 1019157, "Guideline on Nuclear Safety-Related Coatings," Revision 2, issued December 2009 (formerly EPRI Topical Report Nos. 109937 and 1003102) (Ref. 32), provides additional information on the selection, application, inspection, and maintenance of safety-related protective coatings applied to NPP EPRI Topical Report No. 1019157 discusses, in detail, the important considerations related to protective coatings and can be used to supplement the ASTM standards as deemed necessary, with the exception of Section 3.4.2 of the report, which discusses the application of specialized coatings for restoring the structural integrity of a componen The NRC does not endorse the use of specialized coatings for restoring structural integrity. D. IMPLEMENTATION The purpose of this section is to provide information on how applicants and licensees4 may use this guide and information regarding the NRC's plans for using this Regulatory Guid In addition, it describes how the NRC staff has complied with the Backfit Rule, 10 CFR 50.109 and any applicable finality provisions in 10 CFR Part 5 A fixed-alignment adhesion Tester Type II (Test Method B) is the test method that NPPs have historically used. 3 This test standard is ne Historically, adhesion testing of coatings on concrete was performed in accordance with ASTM D 4541-09. 4 In this section, "licensees" include applicants for standard design certifications under 10 CFR Part 5 Rev. 2 of RG 1.54, Page 9 Applicant and Licensees' Use Applicants and licensees may (i.e., voluntarily) use the information in this regulatory guide to develop applications for initial licenses, amendments to licenses, or other requests for NRC regulatory approval (e.g., exemptions). Licensees may use the information in this regulatory guide for actions which do not require prior NRC review and approval (e.g., changes to a facility design under 10 CFR 50.59 which do not require prior NRC review and approval). Licensees may use the information in this Regulatory Guide or applicable parts to resolve regulatory or inspection issues (e.g., by committing to comply with provisions in the regulatory guide). Current licensees may continue to use the guidance that was found acceptable for complying with specific portions of the regulations as part of their license approval process, which may be a previous version of this Regulatory Guid A licensee who believes that the NRC staff is inappropriately imposing this Regulatory Guide as part of a request for a license amendment or request for a change to a previously issued NRC regulatory approval may file a backfitting appeal with the NRC in accordance with applicable procedure NRC Staff Use The NRC staff does not intend or approve any imposition or backfitting of the guidance in this Regulatory Guid The staff does not expect any existing licensee to use or commit to using the guidance in this Regulatory Guide in the absence of a licensee-initiated change to its licensing basi The NRC staff does not expect or plan to request licensees to voluntarily adopt this Regulatory Guide to resolve a generic regulatory issu The NRC staff does not expect or plan to initiate NRC regulatory action which would require the use of this regulatory guide (e.g. issuance of an order requiring the use of the Regulatory Guide, requests for information under 10 CFR 50.4(f) as to whether a licensee intends to commit to use of this regulatory guide, generic communication, or promulgation of a rule requiring the use of this Regulatory Guide) without further back-fit consideratio During inspections of specific facilities, the staff may suggest or recommend that licensees consider various actions consistent with staff positions in this regulatory guid Such suggestions and recommendations would not ordinarily be considered backfitting even if prior versions of this Regulatory Guide are part of the licensing basis of the facility with respect to the subject matter of the inspectio However, the staff may not represent to the licensee that: (i) the licensee's failure to comply with the positions in this Regulatory Guide constitutes a violation; (ii) the licensee may avoid the violation by agreeing to comply with this Regulatory Guide; or (iii) the only acceptable way for the licensee to address the NRC-identified non-compliance or violation is to commit to this Regulatory Guide (i.e., including this Regulatory Guide in the facility's licensing basis).
| | GUIIDE |
| | REGULATORY GUIDE 1.54 QUALITY ASSURANCE REQUIREMENTS FOR PROTECTIVE COATINGS |
| | APPLIED TO WATER-COOLED NUCLEAR POWER PLANTS |
|
| |
|
| If an existing licensee seeks a license amendment or change to an existing regulatory approval, and the staff's consideration of the request involves a regulatory issue which is directly relevant to this Regulatory Guide and the specific subject matter of the new or revised guidance is an essential consideration in the NRC staff's determination of the acceptability of the licensee's request, the staff may require the licensee to use this Regulatory Guide as a prerequisite for NRC approva This is not considered back-fitting as defined in 10 CFR 50.109(a)(1) or a violation of any of the issue finality provisions in 10 CFR Part 5 Conclusion Rev. 2 of RG 1.54, Page 10 This regulatory guide is not being imposed upon current licensees and may be voluntarily used by existing licensee In addition, this Regulatory Guide is issued in conformance with all applicable internal NRC policies and procedures governing backfittin Accordingly, the NRC's staff issuance of this regulatory guide is not considered backfiting, as defined in 10 CFR 50.109(a)(1), nor is it deemed to be in conflict with any of the issue finality provisions in 10 CFR Part 5 REFERENCES1 1. 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," U.S. Nuclear Regulatory Commission, Washington, DC. 2. Regulatory Guide 1.160, "Monitoring the Effectiveness of Maintenance at Nuclear Power Plants," Revision 2, U.S. Nuclear Regulatory Commission, Washington, DC, March 1997. 3. Regulatory Guide 1.54, "Quality Assurance Requirements for Protective Coatings Applied to Water Cooled Nuclear Power Plants," Revision 0, U.S. Nuclear Regulatory Commission, Washington, DC, June 1973. 4. GL 98-04, "Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System after a Loss-of-Coolant Accident because of Construction and Protective Coating Deficiencies and Foreign Material in Containment," U.S. Nuclear Regulatory Commission, Washington, DC, July 14, 199 . ANSI N101.4-1972, "Quality Assurance for Protective Coatings Applied to Nuclear Facilities,"
| | ==A. INTRODUCTION== |
| American National Standards Institute, Washington, DC.2 6. ANSI N101.2-1972, "Protective Coatings (Paints) for Light-Water Nuclear Reactor Containment Facilities," American National Standards Institute, Washington, D . Regulatory Guide 1.54, "Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants," Revision 1, U.S. Nuclear Regulatory Commission, Washington, DC, July 2000. 8. ASTM D 3843-00, "Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities," American Society for Testing and Materials, West Conshohocken, P . ASTM D 3843-00 (reapproved 2008), "Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities," American Society for Testing and Materials, West Conshohocken, PA. 10. ASTM D 3911-95, "Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design-Basis Accident (DBA) Conditions," American Society for Testing and Materials, West Conshohocken, P All NRC regulations listed herein are available electronically through the Electronic Reading Room on the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Copies are also available for inspection or copying for a fee from the NRC's Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD; the mailing address is USNRC PDR, Washington, DC 20555; telephone (301) 415-4737 or (800) 397-4209; fax (301) 415-3548; and e-mail pdr.resource@nrc.go Copies of American National Standards Institute (ANSI) standards may be purchased from ANSI, 1819 L Street, NW., 6th floor, Washington, DC 20036; telephone (202) 293-802 Purchase information is available through the ANSI Web site at http://webstore.ansi.org/ansidocstore/. 3 Copies of American Society for Testing and Materials (ASTM) standards may be purchased from ASTM, 100 Barr Harbor Drive, P.O. Box C700, West Conshohocken, PA 19428-2959; telephone (610) 832-958 Purchase information is available through the ASTM Web site at http://www.astm.or Rev. 2 of RG 1.54, Page 12 11. ASTM D 3911-08, "Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design-Basis Accident (DBA) Conditions," American Society for Testing and Materials, West Conshohocken, P . ASTM D 5144-08, "Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants," American Society for Testing and Materials, West Conshohocken, P . ASTM D 4256-94 "Test Method for Determination of the Decontaminability of Coatings Used in Light-Water Nuclear Power Plants," American Society for Testing and Materials, West Conshohocken, PA. 14. 10 CFR Part 52, "Licenses, Certifications and Approvals for Nuclear Power Plants," U.S. Nuclear Regulatory Commission, Washington, DC. 15. ASTM D 5139-10, "Standard Specification for Sample Preparation for Qualification Testing of Coatings To Be Used in Nuclear Power Plants," American Society for Testing and Materials, West Conshohocken, P . ASTM D 4082-10, "Standard Test Method for Effects of Gamma Radiation on Coatings for Use in Nuclear Power Plants," American Society for Testing and Materials, West Conshohocken, PA. 17. ASTM D 3912-10, "Standard Test Method for Chemical Resistance of Coatings and Linings for Use in Nuclear Power Plants," American Society for Testing and Materials, West Conshohocken, P . ASTM D 4537-04a, "Standard Guide for Establishing Procedures To Qualify and Certify Personnel Performing Coating Work Inspection in Nuclear Facilities," American Society for Testing and Materials, West Conshohocken, P . ASTM D 5498-09, "Standard Guide for Developing a Training Program for Personnel Performing Coating Work Inspection for Nuclear Facilities," American Society for Testing and Materials, West Conshohocken, P . ASTM D 7108-05, "Standard Guide for Establishing Qualifications for a Nuclear Coatings Specialist," American Society for Testing and Materials, West Conshohocken, PA. 21. ASTM D 4227-05, "Standard Practice for Qualification of Coating Applicators for Application of Coatings to Concrete Surfaces," American Society for Testing and Materials, West Conshohocken, P . ASTM D 4228-05, "Standard Practice for Qualification of Coating Applicators for Application of Coatings to Steel Surfaces," American Society for Testing and Materials, West Conshohocken, P . ASTM D 4286-08, "Standard Practice for Determining Coating Contractor Qualifications for Nuclear Powered Electric Generation Facilities," American Society for Testing and Materials, West Conshohocken, P . ASTM D 5163-08, "Standard Guide for Establishing a Program for Condition Assessment of Coating Service Level I Coating Systems in Nuclear Power Plants," American Society for Testing and Materials, West Conshohocken, P Rev. 2 of RG 1.54, Page 13 25. Regulatory Guide 1.82, "Water Sources for Long-Term Recirculation Cooling Following a Loss-Of-Coolant Accident," Revision 3, U.S. Nuclear Regulatory Commission, Washington, DC, November 2003. 26. ASTM D 7167-05, "Standard Guide for Establishing Procedures To Monitor the Performance of Safety-Related Coating Service Level III Lining Systems in an Operating Nuclear Power Plant," American Society for Testing and Materials, West Conshohocken, P . ASTM D 4541-09, "Standard Test Method for Pull-Off Strength of Coatings Using Portable Adhesion Testers," American Society for Testing and Materials, West Conshohocken, P . ASTM D 6677-07, "Standard Test Method for Evaluating Adhesion by Knife," American Society for Testing and Materials, West Conshohocken, P . ASTM D 7234-05, "Standard Test Method for Pull-Off Adhesion Strength of Coatings on Concrete Using Portable Pull-Off Adhesion Testers," American Society for Testing and Materials, West Conshohocken, PA. 30. ASTM D 7491-08, "Standard Guide for Management of Non-Conforming Coatings in Coating Service Level I Areas of Nuclear Power Plants," American Society for Testing and Materials, West Conshohocken, P . ASTM D 4538-05, "Standard Terminology Relating to Protective Coating and Lining Work for Power Generation Facilities," American Society for Testing and Materials, West Conshohocken, P . EPRI Topical Report No. 1019157 "Guideline on Nuclear Safety-Related Coatings," Revision 2, Electric Power Research Institute, Palo Alto, CA, December 200 Copies of the listed Electric Power Research Institute (EPRI) standards and reports may be purchased from EPRI, 3420 Hillview Ave., Palo Alto, CA 94304; telephone (800) 313-3774; fax (925) 609-1310.}}
| | Coatings Applied to Nuclear Facilities,"' for protective coatings applied to ferritic steels, aluminum, stainless Appendix B to 10 CFR Part 50, "Quality Assurance steel, zinc-coated (galvanized) steel, concrete, or masonry Criteria for Nuclear Power Plants and Fuel Reprocessing surfaces of water-cooled nuclear power plants are Plants," establishes overall quality assurance program generally acceptable and provide an adequate basis for requirements for the design, fabrication, construction, complying with the pertinent quality assurance and operation of safety-related nuclear power plant requirements of Appendix B to 10 CFR Part 50 subject structures, systems, and components. This guide to the following: |
| | describes an acceptable method of complying with the Commission's quality assurance requirements with 1. ANSI N101.4-1972 should be used in conjunction regard to protective coatings applied to ferritic steels, with ANSI N45.2-1971, "Quality Assurance Program aluminum, stainless steel, zinc-coated (galvanized) steel, Requirements for Nuclear Power Plants." 2 concrete, or 'Masonry surfaces of water-cooled nuclear power plants. The Advisory Committee on Reactor 2. Subdivision 2.7 of ANSI N101.4-1972 states that Safeguards has been consulted concerning this guide and when references are made to other standards, these has concurred in the regulatory position. references shall imply the most recent or current editions of the referenced standard |
| | |
| | ====s. The specific ==== |
| | |
| | ==B. DISCUSSION== |
| | applicability or acceptability of referenced standards will be covered separately in other regulatory guides, where Subcommittee N101.5.7 of the American National appropriate. |
| | |
| | Standards Institute (ANSI) Standards Committee NIO1, Atomic Industry Facility Design, Construction, and 3. Subdivision 1.1.2 of ANSI N101.4-1972 states that Operation Criteria, under the sponsorship of the quality assurance, as covered by this standard, comprises American Institute of Chemical-Engineers, has developed all those planned and systematic actions necessary to a standard which includes quality assurance provide specified documentation and adequate requirements for protective coatings applied to ferritic confidence that shop or field coating work for nuclear steels, aluminum, stainless steel, zinc-coated (galvanized) facilities will perform satisfactorily in service. This steel, concrete, or masonry surfaces of nuclear facilities. statement should not be interpreted as implying that the This standard was approved by the American National end product of quality assurance actions is the Standards Committee N1O0 and its Secretariat. It was production of specified documentation. The term subsequently approved and designated N101.4-1972 by the American National Standards Institute on November 28, 1972. 'Copies may be obtained from the American Institute of Chemical Engineers, 345 East 47th Street, New York, N.Y. |
| | |
| | ==C. REGULATORY POSITION== |
| | 10017. |
| | |
| | 'Copies may be obtained from the American Society of The requirements and guidelines included in ANSI Mechanical Engineers, United Engineering Center, 345 East 47th N 10 1.4-1972, "Quality Assurance for Protective Street, New York, N.Y. 10017. |
| | |
| | USAEC REGULATORY GUIDES Copies of published guides may be obtained by request Indicating the divisions desired to the US. Atomic Energy Commission. Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public Attention: Director of Regulatory Standards. Comments end suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of Improvements In these guides re encouraged and should be sent to the Secretary the Cornmmssion's regulations, to delineate techniques used by the staff in of the Commission. U.S. Atomic Energy Commission. Washington, D.C. 20545, evluating specific problems or postulated accidents, or to provide guidance to Attention: Chief, Public Proceedings Staff. |
| | |
| | applicants. Regulatory Guides are not substitutes for regulations and compliance with them is not required. Methods and solutions different from those set out in The guides ae issued in the following ten broad divisions: |
| | the guides will be acceptable if they provide a besis for the findings requisite to the issuance or continuance of a permit or license by the Commission. 1. Power Reactors |
| | |
| | ===6. Products=== |
| | 7. Research and Test Reactors |
| | |
| | ===7. Transportation=== |
| | 3. Fuels arid Materials Facilities &. Occupational Health Published guides will be revised periodically, asappropriate, to accommodate 4. Environmental and Siting 9. Antitrust Review comments and to reflect new information or experience. 5. Materials and Plant Protection 1 |
| | |
| | ===0. General=== |
| | |
| | "quality assurance" as used in ANSI N1OI.4-1972 materials used with stainless steel should not be should be considered to comprise all those planned and compounded from or treated with chemical compounds systematic actions necessary to provide adequate containing elements that could contribute to corrosion, confidence that shop or field coating work for nuclear intergranular cracking, or stress corrosion cracking. |
| | |
| | facilities will perform satisfactorily in service. In this Examples of such chemical compounds are those connection it is emphasized that records and documents containing chlorides, fluorides, lead, zinc, copper, sulfur, listed in Subdivisions 7.4 through 7.8, and included in or mercury where such elements are leachable or where the standard, are suggested forms only. Alternate they could be released by breakdown of the chemical documentation consistent with the requirements of compounds under expected environmental conditions Appendix B to 10 CFR Part 50 is also considered (e.g., by radiation). This limitation is not intended to acceptable. prohibit the use of trichlorotrifluoroethane which meets the requirements of Military Specification |
| | 4. Sections 3 and 4 of ANSI N101.4-1972 delineate MiL-C-81302b for cleaning or degreasing of austenitic quality assurance requirements for coating materials and stainless steel provided adequate removal is assured prior surface preparation of substrates. Coatings and, cleaning to painting. |
| | |
| | 1.54-2}} |
|
| |
|
| {{RG-Nav}} | | {{RG-Nav}} |
|
---|
Category:Regulatory Guide
MONTHYEARML23263A9972024-02-0202 February 2024 Watermarked - DG-5072 - Rev 0 of RG 5.90 - Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors ML23286A2682024-02-0202 February 2024 Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23) ML23286A2822024-02-0202 February 2024 Watermarked - DG-5076 - Physical Protection for Part 53 - 10-13-23 ML23286A2512024-02-0202 February 2024 Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23 ML23286A2862024-02-0202 February 2024 Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23 ML23286A2782024-02-0202 February 2024 Watermarked - DG-5075 - Cyber Security 10-13-23 ML23194A1942023-08-31031 August 2023 Draft Regulatory Guide DG-1404, Revision 1 (RG 1.253 Rev 0) Guidance on Ticap for Non-LWRs ML23012A2422023-02-28028 February 2023 DG-1374 RG 1.152 Rev 4 Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants ML22165A0722023-02-28028 February 2023 DG-4027, Draft Regulatory Guide 4.2 Supplement 1, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2 ML23018A2932023-02-16016 February 2023 Draft Regulatory Guide DG-1418 (RG 1.212 Rev 2), Sizing Large Lead-Acid Storage Batteries. (ACRS Copy) Regulatory Guide 5.892022-11-0101 November 2022 Rev.0, Fitness-for-Duty Programs for Commercial Power Reactor and Category I Special Nuclear Material Licensees ML22067A0142022-03-31031 March 2022 Rev 3 ACRS Spent Fuel Heat Generation in an ISFSI ML22048B8222022-02-18018 February 2022 DG-1389 (ACRS Version for 3-16-22 Meeting) - Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors ML22040A0822021-10-30030 October 2021 Document to Support ACRS Subcommittee Meeting - Redline RG 1.57, Rev 3, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components ML21167A3512021-06-0101 June 2021 Rev 5 Final Watermarked for ACRS ML21092A1512021-05-0505 May 2021 Rev. 4 ACRS Version ML21092A1342021-05-0505 May 2021 Rev. 2 ACRS Version ML21181A2492021-04-30030 April 2021 Watermark for ACRS Fc Meeting RG 1.9 Rev 5 ML21006A3352021-04-0101 April 2021 DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities ML20168A8832021-04-0101 April 2021 DG-1371, Proposed Rev 6 of RG 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants ML21006A3372021-04-0101 April 2021 Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities ML21083A2892021-02-28028 February 2021 Draft for Acrs Review ML21048A4482021-02-17017 February 2021 Rev. 2 ML20120A6292021-01-31031 January 2021 Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368) ML20120A6332021-01-31031 January 2021 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, (DG-1366) ML20120A6272021-01-31031 January 2021 ASME Code Cases Not Approved for Use, Revision 7 (DG-1369) ML20120A6312021-01-31031 January 2021 Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367) ML21011A2312021-01-31031 January 2021 Rev 4 (Draft for ACRS Fc Review on 2-3-21) ML21012A1972021-01-12012 January 2021 a Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0 Regulatory Guide 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities2020-12-31031 December 2020 Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20183A4232020-12-31031 December 2020 Draft Regulatory Guide DG-1361 (Proposed Rev. 2 to Reg. Guide 1.89), Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants ML20238B8732020-12-29029 December 2020 Public Comment Resolutions on DG-1362 for RG 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20282A2982020-12-0404 December 2020 DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals ML20282A2992020-12-0404 December 2020 Regulatory Analysis for DG-3055, Rev 0, Regulatory Guide (RG) 3.76, Implementation of Aging Management Requirements for Spent Fuel Storage Renewals ML20210M0472020-12-0101 December 2020 Draft Regulation Guide DG-1288: Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspections of Piping ML20231A8562020-11-30030 November 2020 Draft Regulatory Guide DG-1360, Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants ML20231A8352020-11-30030 November 2020 Draft Regulatory Guide DG-1359, Fire Protection for Nuclear Power Plants ML20307A0462020-11-0202 November 2020 Draft for ACRS Public Meeting, RG 1.200, R3, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20210M0442020-10-28028 October 2020 Regulatory Analysis: Draft Regulatory Guide DG-1288 - an Approach for Plant-Specific, Risk-Informed Decisionmaking for Inservice Inspection of Piping (Proposed Revision 2 of Regulatory Guide 1.178, Dated September 2003) ML20154K5842020-09-17017 September 2020 Results of Periodic Review of Regulatory Guide (RG) 1.78 ML20182A7882020-08-31031 August 2020 DG 1373 for RG 1.240 - Fresh and Spent Fuel Pool Criticality Analyses ML20055G8232020-08-0707 August 2020 DG 1363 for Proposed Rev 4 to Regulatory Guide (RG) 1.105 - Setpoints for Safety-Related Instrumentation Regulatory Guide 3.152020-07-31031 July 2020 Regulatory Guide 3.15. Rev 2, Standard Format and Content of License Applications for Receipt and Storage of Unirradiated Power Reactor Fuel and Associated Radioactive Material at a Nuclear Power Plant Regulatory Guide 1.2362020-07-30030 July 2020 Draft for ACRS Review ML20119A6142020-04-28028 April 2020 Response to Comments for RG 1.236 for ACRS ML20105A4672020-04-14014 April 2020 Memo to OCA - for Revision 1 of Regulatory Guide 8.39, Release of Patients Administered Radioactive Material ML20099F0262020-04-0707 April 2020 Public Comment Resolution Table for DG 1341 (Regulatory Guide (RG) 1.188, Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses, Rev. 2 ML19206A4892020-02-0606 February 2020 Draft Regulatory Guide DG-1287, an Approach for Plant-Specific, risk-Informed Decisionmaking: Technical Specifications ML19116A0772019-08-31031 August 2019 Draft Regulatory Guide DG-5040, Urine Specimen Collection and Test Results Review Under 10 CFR Part 26, Fitness for Duty Programs. ML19203A0892019-07-31031 July 2019 Assessment of the Continued Adequacy of Revision 2 of Regulatory Guide 1.99 - Technical Letter Report 2024-02-02
[Table view]Some use of "" in your query was not closed by a matching "". |
June 1973 U.S. ATOMIC ENERGY COMMISSION
N REGULATORYDIRECTORATE OF REGULATORY STANDARDS
GUIIDE
REGULATORY GUIDE 1.54 QUALITY ASSURANCE REQUIREMENTS FOR PROTECTIVE COATINGS
APPLIED TO WATER-COOLED NUCLEAR POWER PLANTS
A. INTRODUCTION
Coatings Applied to Nuclear Facilities,"' for protective coatings applied to ferritic steels, aluminum, stainless Appendix B to 10 CFR Part 50, "Quality Assurance steel, zinc-coated (galvanized) steel, concrete, or masonry Criteria for Nuclear Power Plants and Fuel Reprocessing surfaces of water-cooled nuclear power plants are Plants," establishes overall quality assurance program generally acceptable and provide an adequate basis for requirements for the design, fabrication, construction, complying with the pertinent quality assurance and operation of safety-related nuclear power plant requirements of Appendix B to 10 CFR Part 50 subject structures, systems, and components. This guide to the following:
describes an acceptable method of complying with the Commission's quality assurance requirements with 1. ANSI N101.4-1972 should be used in conjunction regard to protective coatings applied to ferritic steels, with ANSI N45.2-1971, "Quality Assurance Program aluminum, stainless steel, zinc-coated (galvanized) steel, Requirements for Nuclear Power Plants." 2 concrete, or 'Masonry surfaces of water-cooled nuclear power plants. The Advisory Committee on Reactor 2. Subdivision 2.7 of ANSI N101.4-1972 states that Safeguards has been consulted concerning this guide and when references are made to other standards, these has concurred in the regulatory position. references shall imply the most recent or current editions of the referenced standard
s. The specific
B. DISCUSSION
applicability or acceptability of referenced standards will be covered separately in other regulatory guides, where Subcommittee N101.5.7 of the American National appropriate.
Standards Institute (ANSI) Standards Committee NIO1, Atomic Industry Facility Design, Construction, and 3. Subdivision 1.1.2 of ANSI N101.4-1972 states that Operation Criteria, under the sponsorship of the quality assurance, as covered by this standard, comprises American Institute of Chemical-Engineers, has developed all those planned and systematic actions necessary to a standard which includes quality assurance provide specified documentation and adequate requirements for protective coatings applied to ferritic confidence that shop or field coating work for nuclear steels, aluminum, stainless steel, zinc-coated (galvanized) facilities will perform satisfactorily in service. This steel, concrete, or masonry surfaces of nuclear facilities. statement should not be interpreted as implying that the This standard was approved by the American National end product of quality assurance actions is the Standards Committee N1O0 and its Secretariat. It was production of specified documentation. The term subsequently approved and designated N101.4-1972 by the American National Standards Institute on November 28, 1972. 'Copies may be obtained from the American Institute of Chemical Engineers, 345 East 47th Street, New York, N.Y.
C. REGULATORY POSITION
10017.
'Copies may be obtained from the American Society of The requirements and guidelines included in ANSI Mechanical Engineers, United Engineering Center, 345 East 47th N 10 1.4-1972, "Quality Assurance for Protective Street, New York, N.Y. 10017.
USAEC REGULATORY GUIDES Copies of published guides may be obtained by request Indicating the divisions desired to the US. Atomic Energy Commission. Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public Attention: Director of Regulatory Standards. Comments end suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of Improvements In these guides re encouraged and should be sent to the Secretary the Cornmmssion's regulations, to delineate techniques used by the staff in of the Commission. U.S. Atomic Energy Commission. Washington, D.C. 20545, evluating specific problems or postulated accidents, or to provide guidance to Attention: Chief, Public Proceedings Staff.
applicants. Regulatory Guides are not substitutes for regulations and compliance with them is not required. Methods and solutions different from those set out in The guides ae issued in the following ten broad divisions:
the guides will be acceptable if they provide a besis for the findings requisite to the issuance or continuance of a permit or license by the Commission. 1. Power Reactors
6. Products
7. Research and Test Reactors
7. Transportation
3. Fuels arid Materials Facilities &. Occupational Health Published guides will be revised periodically, asappropriate, to accommodate 4. Environmental and Siting 9. Antitrust Review comments and to reflect new information or experience. 5. Materials and Plant Protection 1
0. General
"quality assurance" as used in ANSI N1OI.4-1972 materials used with stainless steel should not be should be considered to comprise all those planned and compounded from or treated with chemical compounds systematic actions necessary to provide adequate containing elements that could contribute to corrosion, confidence that shop or field coating work for nuclear intergranular cracking, or stress corrosion cracking.
facilities will perform satisfactorily in service. In this Examples of such chemical compounds are those connection it is emphasized that records and documents containing chlorides, fluorides, lead, zinc, copper, sulfur, listed in Subdivisions 7.4 through 7.8, and included in or mercury where such elements are leachable or where the standard, are suggested forms only. Alternate they could be released by breakdown of the chemical documentation consistent with the requirements of compounds under expected environmental conditions Appendix B to 10 CFR Part 50 is also considered (e.g., by radiation). This limitation is not intended to acceptable. prohibit the use of trichlorotrifluoroethane which meets the requirements of Military Specification
4. Sections 3 and 4 of ANSI N101.4-1972 delineate MiL-C-81302b for cleaning or degreasing of austenitic quality assurance requirements for coating materials and stainless steel provided adequate removal is assured prior surface preparation of substrates. Coatings and, cleaning to painting.
1.54-2