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 lection, application, qualification, inspection, and maintenance of protective coatings applied to Nuclear Power Plants.
hyjTitle 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
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be performed GDC 1 also requires licenes to establish and implement a quality assurance (QA) program to provide adequate assurance that the SSCs will satisfactorily perform their safety functions.
GDC 4, “Environmental and Dynamic Effects Design Bas,” 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 accidents.
Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing哈尔滨托福培训学校
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 u in implementing specific parts of the agency’s regulations, techniques that the staff us in evaluating specific problems or postulated accidents, and data that the staff needs in reviewing applications for permits and licens. Regulatory guides are not substitutes for regulations, and compliance with them is not required. Methods and solutions that differ from tho t 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 licen by the Commission.
This guide was issued after consideration of comments received from the public.
Regulatory guides are issued in 10 broad divisions—1, Power Reactors; 2, Rearch 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.
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 v/reading-rm/doc-collections/ and through the NRC’s Agencywide Documents Access and Management System (ADAMS) v/reading-
rm/adams.html, under Accession No. ML102230344. The regulatory analysis may be found in ADAMS under Accession No.
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-r
elated 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 ud in plant emergency operating procedures, (2) who failure could prevent safety-related SSCs from fulfilling their safety-related functions, and (3) who failure could cau a reactor scram or an actuation of a safety-related system. To the extent that protective coatings meet the criteria, the coatings are within the scope of the maintenance rule. The maintenance rule requires the licene 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 the 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 appropriate. Regulatory Guide (RG) 1.160, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,” Revision 2, issued March 1997 (Ref. 2), provides further guidance.
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 3150-0011. 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 number.
B. DISCUSSION
考研英语真题答案NPPs have ud 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 activities. 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 adverly affecting the safety-related SSCs needed to mitigate the accident.
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 NPPs. Protective coatings that met the guidelines would presumably not degrade over the design life of the plant. 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 becau of Construction and Protective Coating Deficiencies and Foreign Material in Conta
inment,” dated July 14, 1998 (Ref. 4). Detached coatings from a substrate that are subquently transported to the intake structures of emergency core cooling systems (ECCSs) may make tho systems unable to satisfy the requirement in
10 CFR 50.46(b)(5) to provide long-term cooling.
Revision 0 to RG 1.54 conditionally endors American National Standards Institute
(ANSI) N101.4-1972, “Quality Assurance for Protective Coatings Applied to Nuclear Facilities” (Ref. 5), and indirectly endors 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),
specifically ASTM Committee D-33 on Protective Coating and Lining Work for Power Generation Facilities.
口才训练视频ASTM has developed appropriate standards to replace ANSI N101.4-1972 and
ANSI N101.2-1972. 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 endorment and regulatory positions on ASTM standards relevant to NPP protective coatings. Since the issuance of Revision 1 to RG 1.54, ASTM has updated many of the standards that RG 1.54 endors to reflect the current industry practice. The NRC is revising RG 1.54 to provide the agency’s regulatory positions on the updated ASTM standards relevant to NPP protective coatings. The NRC has reviewed the ASTM standards cited in Section C of this guide for the lection, qualification, application, and maintenance of protective coatings applied to NPPs and considers them acceptable with the exceptions noted below.
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 N101.4-1972. 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 Ud 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 1.54. ASTM then revid ASTM D 3911-95 as ASTM D 3911-08 (Ref. 11). No
nmandatory Appendix X2 to this standard discuss witness coupons in primary containment. The test coupons, if properly placed, provide a realistic mechanism to test and evaluate the aging of coatings. 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 life. New NPPs should consider the installation of coated test coupons at various locations in the primary containment. The coated test coupons would be reprentative of the aged condition of similar coatings within the primary containment. The licene could u 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 U 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 lected through reproducible evaluation tests. 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 reactors. ASTM D 5144-08 address, by reference, the preparation of test specimens, radiation tolerance testing, the decontaminability of coatings, physical properties, chemical resistance tests, fire evaluation tests, D
BA testing, surface preparation, coating application and inspection, and thermal conductivity testing. Therefore, ASTM D 5144-08 can be viewed as a top-level ASTM standard that provides detailed requirements through reference to other key ASTM standards. Figure 1 shows the additional ASTM standards that provide application-specific guidance; the standards are discusd below.
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 reactors. New reactor designs may u design features that are different from the operating reactors that formed the basis for this RG, and, therefore, adjustments may be necessary. 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 ECCS. Therefore, this RG provides guidance for new reactor designs with the recognition that the licene or applicant may need to adjust some features bad on the particular plant design.
C. REGULATORY POSITION
1.Guidance in American Society for Testing and Materials Standards火影片尾曲
ASTM D 5144-08 and the other ASTM standards discusd below provide guidance on practices and programs that the NRC staff finds acceptable for the lection, application, qualification, inspection, and maintenance of protective coatings applied to NPPs. ASTM Committee D-33 has defined Service Level I, II, and III coating locations to include both safety-related and nonsafety-relat
ed regions as t forth below.
Service Level I, II, and III coatings are defined as follows:
a.Service Level I coatings are ud in areas inside the reactor containment where coating failure
exchangedcould adverly affect the operation of postaccident fluid systems and thereby impair safe
shutdown.
b.Service Level II coatings are ud in areas where coating failure could impair, but not prevent,
normal operating performance. The functions of Service Level II coatings are to provide
corrosion protection and decontaminability1 in tho areas outside the reactor containment that
are subject to radiation exposure and radionuclide contamination. Service Level II coatings are not safety related.
c.Service Level III coatings are ud in areas outside the reactor containment where failure could
adverly affect the safety function of a safety-related SSC. (Note that a coating on the external surface of a reactor containment may be designated Service Level III, although no plants licend 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: a.When using this RG, NRC licenes 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 descriptions.
b.Applicants for design certifications and combined licens under 10 CFR Part 52, “Licens,服装配饰
Certifications, and Approvals for Nuclear Power Plants,” (Ref. 14) may propo to u coatings in ways that do not conform to the rvice level definitions above. For example, an applicant
could propo to designate coatings in certain areas of containment as Service Level II bad on an evaluation that demonstrates that the coatings cannot be transported to the ECCS. 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 report.
1ASTM withdrew ASTM D 4256-94, “Test Method for Determination of the Decontaminability of Coatings Ud 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 test. In addition, this test method generates mixed hazardous waste and does not comply with occupational do as low as reasonably achievable practices.
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 facilities. Licenes may u 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 facilities.
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ASTM D 5139-10, “Standard Specification for Sample Preparation for Qualification Testing of Coatin
gs To Be Ud 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 u 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 U 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 conditions.
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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 samples. ASTM D 3911-08 does not specify minimum acceptance criteria. For Service Level I coatings, licenes or applicants shall meet the following minimum acceptance criteria:
a.Peeling and delamination shall not be permitted.
b.Cracking is not considered a failure unless it is accompanied by delamination or loss of adhesion.
c.Blisters shall be limited to intact blisters that are completely surrounded by sound coating bonded
to the surface.
The licene 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 coatings.
ASTM D 3912-10, “Standard Test Method for Chemical Resistance of Coatings and Linings for U 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 NPPs.
3.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 facilities. This standard provides guidance on the inspection of the education, tra
ining, experience, qualifications, and certification of Service Level I, II, and III coatings inspectors.
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 facilities.
