ML20204E627
| ML20204E627 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1999 |
| From: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| To: | |
| References | |
| TASK-*****, TASK-RE REGGD-01.054, REGGD-1.054, NUDOCS 9903250087 | |
| Download: ML20204E627 (12) | |
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.a u % U.S. NUCLEAR REGULATORY COMMISSION March 1999
/ \ OFFICE OF NUCLEAR RF.3ULATORY RESEARCH ' vision 1 A
[ j Draf t DG-1076
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DRAFT REGULATORY GUIDE
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Contact:
A.W. Serkiz (301)415-6583 DRAFT REGULATORY GUIDE DG-1076 (Proposed Revision 1 to Regulatory Guide 1.54)
SERVICE LEVEL 1, ll, AND lli PROTECTIVE COATINGS APPLIED TO NUCLEAR POWER PLANTS A. INTRODUCTION [$h sw( \
In Appendix A to 10 CFR Part 50, " General Design Criteria for,Nudicar Power Plants,"
b Criterion 1, " Quality Standards and Records," requires that structures, syst' ems, and components important to safety be designed, fabricated, erected, and tested td'qudlity3siandards commensurate with the importance of the safety functions to be performed tAppendi4A' also requires that a quality assurance program be established and implemented in order tohroyide" adequate assurance that these structures, systems, and components will satisfactoriinpefforr'n their safety functions.
g Q2 In Appendix A to 10 CFR Part 50, Criterion 4, "En'vironmental and Dynamic Effects Design Bases," requires that structures, systems, and coiT1pgrientsI(SSCs) important to safety be designed to be compatible with the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including;foislof-cholant accidents.
R y In 10 CFR Part 50, Appendix BNOdility;Aksurance Criteria for Nuclear Power Plants and
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Fuel Reprocessing Plants," establishO overall quality assurance program requirements for the design, fabrication, construction, and operation of s' 'afety-related nuclear power plant SSCs.
M The maintenance rule,10 CFR 50.65, " Requirements for Monitoring the Effectiveness of Maintenance at Nuclearf6ker Plants," includes in its scope all safety-related SSCs and those non-safety-related SSCs: (1kthat sire relied upon to mitigate accidents or transients or are used in plant emergency operating gobeifure's; (2) whose failure could prevent safety-related SSCs from fulfilling their safety-related function 1nd (3) whose failure could cause a reactor scram or an actuation of a safety-related,sy5(em. To the extent that protective coatings meet these criteria, they are within the scope of theEainfriradr'n rn!p ,Tha maintonance rule requires that licensees monitor the 3 9903250087 990331
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PDR REGOD /
01,054 R PDR This regulatory guide is being issued in draf t form to involve the public in the development of a regulatory position in this area. As a draf t being issued for public comment, it does not represent an official NRC staff position.
Public comments are being solicited on the draf t guide (including any implementation schedule) and its associated regulatory analysis or value/ impact statement. Comments should be accompanied by appropriate supporting data. Written comments may be submitted to the Rules C')Wh)
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- and Directives Branch, office of Administration, u.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. Copies of comments
\ received may be examined at the NRC Public Document Room,2120 L Street NW., Washington, DC. Comments will be most helpful if received by July 30,1999. l[' 47 Requests for single copies of draf t or active regulatory guides (which may be reproduced) or for placement on an automatic distribution list for single copies of future draf t guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, OC 20555-0001 Attention: Reproduction and Distribution Services Section, or by f ax to (301)415-2289; or email to DISTRIBUTION @NRC. GOV.
effectiveness of maintenance for these protective coatings (as discrete systems or components or as part of any SSC) in accordance with 10 CFR 50.65(a)(1) or (a)(2), as appropriate. Further guidance is provided in Revision 2 of Regulatory Guide 1.160,
" Monitoring the Effectiveness of Maintenance at Nuclear Power Plants" (Ref.1).
This revision to Regulatory Guide 1.54 is being developed in accordance with Public Law 104-113, OMB Circular A-119, and NRC's Strategic Plan for FY 1997 - 2002, which encourages industry to develop codes, standards, and guides that can be endorsed by the NRC and carried out by industry. The ASTM standards cited in the Regulatory Position of this guide for the selection, qualification, application, and maintenance of protective coatings in nuclear power plants have been reviewed by the NRC staff and found to be acceptable with the exceptions noted.
Regulatory guides are issued to describe so the public methods acceptable to the NRC staff for implementing speufic parts of the NRC's regulations, to explain techniques used by the staff in evaluating specific problems or postulated accidents, and to provide guidance to applicants. Regulatory guides are not substitutes for regulations, and compliance with regulatory guides is not required. Regulatory guides are issued in draft form for public comment to involve the public in developing the regulatory positions and, therefore, such draft regulatory guides do not represent official NRC staff positions.
The information collections contained in this draft regulatory guide are covered by the requirements of 10 CFR Part 50, which were approved by the Office of Management and Budget, approval number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number.
B. DISCUSSION Protective coatings (paints) have been used extensively in nuclear power plants to protect the surfaces of facilities and equipment from 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 Regulatory Guide 1.54, the regulations cited above require that protective coatings be qualified and capable of surviving i I
a design basis 3ccident (DBA) without adversely affecting safety-related SSCs needed to mitigate the accident.
In July 1973, Regulatory Guide 1.54, " Quality Assurance Requirements' for Protective Coatings Applied to Water-Cooled Nuclear Power Plants," was issued to describe an acceptable method for complying with the NRC's quality assurance requirements with regard to protective coatings applied to ferritic steels, aluminum, stainless steel, zinc-coated (galvanized) steel, concrete, or masonry surfaces of water-cooled nuclear power plants. The presumption was that protective coatings that met these guidelines would 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 (Ref. 2).
Detached coatings from the substrate that are transported to emergency core cooling system intake structures may make those systems unable to satisfy the requirement in 10 CFR 50.46(b)(5) to provide long-term cooling.
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\ Regulatory Guide 1.54 conditionally endorsed ANSI N101.4, " Quality Assurance for Protective Coatings Applied to Nuclear Facilities," and indirectly endorsed guidance provided in ANSI N101.2, " Protective Coatings (Paints) for Light Water Nuclear Reactor Containment Facilities." ANSI N101.4 and N 101.2 were formally withdrawn in 1988; responsibility for updating, rewriting, and issuing appropriate replacement standards was transferred to the American Society for Testing and Materials (ASTM), specifically ASTM Committee D-33 on Protective Coating and Lining Work for Power Generation Facilities. However, Regulatory Guide 1.54 was not revised as new ASTM Standards were developed for the application and maintenance of NPP protective coatings.
ASTM D 3843-93, " Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities" (Ref. 3), was approved and issued by ASTM as a partial replacement for ANSI N101.4. 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. 4), has been approved and issued by ASTM to replace the DBA test standard that was referenced in ANSI N101.4 and Regulatory Guide 1.54.
ASTM D 5144-97, " Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants" (Ref. 5), has been developed and issued by the ASTM to provide a common basis on which protective coatings for the surfaces of nuclear power generating f acilities may be qualified and selected by reproducible evaluation tests. This ASTM standard provides guidance for the application and maintenance of protective coatings under the rg expected environmental, operating, and postulated accident conditions for pressurized water
( reactors (PWRs) and boiling water reactors (BWRs).
C. REGULATORY POSITION
- 1. GUIDANCE IN ASTM STANDARDS ASTM D-5144-97 (Ref. 5) and the other ASTM standards discussed below provide l guidance on practices and programs that are acceptable to the NRC staff for the selection, application, qualification, inspection, and maintenance of protective coatings applied in nuclear power plants.
The quality assurance provisions and guidance contained in the standards in this Regulatory Position are generally acceptable and provide methods acceptable to the NRC staff for complying with the pertinent quality assurance requirements of Appendix B to 10 CFR Part 50 subject to the following two exceptions.
(1) .ien using this regulatory guide, NRC licensees should meet the quality assurance provisions and guidance contained in the standards in this regulatory guide and must also meet the commitments and provisions contained in their Quality Assurance Program Description.
p (2) Service Level I, ll, and til coatings are defined as:
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Service Level I coatings are used in areas where the coating failure could adversely l affect the operation of post-accident fluid systems and thereby impair safe shutdown.
l With few exceptions, Service Level 1 applies to coatings inside primary containment.
l Service Level 11 coatings are used in areas where coatings failure could impair, but not prevent, normal operating performance. The functions of Service Level 2 coatings are to provide corrosion protection and to improve the ability to decontaminate those areas outside primary containment that are subject to radiation exposure and radionuclide contamination.
Service Level Ill coatings are used on any exposed surface area located outside containment whose failure could adversely affect normal plant operation or orderly and safe plant shutdown.
ASTM D-5144-97 (Ref. 5) addresses by reference the preparation of test specimens, radiation tolerance testing, decontaminability of coatings, physical properties, chemical resistance tests, fire evaluation tests, DBA testing, surface preparation, coating application and inspection, and thermal conductivity testing. Therefore, ASTM D 5144-97 can be viewed as a top-level ASTM standard that incorporates by reference other key ASTM standards as shown in Figure 1.
- 2. QUALITY ASSURANCE ASTM D 3843-93 (Ref. 3) provides quality assurance practices that are acceptable to the NRC staff and are applicable to safety-related protective coating work in coating Service LevelI areas of nuclear facilities. Applicable portions of practices described may be used as the basis for limited quality assurance for protective coating work in coating Service Level 11 areas of nuclear facilities.
ASTM D 5139-96 (Ref. 6) provides guidance that is acceptable to the NRC staff on the size, composition, and surface preparation for test samples of protective coatings for use in qualification testing of coatings to be used in nuclear power plants as described in ASTM D 391195 and D 4082-95 (Refs 4 and 7).
ASTM D 3911-95 (Ref. 4) provides guidance that is acceptable to the NRC staff on procedures for evaluating protective coating systems tE& ..oecimens under simulated DBA conditions. ASTM D 3911-95 also provides guidance on Londitions and test apparatus for temperature-pressure testing, conditions for radiation testing, and procedures for preparing, examining, and evaluating samples.
ASTM D 4082-95 (Ref. 7) provides a standard test method that is acceptable to the NRC staff for evaluating the effects of gamma radiation on the lifetime radiation tolerance of Service Level I and ll coatings.
ASTM D 4537-96 (Ref. 8) provides guidance that is acceptable to the NRC staff on the qualification and certification of personnel who inspect protective coatings in nuclear facilities. This standard provides guidance on inspection of the education, training, experience, qualifications, and certification of Level I, ll, and 111 coating inspectors.
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- 3. TRAINING AND QUALIFICATION OF PROTECTIVE COATINGS INSPECTORS AND COATING APPLICATORS ASTM D 5498 94 (Ref. 9) provides guidance acceptable to the NRC staff for persons responsible for developing a training program for the indoctrination and training of personnel for inspecting coating work in nuclear facilities and also recommends areas of proficiency that are embodied in the ASTM standards shown in Table 1 in ASTM D 5498-94.
ASTM D4227-95 (Ref.10) provides guidance acceptable to the NRC staff for the qualification of coatings applicators to verify that they are proficient and able to attain the quality required for applying specified coatings to concrete surfaces, including those in a nuclear facility.
ASTM D4228-95 (Ref.11) provides guidance acceptable to the NRC staff for the qualification of coatings applicators to verify that they are proficient and able to attain the quality required for applying specified coatings to steel surfaces, including those in a nuclear facility.
ASTM D4286-96 (Ref.12) provides criteria and methods that are acceptable to the NRC staff to assist utility owners, architects, engineers, and contractors in determining the overall qualifications of a coatings contractor to execute coating work for the primary containment and other safety-related facilities of nuclear power plants. The criteria and requirements for contractors address the contractor's essential basic capability to execute O, nuclear coating work.
- 4. MAINTENANCE OF COATINGS ASTM D 5163 96 (Ref.13) provides guidelines that are acceptable to the NRC staff for establishing an in-service coatings monitoring program for Service Level I coating systems in operating nuclear power plants and for Service Level Il and other areas outside containment (as applicable).
ASTM D 454195 (Ref.14) provides guidance acceptable to the NRC staff for a procedure for evaluating the pull-off strength of coatings using fixed-alignment adhesion testers.
ASTM D 3359-95, Revision A (Ref.15), provides guidance that is acceptable to the NRC staff on test methods for measuring adhesion using tape tests.
ASTM D 5962 96 (Ref.16) provides guidance that is acceptable to the NRC staff on maintaining unqualified coatings (paints) within LevelI areas of a nuclear power facility.
- 5. ASTM STANDARD TERMINOLOGY ASTM D4538 95 (Ref.17) defines standard terms related to protective coating and lining work for power generation facilities that are acceptable to the NRC staff and that are also applicable to protective coatings employed in nuclear power plants.
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- 6. ADDITIONAL INFORM ATION Additionalinformation on the selection, application, inspection, and maintenance of nuclear plant safety-related protective coatings is provided in EPRI Report TR-109937 (Ref.
18), which provides a detailed discussion of important considerations related to protective coatings and can be used to supplement the ASTM Standards guidelines as deemed necessary.
D. IMPLEMENTATION The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plans for using this regulatory guide.
This proposed revision has been released to encourage public participation in its development. Except in those cases in which an applicant proposes an acceptable alternative method for complying with the portions of the NRC's regulations specified in this guide, the methods and guidance to be described in the final guide will reflect public comments received and will be used in the evaluation of submittals in connection with applications for construction permits, operating licenses, and combined licenses. Current
, licensees may, at their option, comply with the guidance in this regulatory guide. Any I
applicable requirements for changing the licensing basis to raflect the change must be followed.
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l REFERENCES
- 1. USNRC, " Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,"
Regulatory Guide 1.160, Revision 2, March 1997.
- 2. USNRC, " 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 Materialin Containment," Generic Letter 98-04, July 14,1998.
- 3. American Society for Testing and Materials, " Standard Practice for Quality Assurance for Protective Coatings Applied to Nuclear Facilities," ASTM D 3843-93.
- 4. American Society for Testing and Materials, " Standard Test Method for Evaluating Coatings Used in Light-Water Nuclear Power Plants at Simulated Design Basis Accident (DBA) Conditions," ASTM D 3911-95.
- 5. American Society for Testing and Materials, " Standard Guide for Use of Protective Coating Standards in Nuclear Power Plants," ASTM D 5144-97.
- 6. American Society for Testing and Materials, " Standard Specification for Sample Preparation for Qualification Testing of Coatings To Be Used in Nuclear Power Plants," ASTM D 5139-90 (Reapproved 1996).
- 7. American Society for Testing and Materials, " Standard Test Method for Effects of Gamma Radiation on Coatings for Use in Light-Water Nuclear Power Plants," ASTM D408 2-95.
- 8. American Society for Testing and Materials, " Standard Guide for Establishing Procedures To Qualify and Certify inspection Personnel for Coating Work in Nuclear j Facilities," ASTM D 4537-91 (Reapproved 1996).
- 9. American Society for Testing and Materials, " Standard Guide for Developing a .
Training Program for Coating Work Inspectors in Nuclear Facilities," ASTM D 5498- 1 94.
- 10. American Society for Testing and Materials, " Star'dard Practice for Qualification of Coating Applicators for Application of Coatings to Concrete Surfaces," ASTM D4227-95.
- 11. American Society for Testing and Materials, " Standard Practice for Qualification of Coating Applicators for Application of Coatings to Steel Surfaces." ASTM D4228 95.
- 12. American Society for Testing and Materials, " Standard Practice for Determining Coating Contractor Qualifications for Nuclear Powered Electric Generation Facilities,"
ASTM D4286-90 (Reapproved 1996).
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- 13. American Society for Testing and Materials, " Standard Guide for Establishing Procedures To Monitor the Performance of Safety Related Coatings in an Operating Nuclear Power Plant," ASTM D5163-96.
- 14. American Society for Testing and Materials, " Standard Test Method for Pull-Off Strength of Coatings Using Portable Adhesion Testers," ASTM D 4541-95.
- 15. American Society for Testing and Materials, " Standard Test Methods for Measuring Adhesion by Tape Test," ASTM D-3359-95, Revision A.
- 16. American Society for Testing and Materials, " Standard Guide for Maintaining Unqualified Coatings (Paints) Within Level l Areas of a Nuclear Power Facility," ASTM D 5962-96.
- 17. American Society for Testing and Materials, " Standard Terminology Relating to Protective Costing and Lining Work for Power Generation Facilities," ASTM D 4538-95.
- 18. Electric Power Research Institute, " Guidelines on the Elements of a Nuclear Safety-Related Coatings," EPRI Report TR-109937, March 1998.
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REGULATORY ANALYSIS The guidance in Regulatory Gaide 1.54, " Quality Assurance Requirements for Protective Coatings Applied to Wah r-Cooled Nuclear Power Plants," has become outdated because the ANSI standards endorsed by the guide have been withdrawn and replaced by ASTM standards. Public Law 104-113, OMB Circular A-119, and NRC's Strr'99 ic P!an for FY1997-2002 encourage, tb9 use of codes, standards, and guides that have been developed by industry and that can be endorsed by the NRC and carried out by industry.
The most cost-beneficial method to update the guidance in Regulatory Guide 1.54 would be to issue a revision of Regulatory Guide 1.54 that endorses updated ASTM standards.
BACKFIT ANALYSIS The proposed regulatory guide does not require a backfit analysis as described in 10 CFR 50.109(c) because this regulatory guide will not require backfitting as described in 10 CFR 50.109(a)(1): rather, this regulatory guide will provide guidance that the lironsec may choose to use.
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