Regulatory Guide 3.21

Quality Assurance Requirements for Protective Coatings Applied to Fuel Reprocessing and to Plutonium Processing and Fuel Fabrication Plants

ML003740118
Person / Time
Issue date:	03/31/1974
From:	Office of Nuclear Regulatory Research
To:
References
RG-3.21
Download: ML003740118 (2)

March 1974 U.S. ATOMIC ENERGY COMMISSION

REGULATORY

.DIRECTORATE OF REGULATORY STANDARDS

GUIDE

• . .4 REGULATORY GUIDE 3.21 QUALITY ASSURANCE REQUIREMENTS FOR PROTECTIVE COATINGS

APPLIED TO FUEL REPROCESSING AND TO PLUTONIUM PROCESSING

AND FUEL FABRICATION PLANTS

. I

A. INTRODUCTION

Standards Committee NIO0, Atomic Industry Facility Design, Construction, and Operation Criteria, under the

.7' Appendix B. "Quality Assurance Criteria for sponsorship of the American Institute of Chemical Nuclear Power Plants and Fuel Reprocessing Plants," to Engineers, has developed a standard which include

10 CFR Part 50, "LUcensing of Production and quality assurance requirements for protective coatings Utilization Facilities," establishes quality assurance applied to ferritic steels, aluminum, stainless steel,

<1 A

requirements for the design, construction, and operation of nuclear power plant and fuel reprocessng plant zinc.coated (galvanized) steel, concrete, or masonry surfaces of nuclear facilities. This standard was approved

.4 structures, systems, and components. Paragraph 70.22(f) by the American National Standards Committee NIOI

of 10 CFR Part 70, "Special Nuclear Material," requires and its Secretariat. It was subsequently approved and that each application for a license to possess and use designated NIOI.4-1972 by the American National special nuclear material in a plutonium processing and Standards Institute on November 28,1972.

fuel fabrication plant contain a description of the quality assurance program to be applied to the design,

C. REGULATORY POSITION

fabrication, construction, testing, and operation of the structures, systems, and components of the plant. It further provides that the description indude a discussion The requirements and guidelines included in ANSI

of how the criteria of Appendix B of Part SO wM be NIO.4-1972, "Qiaity Assuranc

e. for Protecijve

.1.

Coatings Applied to Nuclear Facilities," 1 for protective met. Paragraph 70.23(b) of 10 CFR Part 70 provides that the Commission will approve construction of a coatings applied to ferritic steels, aluminum, stainless plutonium processing and fuel fabrication plant when it steel, zinc-coated (Jalvanlzed) steel, concrete, or has determined that the design bases and the quality masonry surfaces of fuel reprocessing and of plutonium assurance program provide reasonable assurance of processing and fuel fabrication plants are generally protection against natural phenomena and the acceptable and provide an adequate basis for complying consequences of potential accidents, noting also that the with the pertinent quality assurance requirements of

• .1 criteria in Appendix B of 10 CFR Part SO will be used in Appendix B to 10 CFR Part 50 subject to the followrin determining the adequacy of the quality assurance I. ANSI NIOI.4-1972 should be used in conjunction program. This Regulatory Guide describes a method with Regulatory Guide 3.3 which refers to N45.2-1971.

acceptable to the Regulatory staff of complying with the "Quality Assurance Program Requirements for Nuclear Commission's regulations with regard to protective Power Plants." 2 coatings applied to ferritic steels, aluminum, stainless steel, zinc.coated (galvanized) steel, concrete, or masonry surfaces of fuel reprocessing or plutonium ' Copies may be obtained from the American Institute os*

Chemical Engineers. 345 East 47th Street, New York. New processing and fuel fabrication plants. York. 10017

B. DISCUSSION

2 Copies may be obtained from the American Society of Mechanical Eqgineers, United Ergineering Center. 345 E-itt 47th Subcommittee NIOI.5.7 of American National Street. New York, New York 10017 USAEC REGULATORY GUIDES COaOs of "K~l#e Guid" "My be Obtained by recslua andoorng the dr.t.'*nt deeled to the US. Atommc Enetgy Commsiton. Wilwngton. OZ. 20bto Regulatorv Guides me Inued to'describe end make avilale to ffth pulic Attention: Dkector of Regulatory Strderdes. Comnts , and sugestions for Methods scaplae to the AIC Regulatatr t ffthtsntimq am SeetIc pW Of inottprt ne In *an ruids we tenmurged nd shiould be set to the enrins the Commisons regultions, to etinaise Wchalque8 teod by ** etaff m of *h Commalon. US. Atomk Energy CommssIion. Washrq*gto. OC. 20e45.

ilusitng Vpecilic problemns or prutuleatd . uM . wr to provide guiddJna tO Alttention: Chief. Public P rpngStaff.

estmntt. Reguletory Guides amrnot subititute far regul*tions ind 001lWitte with them is not quaid. flat?.c, and Wiutic.e dfMe-.tIfror, the. t out i The guibs we issed in the foflowing ton broed divisons th guides will be eccpteble if they pol ae bull for the findinqg reoutite to Siuence or gotinuana of e permIt or ken" bythem CoanMlsw,. 1. Power Reactors S. Products

2. Research end Test Reactors 7. Trnsponrat.o

3. Fuels wd Mteriý , Facilities a. occupetionel Health Pubt*ehed guisdas will, be rUvisted periotdilyl. as Noprf0Wis. to ocomimOffda 4. nwoniientl end Siting A S. Antitrust Review cominntt end to reflSec n iaofuiole euperlena . Mtetrials ard Plat Protection t

0. General

listed in Subdivisions 7.4 through 7.8 and included in Alternute

2. Subdivision 2.7 of ANSI N101.4-1972 states that the standard are suggested forms only. of when references are made to other standards. these documentation consistent with the requirements considered references shall imply the most recent or current Appendix B to 10 CFR Part 50 is also standards. The specific acceptable.

editions of the references or acceptability of referenced standards will applicability delineate MI be covered separately In other regulatory guides or 4. Sections 3 and 4 of ANSI NI01.4-1972 for coating materials and regulations. where appropriate. quality assurance requirements cleaning of substrates. Coatings and surface preparation not be materials used with stainless steel should treated with chemical compounds

3. Subdivision 1.1.2 of ANSI NIO.4-1972 states that compounded from or corrosion.

quality assurance, as covered by this standard, comprises containing dements that could contribute to corrosion cracking.

all of those planned and systematic actions necessary to integranular cracking, or stress compounds are those provide specified documentation and adequate Examples of such chemical sulfur, for nuclear chlorides, fluorides, lead, zinc, copper, confidence that shop or field coating work containing or where

. . 4.

facilities will perform satisfactorily in service. This or mercury where such elements are leachable the breakdown of the chemical statement should not be interpreted as implying that they could be released by actions is the under expected environmental conditions end product of quality assurance compounds to production of specified documentation.

The term (e.g., by radiation). This limitation is not intended meets prohibit the use of trichlorotrifluotoethane which

"quality assurance" as used in ANSI N101.4-1972 should be considered to comprise all those planned and the requirements of Military Specification austenitic systematic actions necessary to provide adequate MIL.C-81 302b for cleaning or degreasing of prior work for nuclear stainless steel provided adequate removal is assured confidence that shop or field coating service. In this to painting.

facilities will perform satisfactorily in connection its .emphasized that records and documents

'1

• ).. *s

3.21-2