Regulatory Guide 1.26: Difference between revisions

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{{Adams
{{Adams
| number = ML070290283
| number = ML003739964
| issue date = 03/12/2007
| issue date = 02/29/1976
| title = Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants
| title = For Comment, Quality Group Classifications & Standards for Water-,Steam & Radioactive-Waste-Containing Components of Nuclear Power Plants
| author name = Hixon J
| author name =  
| author affiliation = NRC/RES/DFERR/DDME/FAITB
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = Hixon, J B, RES/DFERR, (301) 415-5205
| contact person =  
| case reference number = DG-1152
| document report number = RG-1.06, Rev 3
| document report number = RG-1.026, Rev. 4
| package number = ML070180354
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 8
| page count = 3
}}
}}
{{#Wiki_filter:1 In editions of the ASME Boiler and Pressure Vessel Code published before 1971, Section III uses the terms Class A,
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION  
Class B, and Class C in lieu of Class 1, Class 2, and Class 3.
REGULATORY GUIDE  
 
OFFICE OF STANDARDS DEVELOPMENT
The U.S. Nuclear Regulatory Commission (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 agencys regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff need 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 Commission.
REGULATORY GUIDE 1.26 QUALITY GROUP CLASSIFICATIONS AND STANDARDS FOR
 
WATER-, STEAM-, AND RADIOACTIVE-WASTE-CONTAINING  
This guide was issued after consideration of comments received from the public.  The NRC staff encourages and welcomes comments and suggestions in connection with improvements to published regulatory guides, as well as items for inclusion in regulatory guides that are currently being developed.
COMPONENTS OF NUCLEAR POWER PLANTS
 
The NRC staff will revise existing guides, as appropriate, to accommodate comments and to reflect new information or experience.  Written comments may be submitted to the Rules and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
 
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, General.
 
Requests for single copies of draft or active regulatory guides (which may be reproduced) should be made to the U.S. Nuclear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to (301) 415-2289; or by email to Distribution@nrc.gov.
 
Electronic copies of this guide and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRCs Electronic Reading Room at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML070290283.
 
U.S. NUCLEAR REGULATORY COMMISSION
March 2007 Revision 4 REGULATORY GUIDE
OFFICE OF NUCLEAR REGULATORY RESEARCH
REGULATORY GUIDE 1.26 (Draft was issued as DG-1152, dated November 2006)
QUALITY GROUP CLASSIFICATIONS AND STANDARDS
FOR WATER-, STEAM-, AND
RADIOACTIVE-WASTE-CONTAINING COMPONENTS
OF NUCLEAR POWER PLANTS


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criterion 1, Quality Standards and Records, as set forth in Appendix A,
General Design Criterion 1, "Quality Standards and Records," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," requires that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Section 50.55a,
General Design Criteria for Nuclear Power Plants, to Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50), Licensing of Production and Utilization Facilities (Ref. 1), requires that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed.
"Codes and Standards," of 10 CFR Part 50 requires that components of the reactor coolant pressure boundary be designed, fabricated, erected, and tested in accordance with the requirements for Class 11 components of Section III of the ASME Boiler and Pressure Vessel or equivalent quality standard


Under 10 CFR 50.55a, Codes and Standards, certain systems and components of boiling- and pressurized-water-cooled nuclear power reactors must be designed, fabricated, erected, and tested in accordance with the standards for Class 1, 2, and 31 components given in Section III, Nuclear Power Plant Components, of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Ref. 2) or equivalent quality standards.  This guide describes a quality classification system related to specified national standards that may be used to determine quality standards acceptable to the staff of the U.S. Nuclear Regulatory Commission (NRC) for satisfying General Design Criterion 1 for other safety-related components containing water, steam, or radioactive material in light-water-cooled nuclear power plants.
====s. This guide desc a ====
quality classification system related to specified na alU
standards that may be used to det r er standards acceptable to the NRC staff satisnmg General Design Criterion 1 for other )ety-r ed components containing water, steam, or tive material in light-water-cooled nuclear power plan B. DISd After reviewing r
pplications for con struction permits v ope* glicenses and after dis cussions with r"
tativ of professional societies and industr fe lO
has developed a quality classification for safety-related components con taining water, or radioactive material in water cooled nuc po r plants. The system consists of four
'Editions prior to 1971 of the ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," use the term Class A in lieu of Class 1.


2 Regulatory Guide 1.143, Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants (Ref. 4), provides specific guidance on the classification of radioactive waste management systems.
Revision 3 February 1976 USNRC REGULATORY GUIDES
Comments should be sent to the Secretary of the Commission. U.S. Nuclear ReglaorReguletorv Commission, Washington. D.C.


Rev. 4 of RG 1.26, Page 2 This regulatory guide contains information collections that are covered by the requirements of 10 CFR Part 50 which 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.
05 Attention: Docketing and Regulatory Guides are issued to describe and make available to the public segulato c0
methods acceptable to the NRC staff of implementing specific parts of the ice Section.


==B. DISCUSSION==
Commission's regulations, to delineate techniques used by the staff in evalu.
In the early 1970s, the NRC staff developed a quality classification system to provide licensees with guidance for satisfying General Design Criterion 1.  The system consists of four quality groups, A through D; methods for assigning components to those quality groups; and specific quality standards applied to each quality group.  When the NRC issued Revision 2 of this guide in June 1975 and Draft Revision 3 for public comment in February 1976, 10 CFR 50.55a required only that components of the reactor coolant pressure boundary be designed, fabricated, erected, and tested to the highest available national standards; this corresponded to the quality standards for Quality Group A of the NRC
system.  On March 15, 1984, the Commission published a final rule (Ref. 3) amending 10 CFR 50.55a to incorporate by reference the criteria in Section III of the ASME Code, as they relate to the design and fabrication of Class 2 and 3 components (Quality Group B and C components, respectively).
Because the quality group classification system is well-established, this Revision 4 of Regulatory Guide 1.26 retains the method described in previous versions for determining acceptable quality standards for Quality Group B, C, and D components.  Other systems not covered by this guide, such as instrument and service air, diesel engines and their generators and auxiliary support systems, diesel fuel, emergency and normal ventilation, fuel handling, and radioactive waste management systems,2 should be designed, fabricated, erected, and tested to quality standards commensurate with the safety function to be performed.


The evaluation to establish the quality group classification of these other systems should consider the guidance provided in Regulatory Positions 1 and 2 of this guide.
The guideseare issued inthe following ten broad divisions:
eting specific problems or postulated accidents, or to provide guidance to appli cants. Regulatory Guides are not substitutes tor regulations, and compliance I. Power Reactors
6. Products with them is not required. Methods and solutions different from those set out in
2. Research and Test Reactors
7. Transportation the guides will be acceptable if they provide a basis for the findings requisite to
3. Fuels and Materials Facilities
8. Occupational Health the issuance or continuance of a permit or license by the Commission
4ý Environmental and Siting
9. Antitrust Review Comments and suggestions for improvements in these iuides are encouraged
5. Materials and Plant Protection
10 General at all times, and guides will be revised, as appropriate, to accommodate com ments and to reflect new information or experience. However. comments on Copies of published guides may be obtained by written request indicating the this guide. if received within about two months after its issuance, will be per- divisions desired to the U.S. Nuclear Regulatory Commission. Washington. D.C.


3 The regulations in 10 CFR 50.55a specify the Quality Group A standards for pressure-containing components of the reactor coolant pressure boundary.
ticularly useful in evaluating the need for an early revision
20655. Attention: Director. Office of Standards Development.


4 The system boundary includes those portions of the system necessary to accomplish the specified safety function and connected piping up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure when the safety function is required.
quality groups, A throu me s for assigning components to these alit oups, d the specific quality standards app*
quality group. The initial portion of t sy is cribed in §50.55a of  
10 CFR Part 50.


5 The turbine stop valve and turbine bypass valve, although not included in Quality Group B, should be subjected to a quality assurance program at a level generally equivalent to Quality Group B.
"cre s that components of the reactor coolant e
 
undary be designed, fabri cated, ere an d to the highest available national st M
Rev. 4 of RG 1.26, Page 3
s corresponds to the quality stan d g
r quality Group A of the NRC
system_ .
e describes a method for determining tab onty standards for the remaining safety r
colonents containing radioactive material, a
steam, i.e., quality Group B, C, and D
Shnents. Other systems not covered by this guide, ch as instrument and service air, diesel engine and its erators and auxiliary support systems, diesel fuel, emergency and normal ventilation, fuel handling, and radioactive waste management systems,2 should be designed, fabricated, erected, and tested to quality standards commensurate with the safety function to be performed. Evaluation to establish the quality group classification of these other systems should include consideration of the guidance provided in regulatory positions C.1 and C.2 of this guide.


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
1.
1. The Group B quality standards given in Table 1 of this guide should be applied to water- and steam containing pressure vessels, heat exchangers (other than turbines and condensers), storage tanks, piping, pumps, and valves that are either part of the reactor coolant pressure boundary defined in §50.2(v) but excluded
'Specific guidance on the quality group classification of radio- I
active waste management systems is under development.


Quality Group B
*Lines indicate substantive changes from previous issue.
The Quality Group B standards given in Table 1 of this guide should be applied to water- and steam-containing pressure vessels, heat exchangers (other than turbines and condensers), storage tanks, piping, pumps, and valves that are either (1) part of the reactor coolant pressure boundary defined in
10 CFR 50.2 but excluded from the requirements of 10 CFR 50.55a3 pursuant to paragraph (c)(2)
of that section, or (2) not part of the reactor coolant pressure boundary but part of the following:
(a)
systems or portions of systems4 important to safety that are designed for (i) emergency core cooling, (ii) postaccident containment heat removal, or (iii) postaccident fission product removal (b)
systems or portions of systems5 important to safety that are designed for (i) reactor shutdown or (ii) residual heat removal (c)
those portions of the steam systems of boiling-water reactors extending from the outermost containment isolation valve up to but not including the turbine stop and bypass valves,5 and connected piping up to and including the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation; alternatively, for boiling-water reactors containing a shutoff valve (in addition to the two containment isolation valves)
in the main steamline and the main feedwater line, those portions of the steam and feedwater systems extending from the outermost containment isolation valves up to and including the shutoff valve or the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation (d)
those portions of the steam and feedwater systems of pressurized-water reactors extending from and including the secondary side of steam generators up to and including the outermost containment isolation valves, and connected piping up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure during all modes of normal reactor operation (e)
systems or portions of systems5 that are connected to the reactor coolant pressure boundary and are not capable of being isolated from the boundary during all modes of normal reactor operation by two valves, each of which is either normally closed or capable of automatic closure


6 Components in influent lines may be classified as Quality Group D if they are capable of being isolated from the reactor coolant pressure boundary by an additional valve that has high leaktight integrity.
from the requirements of §50.55a3 pursuant to foot note 2 of that section or not part of the reactor coolant pressure boundary but part of:
a. Systems or portions of systems4 important to safety that are designed for (1) emergency core cooling,
(2) postaccident containment heat removal, or (3) post accident fission product removal.


Rev. 4 of RG 1.26, Page 4
b. Systems or portions of systems4 important to safety that are designed for (1) reactor shutdown or
2.
(2) residual heat removal.


Quality Group C
c. Those portions of the steam systems of boiling water reactors extending from the outermost contain ment isolation valve up to but not including the turbine stop and bypass valvess and connected piping up to and including the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation. Alternatively, for boiling water re actors containing a shutoff valve (in addition to the two containment isolation valves) in the main steam line and in the main feedwater line, Group B quality standards should be applied to those portions of the steam and feedwater systems extending from the outermost con tainmen/t isolation valves up to and including the shutoff valve or the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation.
The Quality Group C standards given in Table 1 of this guide should be applied to water-, steam-,
and radioactive-waste-containing pressure vessels; heat exchangers (other than turbines and condensers);
storage tanks; piping; pumps; and valves that are not part of the reactor coolant pressure boundary or included in Quality Group B but part of the following:
(a)
cooling water and auxiliary feedwater systems or portions of those systems5 important to safety that are designed for (i) emergency core cooling, (ii) postaccident containment heat removal, (ii) postaccident containment atmosphere cleanup, or (iv) residual heat removal from the reactor and from the spent fuel storage pool (including primary and secondary cooling systems),
although Quality Group B includes portions of those systems that are required for their safety functions and that (i) do not operate during any mode of normal reactor operation and (ii) cannot be tested adequately (b)
cooling water and seal water systems or portions of those systems5 important to safety that are designed for the functioning of components and systems important to safety, such as reactor coolant pumps, diesels, and the control room (c)
systems or portions of systems5 that are connected to the reactor coolant pressure boundary and are capable of being isolated from that boundary during all modes of normal reactor operation by two valves, each of which is either normally closed or capable of automatic closure6 (d)
systems, other than radioactive waste management systems3, not covered by Regulatory Positions
2(a) through 2(c) (above) that contain or may contain radioactive material and whose postulated failure would result in conservatively calculated potential offsite doses [using meteorology as recommended in Regulatory Guide 1.3, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling-Water Reactors (Ref. 5),
and Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized-Water Reactors (Ref. 6)]
that exceed 0.5 rem to the whole body or its equivalent to any part of the body; only single component failures need be assumed for those systems located in Seismic Category I structures, and no credit should be taken for automatic isolation from other components in the system or for treatment of released material, unless the isolation or treatment capability is designed to the appropriate seismic and quality group standards and can withstand loss of offsite power and a single failure of an active component


Rev. 4 of RG 1.26, Page 5
d. Those portions of the steam and feedwater systems of pressurized water reactors extending from and including the secondary side of steam generators up to and including the outermost containment isolation valves and connected piping up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure during all modes of normal reactor operation.
3.


Quality Group D
e. Systems or portions of systems 4 that are connected to the reactor coolant pressure boundary and are not capable of' being isolated from the boundary during all modes of normal reactor operation by two valves, each of which is either normally closed or capable of automatic closure.
The Quality Group D standards given in Table 1 of this guide should be applied to water- and steam-containing components that are not part of the reactor coolant pressure boundary or included in Quality Groups B or C, but are part of systems or portions of systems that contain or may contain radioactive material.


Table 1 Components QUALITY STANDARDS
2. The Group C quality standards given in Table 1 of this guide should be applied to water-, steam-, and  
Quality Group B
3Group A quality standards that are required for pressure containing components of the reactor coolant pressure bound ary are specified in Section 50.55a of 10 CFR Part 50.
Quality Group C
Quality Group D
Pressure Vessels ASME Boiler and Pressure Vessel Code, Section III,
Rules for Construction of Nuclear Facility Components,a,b Class 2 ASME Boiler and Pressure Vessel Code, Section III,
Rules for Construction of Nuclear Facility Components,a,b Class 3 ASME Boiler and Pressure Vessel Code, Section VIII,
Division 1, Rules for Construction of Pressure Vessels (Ref. 7)
Piping As above As above ASME B31.1 (Ref. 8)
Pumps As above As above Manufacturers standards Valves As above As above ASME B31.1 (Ref. 8)
Atmospheric Storage Tanks As above As above API-650 (Ref. 9),
AWWA D-100 (Ref. 10),
or ASME B96.1 (Ref. 11)
0-15 psig Storage Tanks As above As above API-620 (Ref. 12)
a See 10 CFR 50.55a for guidance regarding the ASME Code and addenda to be applied.


b Other regulatory guides or Commission regulations cover the specific applicability of code cases, where appropriate.
"4The system boundary includes those portions of the system required to accomplish the specified safety function and connected piping up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of aitomatic closure when the safety function is required.


Applicants proposing the use of code cases not covered by guides or regulations should demonstrate that an acceptable level of quality and safety would be achieved.
$The turbine stop valve and the turbine bypass valve, although not included in quality group B, should be subjected to a quality assurance program at a level generally equivalent to quality group B.


Rev. 4 of RG 1.26, Page 6
radioactive-waste-containing pressure vessels, heat ex changers (other than turbines and condensers), storage tanks, piping, pumps, and valves not part of the reactor coolant pressure boundary or included in quality Group B but part of:
a. Cooling water and auxiliary feedwater systems or portions of these systems4 important to safety that are designed for (1) emergency core cooling, (2) post accident containment heat removal, (3) postaccident containment atmosphere cleanup, or (4) residual heat removal from the reactor and from the spent fuel storage pool (including primary and secondary cooling systems). 
Portions of these systems that are required for their safety functions and that (1) do not operate during any mode of normal reactor operation and (2) cannot be tested adequately should be classified as Group B.


==D. IMPLEMENTATION==
b. Cooling water and seal water systems or por tions of these systems 4 important to safety that are designed for functioning of components and systems important to safety, such as reactor coolant pumps, diesels, and control room.
The purpose of this section is to provide information to applicants and licensees regarding the NRC staffs plans for using this regulatory guide.  No backfitting is intended or approved in connection with the issuance of this guide.


Except in those cases in which an applicant or licensee proposes or has previously established an acceptable alternative method for complying with specified portions of the NRCs regulations, the NRC staff will use the methods described in this guide to evaluate (1) submittals in connection with applications for construction permits, standard plant design certifications, operating licenses, early site permits, and combined licenses; and (2) submittals from operating reactor licensees who voluntarily propose to initiate system modifications if there is a clear nexus between the proposed modifications and the subject for which guidance is provided herein.
c. Systems or portions of systems 4 that are connected to the reactor coolant pressure boundary and are capable of being isolated from that boundary during all modes of normal reactor operation by two valves, each of which is either normally closed or capable of automatic closure.6 d. Systems, other than radioactive waste manage ment systems, 2 not covered by items 2.a. through 2.c.


REGULATORY ANALYSIS / BACKFIT ANALYSIS
above that contain or may contain radioactive material and whose postulated failure would result in conserva tively calculated potential offsite doses (using meteorol ogy as recommended by Regulatory Guide  
The regulatory analysis and backfit analysis for this regulatory guide are available in Draft Regulatory Guide DG-1152, Quality Group Classifications and Standards for Water-, Steam-,
1.3,  
and Radioactive-Waste-containing Components of Nuclear Power Plants (Ref. 13). The NRC issued DG-1152 in November 2006 to solicit public comment on the draft of this Revision 4 of Regulatory Guide 1.26.
"Assumptions Used for Evaluating the Potential Radio logical Consequences of a Loss of Coolant Accident for Boiling Water Reactors," and Regulatory Guide 1.4,  
"Assumptions Used for Evaluating the Potential Radio logical Consequences of a Loss of Coolant Accident for Pressurized Water Reactors") that exceed 0.5 rem to the whole body or its equivalent to any part of the body.


7 All NRC regulations listed herein are available electronically through the Public Electronic Reading Room on the NRCs public Web site, at http://www.nrc.gov/reading-rm/doc-collections/cfr/part050.  Copies are also available for inspection or copying for a fee from the NRCs Public Document Room at 11555 Rockville Pike, Rockville, MD; the PDRs mailing address is USNRC PDR, Washington, DC 20555; telephone (301) 415-4737 or (800) 397-4209; fax (301)
For those systems located in Seismic Category I struc tures, only single component failures need be assumed.
415-3548; email PDR@nrc.gov.


8 Copies of ASME standards discussed herein may be obtained from the American Society of Mechanical Engineers, Three Park Avenue, New York, New York  10016-5990; telephone (800) 843-2763;
(However, no credit for automatic isolation from other components in the system or for treatment of released material should be taken unless the isolation or treat ment capability is designed to the appropriate seismic and quality group standards and can withstand loss of offsite power and a single failure of an active compo nent.)  
http://www.asme.org/Codes/Publications/.
4Components in influent lines may be classified as Group D
9 All Federal Register notices listed herein were issued by the U.S. Nuclear Regulatory Commission.  Copies are available for inspection or copying for a fee from the NRCs Public Document Room at 11555 Rockville Pike, Rockville, MD; the PDRs mailing address is USNRC PDR, Washington, DC 20555; telephone (301) 415-4737 or (800) 397-4209; fax (301) 415-3548; email PDR@nrc.gov.
provided they are capable of being isolated from the reactor coolant pressure boundary by an additional valve which has high leaktight integrity.


10
1.26-2
All regulatory guides listed herein were published by the U.S. Nuclear Regulatory Commissio


====n. Where an ADAMS====
3. The Group D quality standards given in Table I of this guide should be applied to water- and steam containing components not part of the reactor coolant pressure boundary or included in quality Groups B or C
accession number is identified, the specified regulatory guide is available electronically through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html.
but part of systems or portions of systems that contain S-or may contain radioactive material.


All other regulatory guides are available electronically through the Electronic Reading Room on the NRCs public Web site, at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/.  Single copies of regulatory guides may also be obtained free of charge by writing the Reproduction and Distribution Services Section, ADM, USNRC,
==D. IMPLEMENTATION==
Washington, DC 20555-0001, or by fax to (301)415-2289, or by email to DISTRIBUTION@nrc.gov.  Active guides may also be purchased from the National Technical Information Service (NTIS) on a standing order basis.  Details on this service may be obtained by contacting NTIS at 5285 Port Royal Road, Springfield, Virginia 22161, online at http://www.ntis.gov, by telephone at (800) 553-NTIS (6847) or (703)605-6000, or by fax to (703) 605-6900.  Copies are also available for inspection or copying for a fee from the NRCs Public Document Room (PDR), which is located at 11555 Rockville Pike, Rockville, Maryland; the PDRs mailing address is USNRC PDR, Washington, DC 20555-0001.
The purpose of this section is to provide information to applicants regarding the NRC staff's plans for using this regulatory guide.
 
The PDR can also be reached by telephone at (301) 415-4737 or (800) 397-4209, by fax at (301) 415-3548, and by email to PDR@nrc.gov.
 
Rev. 4 of RG 1.26, Page 7 REFERENCES
1.
 
U.S. Code of Federal Regulations, Title 10, Part 50, Domestic Licensing of Production and Utilization Facilities, U.S. Nuclear Regulatory Commission, Washington, DC.7
2.
 
ASME Boiler & Pressure Vessel Code, Section III, Nuclear Power Plant Components, American Society of Mechanical Engineers, New York, New York.8
3.
 
Codes and Standards for Nuclear Power Plants, U.S. Nuclear Regulatory Commission, Federal Register, Vol. 49, March 15, 1984, p. 9711.9
4.
 
Regulatory Guide 1.143, Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants, U.S. Nuclear Regulatory Commission, Washington, DC.10
5.
 
Regulatory Guide 1.3, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling-Water Reactors, U.S. Nuclear Regulatory Commission, Washington, DC.10
6.
 
Regulatory Guide 1.4, Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized-Water Reactors, U.S. Nuclear Regulatory Commission, Washington, DC.10
 
11 Copies of API standards discussed herein may be obtained from the American Petroleum Institute , 1220 L Street, NW,
Washington, DC 20005-4070; telephone (800) 926-7337; http://www.api.org/Publications/.
12 Copies of AWWA standards discussed herein may be obtained from the American Water Works Association ,
6666 W. Quincy Ave., Denver, CO 80235 ; telephone (202) 682-8000;
http://www.awwa.org/bookstore/Category.cfm?cat=ALLSTD.
 
13 Draft Regulatory Guide DG-1152 is available electronically under Accession No. ML063100379 in the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html.
 
Copies are also available for inspection or copying for a fee from the NRCs Public Document Room (PDR), which is located at 11555 Rockville Pike, Rockville Maryland; the PDRs mailing address is USNRC PDR, Washington, DC
20555-0001.  The PDR can also be reached by telephone at (301) 415-4737 or (800) 397-4209 by fax at (301) 415-3548, and by email to PDR@nrc.gov.
 
Rev. 4 of RG 1.26, Page 8
7.
 
ASME Boiler and Pressure Vessel Code, Section VIII, Division 1, Rules for Construction of Pressure Vessels, American Society of Mechanical Engineers, New York, New York.8
8.
 
ASME B31.1, Power Piping, American Society of Mechanical Engineers, New York, New York.8
9.
 
API-650, Welded Steel Tanks for Oil Storage, American Petroleum Institute, Washington, DC.11
10.


AWWA D-100, Welded Steel Tanks for Water Storage, American Water Works Association, Denver, Colorado.12
This guide reflects current NRC staff practice. There fore, except in those cases in which the applicant proposes an acceptable alternative method for comply ing with specified portions of the Commission's regula tions, the method described herein is being and will continue to be used in the evaluation of submittals for operating license or construction permit applications until this guide is revised as a result of suggestions from the public or additional staff review.
11.


ASME B96.1, Welded Aluminum-Alloy Storage Tanks, American Society of Mechanical Engineers, New York, New York.8
TABLE 1 QUALITY STANDARDS
12.
components QuAlity B
Quality C
Quality D
Pressure Vessels ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure Vessel Code, Section III,
Vessel Code, Section III,
Vessel Code, Section VIII,
"Nuclear Power Plant Com-
"Nuclear Power Plant Corn- Division 1 ponents," a, b, c Class 2 ponents,,a, b, c Class 3 Piping As above As above ANSI B31.1.0 Power Piping Pumps As above As above Manufacturers standards Valves As above As above ANSI B31.1.0
Atmospheric As above As above API-650, AWWA D 100, or Storage Tanks ANSI B 96.1
0-15 psig As above As above API -620
Storage Tanks aSee Section 50.55a for guidance with regard to the Code and Addenda to be applied.


API-620, Design and Construction of Large, Welded, Low-Pressure Storage Tanks, American Petroleum Institute, Washington, DC.11
bASME Code N-symbol need not be applied.
13.


Draft Regulatory Guide DG-1152, Quality Group Classifications and Standards for Water-,
cThe specific applicability of code cases will be covered separately in other regulatory guides or in Commission regulations, where appropriate. Applicants proposing the use of code cases not covered by guides or regulations should demonstrate that an acceptable level of quality and safety would be achieved.}}
Steam-, and Radioactive-Waste-containing Components of Nuclear Power Plants, U.S. Nuclear Regulatory Commission, Washington, DC.13}}


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Revision as of 02:08, 17 January 2025

For Comment, Quality Group Classifications & Standards for Water-,Steam & Radioactive-Waste-Containing Components of Nuclear Power Plants
ML003739964
Person / Time
Issue date: 02/29/1976
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.06, Rev 3
Download: ML003739964 (3)
v • d • e


U.S. NUCLEAR REGULATORY COMMISSION

REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.26 QUALITY GROUP CLASSIFICATIONS AND STANDARDS FOR

WATER-, STEAM-, AND RADIOACTIVE-WASTE-CONTAINING

COMPONENTS OF NUCLEAR POWER PLANTS

A. INTRODUCTION

General Design Criterion 1, "Quality Standards and Records," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Licensing of Production and Utilization Facilities," requires that structures, systems, and components important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Section 50.55a,

"Codes and Standards," of 10 CFR Part 50 requires that components of the reactor coolant pressure boundary be designed, fabricated, erected, and tested in accordance with the requirements for Class 11 components of Section III of the ASME Boiler and Pressure Vessel or equivalent quality standard

s. This guide desc a

quality classification system related to specified na alU

standards that may be used to det r er standards acceptable to the NRC staff satisnmg General Design Criterion 1 for other )ety-r ed components containing water, steam, or tive material in light-water-cooled nuclear power plan B. DISd After reviewing r

pplications for con struction permits v ope* glicenses and after dis cussions with r"

tativ of professional societies and industr fe lO

has developed a quality classification for safety-related components con taining water, or radioactive material in water cooled nuc po r plants. The system consists of four

'Editions prior to 1971 of the ASME Boiler and Pressure Vessel Code,Section III, "Nuclear Power Plant Components," use the term Class A in lieu of Class 1.

Revision 3 February 1976 USNRC REGULATORY GUIDES

Comments should be sent to the Secretary of the Commission. U.S. Nuclear ReglaorReguletorv Commission, Washington. D.C.

05 Attention: Docketing and Regulatory Guides are issued to describe and make available to the public segulato c0

methods acceptable to the NRC staff of implementing specific parts of the ice Section.

Commission's regulations, to delineate techniques used by the staff in evalu.

The guideseare issued inthe following ten broad divisions:

eting specific problems or postulated accidents, or to provide guidance to appli cants. Regulatory Guides are not substitutes tor regulations, and compliance I. Power Reactors

6. Products with them is not required. Methods and solutions different from those set out in

2. Research and Test Reactors

7. Transportation the guides will be acceptable if they provide a basis for the findings requisite to

3. Fuels and Materials Facilities

8. Occupational Health the issuance or continuance of a permit or license by the Commission

4ý Environmental and Siting

9. Antitrust Review Comments and suggestions for improvements in these iuides are encouraged

5. Materials and Plant Protection

10 General at all times, and guides will be revised, as appropriate, to accommodate com ments and to reflect new information or experience. However. comments on Copies of published guides may be obtained by written request indicating the this guide. if received within about two months after its issuance, will be per- divisions desired to the U.S. Nuclear Regulatory Commission. Washington. D.C.

ticularly useful in evaluating the need for an early revision

20655. Attention: Director. Office of Standards Development.

quality groups, A throu me s for assigning components to these alit oups, d the specific quality standards app*

quality group. The initial portion of t sy is cribed in §50.55a of

10 CFR Part 50.

"cre s that components of the reactor coolant e

undary be designed, fabri cated, ere an d to the highest available national st M

s corresponds to the quality stan d g

r quality Group A of the NRC

system_ .

e describes a method for determining tab onty standards for the remaining safety r

colonents containing radioactive material, a

steam, i.e., quality Group B, C, and D

Shnents. Other systems not covered by this guide, ch as instrument and service air, diesel engine and its erators and auxiliary support systems, diesel fuel, emergency and normal ventilation, fuel handling, and radioactive waste management systems,2 should be designed, fabricated, erected, and tested to quality standards commensurate with the safety function to be performed. Evaluation to establish the quality group classification of these other systems should include consideration of the guidance provided in regulatory positions C.1 and C.2 of this guide.

C. REGULATORY POSITION

1. The Group B quality standards given in Table 1 of this guide should be applied to water- and steam containing pressure vessels, heat exchangers (other than turbines and condensers), storage tanks, piping, pumps, and valves that are either part of the reactor coolant pressure boundary defined in §50.2(v) but excluded

'Specific guidance on the quality group classification of radio- I

active waste management systems is under development.

  • Lines indicate substantive changes from previous issue.

from the requirements of §50.55a3 pursuant to foot note 2 of that section or not part of the reactor coolant pressure boundary but part of:

a. Systems or portions of systems4 important to safety that are designed for (1) emergency core cooling,

(2) postaccident containment heat removal, or (3) post accident fission product removal.

b. Systems or portions of systems4 important to safety that are designed for (1) reactor shutdown or

(2) residual heat removal.

c. Those portions of the steam systems of boiling water reactors extending from the outermost contain ment isolation valve up to but not including the turbine stop and bypass valvess and connected piping up to and including the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation. Alternatively, for boiling water re actors containing a shutoff valve (in addition to the two containment isolation valves) in the main steam line and in the main feedwater line, Group B quality standards should be applied to those portions of the steam and feedwater systems extending from the outermost con tainmen/t isolation valves up to and including the shutoff valve or the first valve that is either normally closed or capable of automatic closure during all modes of normal reactor operation.

d. Those portions of the steam and feedwater systems of pressurized water reactors extending from and including the secondary side of steam generators up to and including the outermost containment isolation valves and connected piping up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure during all modes of normal reactor operation.

e. Systems or portions of systems 4 that are connected to the reactor coolant pressure boundary and are not capable of' being isolated from the boundary during all modes of normal reactor operation by two valves, each of which is either normally closed or capable of automatic closure.

2. The Group C quality standards given in Table 1 of this guide should be applied to water-, steam-, and

3Group A quality standards that are required for pressure containing components of the reactor coolant pressure bound ary are specified in Section 50.55a of 10 CFR Part 50.

"4The system boundary includes those portions of the system required to accomplish the specified safety function and connected piping up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of aitomatic closure when the safety function is required.

$The turbine stop valve and the turbine bypass valve, although not included in quality group B, should be subjected to a quality assurance program at a level generally equivalent to quality group B.

radioactive-waste-containing pressure vessels, heat ex changers (other than turbines and condensers), storage tanks, piping, pumps, and valves not part of the reactor coolant pressure boundary or included in quality Group B but part of:

a. Cooling water and auxiliary feedwater systems or portions of these systems4 important to safety that are designed for (1) emergency core cooling, (2) post accident containment heat removal, (3) postaccident containment atmosphere cleanup, or (4) residual heat removal from the reactor and from the spent fuel storage pool (including primary and secondary cooling systems).

Portions of these systems that are required for their safety functions and that (1) do not operate during any mode of normal reactor operation and (2) cannot be tested adequately should be classified as Group B.

b. Cooling water and seal water systems or por tions of these systems 4 important to safety that are designed for functioning of components and systems important to safety, such as reactor coolant pumps, diesels, and control room.

c. Systems or portions of systems 4 that are connected to the reactor coolant pressure boundary and are capable of being isolated from that boundary during all modes of normal reactor operation by two valves, each of which is either normally closed or capable of automatic closure.6 d. Systems, other than radioactive waste manage ment systems, 2 not covered by items 2.a. through 2.c.

above that contain or may contain radioactive material and whose postulated failure would result in conserva tively calculated potential offsite doses (using meteorol ogy as recommended by Regulatory Guide

1.3,

"Assumptions Used for Evaluating the Potential Radio logical Consequences of a Loss of Coolant Accident for Boiling Water Reactors," and Regulatory Guide 1.4,

"Assumptions Used for Evaluating the Potential Radio logical Consequences of a Loss of Coolant Accident for Pressurized Water Reactors") that exceed 0.5 rem to the whole body or its equivalent to any part of the body.

For those systems located in Seismic Category I struc tures, only single component failures need be assumed.

(However, no credit for automatic isolation from other components in the system or for treatment of released material should be taken unless the isolation or treat ment capability is designed to the appropriate seismic and quality group standards and can withstand loss of offsite power and a single failure of an active compo nent.)

4Components in influent lines may be classified as Group D

provided they are capable of being isolated from the reactor coolant pressure boundary by an additional valve which has high leaktight integrity.

1.26-2

3. The Group D quality standards given in Table I of this guide should be applied to water- and steam containing components not part of the reactor coolant pressure boundary or included in quality Groups B or C

but part of systems or portions of systems that contain S-or may contain radioactive material.

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants regarding the NRC staff's plans for using this regulatory guide.

This guide reflects current NRC staff practice. There fore, except in those cases in which the applicant proposes an acceptable alternative method for comply ing with specified portions of the Commission's regula tions, the method described herein is being and will continue to be used in the evaluation of submittals for operating license or construction permit applications until this guide is revised as a result of suggestions from the public or additional staff review.

TABLE 1 QUALITY STANDARDS

components QuAlity B

Quality C

Quality D

Pressure Vessels ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure Vessel Code,Section III,

Vessel Code,Section III,

Vessel Code,Section VIII,

"Nuclear Power Plant Com-

"Nuclear Power Plant Corn- Division 1 ponents," a, b, c Class 2 ponents,,a, b, c Class 3 Piping As above As above ANSI B31.1.0 Power Piping Pumps As above As above Manufacturers standards Valves As above As above ANSI B31.1.0

Atmospheric As above As above API-650, AWWA D 100, or Storage Tanks ANSI B 96.1

0-15 psig As above As above API -620

Storage Tanks aSee Section 50.55a for guidance with regard to the Code and Addenda to be applied.

bASME Code N-symbol need not be applied.

cThe specific applicability of code cases will be covered separately in other regulatory guides or in Commission regulations, where appropriate. Applicants proposing the use of code cases not covered by guides or regulations should demonstrate that an acceptable level of quality and safety would be achieved.


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