ML19221A856
| ML19221A856 | |
| Person / Time | |
|---|---|
| Issue date: | 02/29/1976 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| REGGD-01.026, REGGD-1.026, NUDOCS 7907100120 | |
| Download: ML19221A856 (3) | |
Text
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n3 U.S. NUCLEAR REGULATORY COMMISSION February 1976 REC CORYGL DE OFFICE OF STANDARDS DEVELOPMENT REGULAluH v GU!OE 12G
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QUALITY GROUP CLASSIFICATIONS AND STANDARr.,S FOR WATER, STEAM, AND RADIOACTIVE-WASTE-CONTAINING COMPONENTS OF NUCLEAR POWER PLANTS A
d b
quality groups, A through,b, mYthyds for assigning A. INTRODUCTION components to these giahtygroups,#and the specific General Design Criterion 1, "Quahty Standards and quahty standards app %SJs.N exh quality group. The Records," of Appendix A," General Design Criteria for initial portion of tWs sNmibis ibed in 50.55a of 10 CFR Part 50(Wi reMes that components of the reactor coolant ppE@re,houndary be designed N'uclear Power Plants," to 10 CFR Part 50, "Liceming of Production and Utilization Facilities," requires that structures, systems, and components important to safety cated, eredd. arhtg$fted to the highest available be designed, fabricated, erected, and tested to quality national stan3sgs; tnis corresponds to the quahty standards commensurate with the importance of the standsdc equke64or quahty Group A of the NRC safety functions to be performed. Section 50.5 5a, systentJhQde describes a method for determming
" Codes and Standards," of 10 CFR Part 50 requires that accsptabh gua'hty standards for the remaining safety-components of the reactor coolant pressure boundary be rthtd components containing radioactive material, designed, fabricated. erected, and tested in accordance 1watC or steam, i.e., quahty Group B, C, and D with the requirements for Class I components of Teceponents. Other systems not covered by this guide, Section 111 of the ASME Boiler and Pressure Vessel Codt
%2cfi as instrument and service air, diesel engme and its or equivalent quality standards. This guide desc;ibes a'g seneraWrs and auxiliary support systems, diesel fuel, qahty dassification system related to.pecified n&nal 7 e nerreacy and normal ver tilation, fuel handhng, and stanuards that may be used to determir4 quahtyg -
radiactive waste management systems,2 should be l*
standards acceptable to the NRC staff for satisfymg designed, fabricated, erected, and tested to quality General Design Criterion I for other ' egety-riJated standa-ds commensurate with the safety function to be components containing water, steam, or Irnhoactive performed. Evaluation to establish the quahty group matenalin hght water-cooled nuclear power plants.
classification of these other systems should include consideration of the guidance provided in regulatory positions C.1 and C.2 of this guide.
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B. DiscusstGN
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C. REGULATORY POSITION
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After reviewing a number of appheations for con-struction permits and operstmg licenses and after dis-
- 1. The Group B quality standards given in Table 1 of cussions with -reprezntattves of professional societies this side should be apphed to water and steam-and industty,'the NRC afaff has developed a quality contn.ung pressure vessels, heat exchangers (other than classification system for safety-related comperients con-turbines and condensers), storage tanks, piping, pumps, taming water, steam, or radioactive material in water-and valves that are either part of the reactor coolant cooled nuclear poker plants.The system consists of four pressure boundary defined in 50.2(v) but excluded
'I ditions prior to 1971 of the ASMI Butler and Pressure Vessel
' Specific guidance on the quahty group classifkation of radu-l Code,Section I!L " Nuclear Power Plant Components," use the active waste management systems is under development.
l term Class A in heu of Class 1.
- Lines indicate substantive changes from prenous issue.
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3 from t:n requirements of 50.5 5a pursuant to foot-radioactive-waste-contaimng pressure vessels, heat e x-note 2 of that section or not part of the reactor coolant changers (other than turbines and condensers), storage pressure boundary but part of:
tanks, piping, pumps, and valves not part of the reactor coolant pressure boundary or includedin quality Group
- a. Systems or portions of systems
- important tc B but part of:
safety that are designed for (1) emergency core cooling,.
(2) postaccident containment heat removal, or (3) post-
- a. Cooling water and aux 1hary feedwater systems accident fission product removal.
or portions of'these systems
- important to safety that are designed for (1) emergency core coohng, (2) post-
- b. Systems or portions of systems' important to accident containment heat removal, (3) postaccident safety that are designed for (1) reactor shutdown or containment atmosphere cleanup, or (4) residual heat (2) residual heat removal.
removal from the reactor and from the spent fuel storage pool (including primary and secondary coohng systemst
- c. Those pornons of the steam systems of boiling Portions of these systems that are required for their water nators extendmg from the outermost contain-safety functions and that (1)do not operate dunng any rnent isolation valve up to tut not including the turbine mode of normal reactor operation and (2)cannot be stop and bypass valves and connected piping up tu anj tested adequately should be classified as Group B.
5 includmg the first valve that is either normally closed or capable of autonutic closure during all modes of normal
- b. Cooling water and seal wawa syttems or por-s reactor operation. Alternatively, for boihng water re-tions of these systems" important to safety that are actors containing a shutoff valve (in addition to the two designed for functioning of components and systems containment isolation valves) in the main steam line and important to safety, such as reactor coolant pumps, in the mam feedwater line, Group B quality standards diesels, and control room, should be applied to those portions of the steam and feedwater systems extending from the outermost con-
- c. Systems or portions of systems" that are tamment isolation valves up to and including the shutoff connected to the reactor coolant pressure boundary and valve or the first valve that is either normally closed or are capable of being isolated from that boundary during capable of automatic closure during all modes of normal all modes of normal reactor operation by two valves, reactor operation.
each of whkh is either normally closed or capable of automatic closure.'
- d. Those portions of the steam and feedwater systems of pressunzed water reactors extendmg from
- d. Systems, other than radioactive waste manage.
and mcluding the secondary side of steam generators up ment systems,2 not covered by items 2.a. through 2.c.
to and includmg the outermost containment isolation above that contain or may contain radioactive matenal valves and connected piping up to and includmg the first and whose postulated failure would resuh in conserva-vahe unclu ing a safety or relief valve) that is either d
tively calcuhted potential offsite doses (using meteorol-normally closed or capable of automatic closure during a!! modes of' normal reactor operation gy s recommended by Regulatoiy Guide 1.3,
" Assumptions Used for Evaluatirig the Potentiel Radio-I gical Consequences of a Loss of Coolant Accident for
- e. Systems or portions of systems' that are B iling Water Reactors,, and Regulatory Guide 1.4, connected to the reactor coolant pressure boundary and
" Assumptions Used for Evaluating the Potcntial Radio-are not capable of being isolated from the boundary logie 1 C nsequences of a 1ess of Coolant Accident f or dunng all modes of normal reactor operation by two Pressunzed Water Reactors ) that exceed 0.5 rem to the valves, each of which is either noimally closed or capable whole body or its equivalent to any part of the body.
of automatic closure.
For those systems locateu m Seismic Category I strue tures, only single component failures need be assumed.
The Group C quality standards given in Teb..c 1 of ver, no credit for automatie isolation from other this guide should be applied to weer, steam, and components in the system or for treatment of released 8 Group A qualny standards that are requued for pres ure material shoald be taken "nless the iso'ation or treat-tenninmg componenh of the resctor coolant pressure bound-ment caoability is designed to the appropriate seismic ary irc spestf-d a Sestion 50.5Sa of 10 Cl R Part 50.
ml quality group standards and can withstand loss of
'The y stem bondary meludes those portions of the system g
gg gp g,
required to ac amphsh the spesified safe ty f un ctior. and cannet ted firmg q (o and meludm; the first vahe unclud'ng a nen t. )
utety or rehef vahel that is either.wrmally ciosed or capable vf automatic closure w hen the safety f un.non is required.
' The turbme stop valve and the turbme bypass salve, although
' Components m mfluent 1mes may be classified as Group D not mt!uded in quahty group B, should be subytted to a pronfed they are capable of being isol.ted f rom the reactor q u.h t y assurante program at a level generally equivalent to coola nt pressure boundary by an addinonal valve whish has quabty group B.
high leaktight integrity.
125 132
'2'2
- 3. The Group D quahty standards ginn in Table 1 of This guide reflects current NRC staff practice. There-9.>:ntaming components no:
s guide should be apphed to water-and steam-fore, except in those cases in which the appbcant part of the reactor coolant proposes an acceptable alternative method for comply-pressure boundary or included in qualitv Groups B or C ing with specified portions of the Commission's regula-but part of systems or portions of systems that contain tions, the method described herein is being and wtll or may contain radioactive material.
continue to be uwd in the enluation of submittals for operating license or construction permit applications D. IMPLEMENTATION until this guide is revised as a result of suggestions from the public or additional staff review.
The purpose of this section is to provide information to appheants regarding the NRC staff's plans for using this regulatory guide.
TABLE 1
- QUAL ITY S TANDA RDS Con;onen ts Quality B Quality C Qushty D H e n., ; V.wls ASME Boiler and Pressure ASME Boiler and Pressure ASME Boiler and Pressure v em.
C9 'iectio n !!!
Veswl Code, Section lil, Ve sse. Code, Section Vl!!,
" Nuclear Power Plant Cone "Mylear Power Plant Com-Division 1 ponents," 8 b C Class 2 poneats,"ar o c;,,, ;
Piping As above As above ANSI B31.1.0 Power Piping Pumps As above As above Manuf acturers standards e
alves As above As above ANSI B31.1.0 Atmospheric As above As abcve API-650, AVAVA D 100, or Storage Tanks ANSI B 96.1 015 psig As above As above API-620 Storage Tanks a see Secnon So.55a for guidance with regard to the Code and Addenda to be apphed.
bASME Code N - symbol need not be apphed.
c The speofic apphcabihty of code cases will be covered separately in other regulatory guides or in Commission regulations, where appropesate. Apphcants prcposing the use of code cases not covered by guides or regulations should demonstrate that an acceptab!e level of quahty and safety would be achieved.
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