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{{#Wiki_filter:4"'*1* | {{#Wiki_filter:4" L. | ||
'*1*. 4` | |||
May 1973 U.S. ATOMIC ENERGY COMMISSION | |||
( | |||
R GULATORY GUIDE | |||
DIRECTORATE OF REGULATORY STANDARDS | |||
REGULATORY GUIDE 1.51 INSEF IVICE INSPECTION OF ASME CODE CLASS 2 AND 3 NUCLEAR POW TER PLANT COMPONENTS | |||
==A. INTRODUCTION== | ==A. INTRODUCTION== | ||
General Design Criteria 36. "Inspection | componen ts. In the Winter 1972 Addenda to Section XI, 3 acceptable inservice inspection requirements are General Design Criteria 36. "Inspection of specified for Code Class 22 components. Code Class 32 Emergency Core Cooling System." 39. "Inspection of components are not presently included in Section X1 Containment Heat Removal System." 42, "Inspection of requirements, but they should also be part of the Containment Atmosphere Cleanup Systems," and 45. scheduled inservice inspection progra | ||
====m. The inspection==== | |||
"Inspection of Cooling Water System," of Appendix A requirements need not be as extensive as those required to 10 CFR Part 50. "Generzl Desian Criteria for Nuclear for Code Class 2 components but should, as a minimum. | |||
Power Plants," require that the subject systems be include visual inspection of Code Class 3 componentb designed to permit appropriate periodic inspection of and their supports. For such inspections to be effective. | |||
important component parts of the systems to assure they should be performed at periods when the system integrity and capability. Regulatory Guide 1.26 components are under pressure of sutficienti nagnitude (Safety Giuide 26). "Quality Group Classification and to properly represent the intended service condition. | |||
Standards," in conjunction with § 50.55a of 10 CFR This may require that the inspections of Code Class ' | |||
Part 50 describes a quality classification system related components be scheduled to coincide with system to specified industry codes that may be used to performance tests, component functional tests, and determine quality standards for water- and system pressure tests in order to benefit from the steam-containing components important to the safety of pressure levels established for these test | |||
====s. Section XI==== | |||
water-cooled nuclear power plants. This guide describes defines an inspection interval for Code Class I and 2 acceptable methods of implementing the periodic components as 10 years, and the inservice inspection inservice inspection requirements for American Society program for Code Class 3 components should be based of Mechanical Engineers (ASME) Code Class 2 and 3 on the same time interval. | |||
components. This guide applies to light-water-cooled reactors. The Advisory Committee on Reactor Code Class 3 components required to function Safeguards has been consulted concerning this guide and during normal reactor operation would generally he has concurred in the regulatory position. accessible during reactor downtime, and they should be inspected at least once toward the end ot each | |||
==B. DISCUSSION== | ==B. DISCUSSION== | ||
The ASME Boiler and Pressure Vessel Code ( | inspection interval. Components in systems or portiovri of systems which are not required to futiction during The ASME Boiler and Pressure Vessel Code (ASME reactor operation can be inspected independently of B&PV Code), Section XI, "Rules for Inservice reactor downtime. | ||
Inspection of Nuclear Reactor Systems."' specifies requirements for ilservice inspection of Code Class 12 The visual inspection of Code Class 3 components should be conducted for signs or evidence of leak.:'c | |||
'Copies may he obtained from American Society of caused by structural distress or corrosion effects on the, Mechanical Enqincers. United Engineering Center, 345 Ea'st 47th components. In addition, supports and hangers lilt Street, New York, N.Y. 100 17. piping and Code Class 3 componenls over 4 inches ill IC6mponents classified as AEC Quality Group A. B, and C dianicter should be inspected for evidence of inadcqmtm should conform to the requirements of the ASSlI' Boiler and support, unintended restrmint. or structur:al distress. | |||
Pressure Vessel Code for Class I. 2. and 3 components, "ASME B&PV Code, Sectiotni Xl. Wintter 1972 Addtenda. | |||
resp ctively. | |||
USAEC REGULATORY GUIDES Copies of publiihed guide% may be obtained by es.luftl indicating the div~iun; | |||
'I,The pressure developed in components during | desired to the US. Atomic Energy Cumr,$,s.on. Washtrinton. DZ.. 2CS4t. | ||
I- , | |||
public Attention: Director of negulatnry Stsnd3ordi. Coermtnts .*n*J st*,q-toon Regulatory Guides are issued /o describe and ,'r1te available lt. thepants of imirovemlrts in htfe gklir Mi enc)ur'ed and should be %tntto ite SetjPri itethods acceptbhle to the AEC Rl'gulatory stifl of imnplemrnting specific g*e.hnique% uStit by 9.- staff in of the Contsnist*On. U.S. Alomic Enetriv Cunmmostun. Vlh.hirigit.. D.C. 20U-45. | |||
the Comminsion's tegulisions, to dielinete Attention: Chief. Pubic Proceedings Sliit. | |||
e'llualtng specific problems or pOstulated .,cidt'*.tls. at to provide gait'enco in applicants. Regulatory Guides ere not substitutes for 'eguitiuni And compliance out in The guides areissued in the follosring ton brail drisic.ni: | |||
with them it not requirad. Methodt and stolution* differont frmt ihoos %st the guides wvillbe acceputable if they provide a batis far tim finrdmtlt reQuitl-l to 2. R eIe ref endT itw*Re tcto t 7. T *ortniin srini the i muantce otcontinuance of a o*erm it of Icente by the Com m ,ssion. | |||
* | |||
3. Fuels anorM4teiitis FaitIlt," . Occu*i1tionl Heaslth accomnodate 4. Environtat.rll am Sam)t', 9. Antitrust Review Publihhed guiders will be revised periodicull,.at apOraOrtipr.,to S. Materitls &nd Plant Protection 10. General eproetients and to reflect new infoorntatOn of experience. | |||
'I, | |||
The pressure developed in components during a tested and inspected at least once during each 10-year system performance lest, a component performance test, inspection interval. | |||
or a system pressure test should be representative of b. In addition, all components should be inspected conditions under which the systems should be leaktight during periods of normal reactor operation or during during operation. The lest pressure should be at least system performance testing at least once during every | |||
110 percent of the system design pressure. However. the one-third of each inspection interval. | |||
pressure developed during the conduct of a periodic system performance test would be acceptable during 3. Inspection requirements for ASME Code Class 3 inspections conducted in periods between the pressure components should include the following: | |||
tests. Certain components. such as open storage tanks a. System pressure tests should be performed to including piping to the first shutoff valve, cannot readily the extent necessary to perform the component be pressure tested. The hydrostatic pressure developed examination. Test pressure should be at least: | |||
with tanks filled to their design capacity would be an (1) For closed systems, 110 percent of the acceptable test pressure for such tanks and connected design pressure. | |||
piping. (2) For open storage tanks, the nominal hydrostatic pressure developed with the tanks filled to | |||
==C. REGULATORY POSITION== | ==C. REGULATORY POSITION== | ||
I. Inservice inspection requirements for ASME | design capacity. | ||
(3) Open-ended portions of systems may be I. Inservice inspection requirements for ASME Code exempted from pressure testing. | |||
Class 22 components should comply with the ASME b. Visual inspections for evidence of unanticipated B&PV Code. Section X1 and the Winter 1972 Addenda' component leakage, structural distress. or corrosion. | |||
for Class 2 components except that subparagraph c. Inspection of supports and hangers for piping ISC-261(a) should be changed to read as follows: and components over 4 inches in diameter for evidence of inadequate support, unintended restraint, or | |||
"Components in systems or portions of systems strurtural distress. | |||
which recirculate reactor coolant during normal reactor operation, and are designed for pressure and 4. Records of the inserice inspection should be tempcrature in excess of either 275 psig or 200°F established and maintained for the life of the plant and shall be examined in accordance with the should include: | |||
requirements specified in Table ISC-261 ." a. Identification of systems components inspected; | |||
2. Inspection programs for ASME Code Class 32 b. Date of inspection; | |||
components should be performed according to the c. Repair or replacement; and following schedules: d. Signature of employee certifying dte inspection a. All of the components should be pressure was made. | |||
It | |||
1.5 1-2}} | |||
{{RG-Nav}} | {{RG-Nav}} |
Latest revision as of 10:12, 4 November 2019
ML13350A361 | |
Person / Time | |
---|---|
Issue date: | 05/31/1973 |
From: | US Atomic Energy Commission (AEC) |
To: | |
References | |
RG-1.051 | |
Download: ML13350A361 (2) | |
4" L.
'*1*. 4`
May 1973 U.S. ATOMIC ENERGY COMMISSION
(
R GULATORY GUIDE
DIRECTORATE OF REGULATORY STANDARDS
REGULATORY GUIDE 1.51 INSEF IVICE INSPECTION OF ASME CODE CLASS 2 AND 3 NUCLEAR POW TER PLANT COMPONENTS
A. INTRODUCTION
componen ts. In the Winter 1972 Addenda to Section XI, 3 acceptable inservice inspection requirements are General Design Criteria 36. "Inspection of specified for Code Class 22 components. Code Class 32 Emergency Core Cooling System." 39. "Inspection of components are not presently included in Section X1 Containment Heat Removal System." 42, "Inspection of requirements, but they should also be part of the Containment Atmosphere Cleanup Systems," and 45. scheduled inservice inspection progra
m. The inspection
"Inspection of Cooling Water System," of Appendix A requirements need not be as extensive as those required to 10 CFR Part 50. "Generzl Desian Criteria for Nuclear for Code Class 2 components but should, as a minimum.
Power Plants," require that the subject systems be include visual inspection of Code Class 3 componentb designed to permit appropriate periodic inspection of and their supports. For such inspections to be effective.
important component parts of the systems to assure they should be performed at periods when the system integrity and capability. Regulatory Guide 1.26 components are under pressure of sutficienti nagnitude (Safety Giuide 26). "Quality Group Classification and to properly represent the intended service condition.
Standards," in conjunction with § 50.55a of 10 CFR This may require that the inspections of Code Class '
Part 50 describes a quality classification system related components be scheduled to coincide with system to specified industry codes that may be used to performance tests, component functional tests, and determine quality standards for water- and system pressure tests in order to benefit from the steam-containing components important to the safety of pressure levels established for these test
s. Section XI
water-cooled nuclear power plants. This guide describes defines an inspection interval for Code Class I and 2 acceptable methods of implementing the periodic components as 10 years, and the inservice inspection inservice inspection requirements for American Society program for Code Class 3 components should be based of Mechanical Engineers (ASME) Code Class 2 and 3 on the same time interval.
components. This guide applies to light-water-cooled reactors. The Advisory Committee on Reactor Code Class 3 components required to function Safeguards has been consulted concerning this guide and during normal reactor operation would generally he has concurred in the regulatory position. accessible during reactor downtime, and they should be inspected at least once toward the end ot each
B. DISCUSSION
inspection interval. Components in systems or portiovri of systems which are not required to futiction during The ASME Boiler and Pressure Vessel Code (ASME reactor operation can be inspected independently of B&PV Code),Section XI, "Rules for Inservice reactor downtime.
Inspection of Nuclear Reactor Systems."' specifies requirements for ilservice inspection of Code Class 12 The visual inspection of Code Class 3 components should be conducted for signs or evidence of leak.:'c
'Copies may he obtained from American Society of caused by structural distress or corrosion effects on the, Mechanical Enqincers. United Engineering Center, 345 Ea'st 47th components. In addition, supports and hangers lilt Street, New York, N.Y. 100 17. piping and Code Class 3 componenls over 4 inches ill IC6mponents classified as AEC Quality Group A. B, and C dianicter should be inspected for evidence of inadcqmtm should conform to the requirements of the ASSlI' Boiler and support, unintended restrmint. or structur:al distress.
Pressure Vessel Code for Class I. 2. and 3 components, "ASME B&PV Code, Sectiotni Xl. Wintter 1972 Addtenda.
resp ctively.
USAEC REGULATORY GUIDES Copies of publiihed guide% may be obtained by es.luftl indicating the div~iun;
desired to the US. Atomic Energy Cumr,$,s.on. Washtrinton. DZ.. 2CS4t.
I- ,
public Attention: Director of negulatnry Stsnd3ordi. Coermtnts .*n*J st*,q-toon Regulatory Guides are issued /o describe and ,'r1te available lt. thepants of imirovemlrts in htfe gklir Mi enc)ur'ed and should be %tntto ite SetjPri itethods acceptbhle to the AEC Rl'gulatory stifl of imnplemrnting specific g*e.hnique% uStit by 9.- staff in of the Contsnist*On. U.S. Alomic Enetriv Cunmmostun. Vlh.hirigit.. D.C. 20U-45.
the Comminsion's tegulisions, to dielinete Attention: Chief. Pubic Proceedings Sliit.
e'llualtng specific problems or pOstulated .,cidt'*.tls. at to provide gait'enco in applicants. Regulatory Guides ere not substitutes for 'eguitiuni And compliance out in The guides areissued in the follosring ton brail drisic.ni:
with them it not requirad. Methodt and stolution* differont frmt ihoos %st the guides wvillbe acceputable if they provide a batis far tim finrdmtlt reQuitl-l to 2. R eIe ref endT itw*Re tcto t 7. T *ortniin srini the i muantce otcontinuance of a o*erm it of Icente by the Com m ,ssion.
3. Fuels anorM4teiitis FaitIlt," . Occu*i1tionl Heaslth accomnodate 4. Environtat.rll am Sam)t', 9. Antitrust Review Publihhed guiders will be revised periodicull,.at apOraOrtipr.,to S. Materitls &nd Plant Protection 10. General eproetients and to reflect new infoorntatOn of experience.
'I,
The pressure developed in components during a tested and inspected at least once during each 10-year system performance lest, a component performance test, inspection interval.
or a system pressure test should be representative of b. In addition, all components should be inspected conditions under which the systems should be leaktight during periods of normal reactor operation or during during operation. The lest pressure should be at least system performance testing at least once during every
110 percent of the system design pressure. However. the one-third of each inspection interval.
pressure developed during the conduct of a periodic system performance test would be acceptable during 3. Inspection requirements for ASME Code Class 3 inspections conducted in periods between the pressure components should include the following:
tests. Certain components. such as open storage tanks a. System pressure tests should be performed to including piping to the first shutoff valve, cannot readily the extent necessary to perform the component be pressure tested. The hydrostatic pressure developed examination. Test pressure should be at least:
with tanks filled to their design capacity would be an (1) For closed systems, 110 percent of the acceptable test pressure for such tanks and connected design pressure.
piping. (2) For open storage tanks, the nominal hydrostatic pressure developed with the tanks filled to
C. REGULATORY POSITION
design capacity.
(3) Open-ended portions of systems may be I. Inservice inspection requirements for ASME Code exempted from pressure testing.
Class 22 components should comply with the ASME b. Visual inspections for evidence of unanticipated B&PV Code. Section X1 and the Winter 1972 Addenda' component leakage, structural distress. or corrosion.
for Class 2 components except that subparagraph c. Inspection of supports and hangers for piping ISC-261(a) should be changed to read as follows: and components over 4 inches in diameter for evidence of inadequate support, unintended restraint, or
"Components in systems or portions of systems strurtural distress.
which recirculate reactor coolant during normal reactor operation, and are designed for pressure and 4. Records of the inserice inspection should be tempcrature in excess of either 275 psig or 200°F established and maintained for the life of the plant and shall be examined in accordance with the should include:
requirements specified in Table ISC-261 ." a. Identification of systems components inspected;
2. Inspection programs for ASME Code Class 32 b. Date of inspection;
components should be performed according to the c. Repair or replacement; and following schedules: d. Signature of employee certifying dte inspection a. All of the components should be pressure was made.
It
1.5 1-2