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{{#Wiki_filter:4"'*1*.(L.4`U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:4"                                                                                                                                                                             L.
R GULATORY DIRECTORATE  
 
OF REGULATORY  
'*1*. 4`
STANDARDS May 1973 GUIDE INSEF REGULATORY  
                                                                                                                                                                    May 1973 U.S. ATOMIC ENERGY COMMISSION
GUIDE 1.51 IVICE INSPECTION  
(
OF ASME CODE CLASS 2 AND 3 NUCLEAR POW  
                                        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 of Emergency Core Cooling System." 39. "Inspection of Containment Heat Removal System." 42, "Inspection of Containment Atmosphere Cleanup Systems," and 45."Inspection of Cooling Water System," of Appendix A to 10 CFR Part 50. "Generzl Desian Criteria for Nuclear Power Plants," require that the subject systems be designed to permit appropriate periodic inspection of important component parts of the systems to assure system integrity and capability.
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


Regulatory Guide 1.26 (Safety Giuide 26). "Quality Group Classification and Standards," in conjunction with § 50.55a of 10 CFR Part 50 describes a quality classification system related to specified industry codes that may be used to determine quality standards for water- and steam-containing components important to the safety of water-cooled nuclear power plants. This guide describes acceptable methods of implementing the periodic inservice inspection requirements for American Society of Mechanical Engineers (ASME) Code Class 2 and 3 components.
====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.


This guide applies to light-water-cooled reactors.
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.


The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.
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.


==B. DISCUSSION==
Standards," in conjunction with § 50.55a of 10 CFR                                        This may require that the inspections of Code Class '
The ASME Boiler and Pressure Vessel Code (ASME B&PV Code), Section XI, "Rules for Inservice Inspection of Nuclear Reactor Systems."'
        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
specifies requirements for ilservice inspection of Code Class 12'Copies may he obtained from American Society of Mechanical Enqincers.


United Engineering Center, 345 Ea'st 47th Street, New York, N.Y. 100 17.IC6mponents classified as AEC Quality Group A. B, and C should conform to the requirements of the ASSlI' Boiler and Pressure Vessel Code for Class I. 2. and 3 components, resp ctivel
====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.


====y. TER PLANT COMPONENTS====
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
componen ts. In the Winter 1972 Addenda to Section XI, 3 acceptable inservice inspection requirements are specified for Code Class 22 components.


Code Class 32 components are not presently included in Section X1 requirements, but they should also be part of the scheduled inservice inspection program. The inspection requirements need not be as extensive as those required for Code Class 2 components but should, as a minimum.include visual inspection of Code Class 3 componentb and their supports.
==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.
For such inspections to be effective.
 
they should be performed at periods when the components are under pressure of sutficienti nagnitude to properly represent the intended service condition.
 
This may require that the inspections of Code Class 'components be scheduled to coincide with system performance tests, component functional tests, and system pressure tests in order to benefit from the pressure levels established for these tests. Section XI defines an inspection interval for Code Class I and 2 components as 10 years, and the inservice inspection program for Code Class 3 components should be based on the same time interval.Code Class 3 components required to function during normal reactor operation would generally he accessible during reactor downtime, and they should be inspected at least once toward the end ot each inspection interval.


Components in systems or portiovri of systems which are not required to futiction during reactor operation can be inspected independently of reactor downtime.The visual inspection of Code Class 3 components should be conducted for signs or evidence of leak.:'c caused by structural distress or corrosion effects on the, components.
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.


In addition, supports and hangers lilt piping and Code Class 3 componenls over 4 inches ill dianicter should be inspected for evidence of inadcqmtm support, unintended restrmint.
Pressure Vessel Code for Class I. 2. and 3 components,                                          "ASME B&PV Code, Sectiotni Xl. Wintter 1972 Addtenda.


or structur:al distress."ASME B&PV Code, Sectiotni Xl. Wintter 1972 Addtend
resp ctively.


====a. USAEC REGULATORY ====
USAEC REGULATORY GUIDES                                         Copies of publiihed guide% may be obtained by es.luftl indicating the div~iun;
GUIDES Copies of publiihed guide% may be obtained by es.luftl indicating the div~iun;desired to the US. Atomic Energy Cumr,$,s.on.
                                                                                                desired to the US. Atomic Energy Cumr,$,s.on. Washtrinton. DZ..        2CS4t.


Washtrinton.
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.


DZ.. 2CS4t.Regulatory Guides are issued /o describe and ,'r1te available lt. the public Attention:  
the Comminsion's tegulisions, to dielinete Attention: Chief. Pubic Proceedings Sliit.
Director of negulatnry Stsnd3ordi.


Coermtnts , I-itethods acceptbhle to the AEC Rl'gulatory stifl of imnplemrnting specific pants of imirovemlrts in htfe gklir Mi enc)ur'ed and should be %tnt to ite SetjPri the Comminsion's tegulisions, to dielinete uStit by 9.- staff in of the U.S. Alomic Enetriv Cunmmostun.
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.


Vlh.hirigit..  
*
D.C. 20U-45.e'llualtng specific problems or pOstulated at to provide gait'enco in Attention:
                                                                                                  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.
Chief. Pubic Proceedings Sliit.applicants.


Regulatory Guides ere not substitutes for 'eguitiuni And compliance with them it not requirad.
'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.


Methodt and differont frmt ihoos %st out in The guides are issued in the follosring ton brail drisic.ni:
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
the guides wvill be acceputable if they provide a batis far tim finrdmtlt reQuitl-l to the i muan tce ot continuance of a it of Icente by the Com m ,ssion. 2. R eIe ref end T itw* Re tcto t 7. T srini rtniin 3. Fuels anor M4teiitis FaitIlt," .
    110 percent of the system design pressure. However. the          one-third of each inspection interval.
Heaslth Publihhed guiders will be revised periodicull,.
at apOraOrtipr., to accomnodate
4. Environtat.rll am Sam)t', 9. Antitrust Review eproetients and to reflect new infoorntatOn of experience.


S. Materitls
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:
&nd Plant Protection
    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:
1
    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.


===0. General ===
piping.                                                                     (2) For open storage tanks, the nominal hydrostatic pressure developed with the tanks filled to
'I, The pressure developed in components during a system performance lest, a component performance test, or a system pressure test should be representative of conditions under which the systems should be leaktight during operation.


The lest pressure should be at least 110 percent of the system design pressure.
==C. REGULATORY POSITION==
design capacity.


However. the pressure developed during the conduct of a periodic system performance test would be acceptable during inspections conducted in periods between the pressure tests. Certain components.
(3) Open-ended portions of systems may be I. Inservice inspection requirements for ASME Code                exempted from pressure testing.


such as open storage tanks including piping to the first shutoff valve, cannot readily be pressure tested. The hydrostatic pressure developed with tanks filled to their design capacity would be an acceptable test pressure for such tanks and connected piping.C. REGULATORY
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.
POSITION I. Inservice inspection requirements for ASME Code Class 22 components should comply with the ASME B&PV Code. Section X1 and the Winter 1972 Addenda'for Class 2 components except that subparagraph ISC-261(a)
should be changed to read as follows: "Components in systems or portions of systems which recirculate reactor coolant during normal reactor operation, and are designed for pressure and tempcrature in excess of either 275 psig or 200°F shall be examined in accordance with the requirements specified in Table ISC-261 ." 2. Inspection programs for ASME Code Class 32 components should be performed according to the following schedules:
a. All of the components should be pressure It tested and inspected at least once during each 10-year inspection interval.b. In addition, all components should be inspected during periods of normal reactor operation or during system performance testing at least once during every one-third of each inspection interval.3. Inspection requirements for ASME Code Class 3 components should include the following:
a. System pressure tests should be performed to the extent necessary to perform the component examination.


Test pressure should be at least: (1) For closed systems, 110 percent of the design pressure.(2) For open storage tanks, the nominal hydrostatic pressure developed with the tanks filled to design capacity.(3) Open-ended portions of systems may be exempted from pressure testing.b. Visual inspections for evidence of unanticipated component leakage, structural distress.
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.


or corrosion.
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.


c. Inspection of supports and hangers for piping and components over 4 inches in diameter for evidence of inadequate support, unintended restraint, or strurtural distress.4. Records of the inserice inspection should be established and maintained for the life of the plant and should include: a. Identification of systems components inspected;
It
b. Date of inspection;
                                                                1.5 1-2}}
c. Repair or replacement;
and d. Signature of employee certifying dte inspection was made.1.5 1-2}}


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Latest revision as of 10:12, 4 November 2019

Inservice Inspection of ASME Code Class 2 and 3 Nuclear Power Plant Components
ML13350A361
Person / Time
Issue date: 05/31/1973
From:
US Atomic Energy Commission (AEC)
To:
References
RG-1.051
Download: ML13350A361 (2)
v • d • e


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


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