Regulatory Guide 1.51: Difference between revisions

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{{#Wiki_filter:4"'*1*.(L.4`U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:4"'*1*.(L.4`U.S. ATOMIC ENERGY COMMISSION
R GULATORYDIRECTORATE
R GULATORY DIRECTORATE
OF REGULATORY  
OF REGULATORY  
STANDARDS
STANDARDS May 1973 GUIDE INSEF REGULATORY
May 1973GUIDEINSEFREGULATORY
GUIDE 1.51 IVICE INSPECTION  
GUIDE 1.51IVICE INSPECTION  
OF ASME CODE CLASS 2 AND 3 NUCLEAR POW  
OF ASME CODE CLASS 2AND 3 NUCLEAR POW


==A. INTRODUCTION==
==A. INTRODUCTION==
General Design Criteria  
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.
36. "Inspection ofEmergency Core Cooling System."  
39. "Inspection ofContainment Heat Removal System."  
42, "Inspection ofContainment Atmosphere Cleanup Systems,"  
and 45."Inspection of Cooling Water System,"  
of Appendix Ato 10 CFR Part 50. "Generzl Desian Criteria for NuclearPower Plants,"  
require that the subject systems bedesigned to permit appropriate periodic inspection ofimportant component parts of the systems to assuresystem integrity and capability.


Regulatory Guide 1.26(Safety Giuide 26). "Quality Group Classification andStandards,"  
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.
in conjunction with § 50.55a of 10 CFRPart 50 describes a quality classification system relatedto specified industry codes that may be used todetermine quality standards for water- andsteam-containing components important to the safety ofwater-cooled nuclear power plants. This guide describes acceptable methods of implementing the periodicinservice inspection requirements for American Societyof Mechanical Engineers (ASME) Code Class 2 and 3components.


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


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


==B. DISCUSSION==
==B. DISCUSSION==
The ASME Boiler and Pressure Vessel Code (ASMEB&PV Code), Section XI, "Rules for Inservice Inspection of Nuclear Reactor Systems."'  
The ASME Boiler and Pressure Vessel Code (ASME B&PV Code), Section XI, "Rules for Inservice Inspection of Nuclear Reactor Systems."'  
specifies requirements for ilservice inspection of Code Class 12'Copies may he obtained from American Society ofMechanical Enqincers.
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 47thStreet, New York, N.Y. 100 17.IC6mponents classified as AEC Quality Group A. B, and Cshould conform to the requirements of the ASSlI' Boiler andPressure Vessel Code for Class I. 2. and 3 components, resp ctivel
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


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


Code Class 32components are not presently included in Section X1requirements, but they should also be part of thescheduled inservice inspection program.
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.
 
The inspection requirements need not be as extensive as those requiredfor Code Class 2 components but should, as a minimum.include visual inspection of Code Class 3 componentb and their supports.


For such inspections to be effective.
For such inspections to be effective.


they should be performed at periods when thecomponents are under pressure of sutficienti nagnitude to properly represent the intended service condition.
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 systemperformance tests, component functional tests, andsystem pressure tests in order to benefit from thepressure levels established for these tests. Section XIdefines an inspection interval for Code Class I and 2components as 10 years, and the inservice inspection program for Code Class 3 components should be basedon the same time interval.
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.


Code Class 3 components required to functionduring normal reactor operation would generally heaccessible during reactor downtime, and they should beinspected at least once toward the end ot eachinspection 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.


Components in systems or portiovri of systems which are not required to futiction duringreactor operation can be inspected independently ofreactor downtime.
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.


The visual inspection of Code Class 3 components should be conducted for signs or evidence of leak.:'ccaused by structural distress or corrosion effects on the,components.
or structur:al distress."ASME B&PV Code, Sectiotni Xl. Wintter 1972 Addtend


In addition, supports and hangers liltpiping and Code Class 3 componenls over 4 inches illdianicter should be inspected for evidence of inadcqmtm support, unintended restrmint.
====a. USAEC REGULATORY ====
 
or structur:al distress.
 
"ASME B&PV Code, Sectiotni Xl. Wintter 1972 Addtenda.
 
USAEC REGULATORY  
GUIDES Copies of publiihed guide% may be obtained by es.luftl indicating the div~iun;desired to the US. Atomic Energy Cumr,$,s.on.
GUIDES Copies of publiihed guide% may be obtained by es.luftl indicating the div~iun;desired to the US. Atomic Energy Cumr,$,s.on.


Line 77: Line 61:
Director of negulatnry Stsnd3ordi.
Director of negulatnry Stsnd3ordi.


Coermtnts  
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.
, 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 SetjPrithe Comminsion's tegulisions, to dielinete uStit by 9.- staff in of the U.S. Alomic Enetriv Cunmmostun.


Vlh.hirigit..  
Vlh.hirigit..  
Line 87: Line 70:


Methodt and differont frmt ihoos %st out in The guides are issued in the follosring ton brail drisic.ni:
Methodt and differont frmt ihoos %st out in The guides are issued in the follosring ton brail drisic.ni:
the guides wvill be acceputable if they provide a batis far tim finrdmtlt reQuitl-l tothe 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 rtniin3. Fuels anor M4teiitis FaitIlt," .
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," .
HeaslthPublihhed guiders will be revised periodicull,.  
Heaslth Publihhed guiders will be revised periodicull,.  
at apOraOrtipr.,  
at apOraOrtipr., to accomnodate  
to accomnodate  
4. Environtat.rll am Sam)t', 9. Antitrust Review eproetients and to reflect new infoorntatOn of experience.
4. Environtat.rll am Sam)t', 9. Antitrust Revieweproetients and to reflect new infoorntatOn of experience.


S. Materitls  
S. Materitls  
Line 98: Line 80:


===0. General ===
===0. General ===
'I,The pressure developed in components during asystem performance lest, a component performance test,or a system pressure test should be representative ofconditions under which the systems should be leaktight during operation.
'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 least110 percent of the system design pressure.
 
However.


thepressure developed during the conduct of a periodicsystem performance test would be acceptable duringinspections conducted in periods between the pressuretests. Certain components.
The lest pressure should be at least 110 percent of the system design pressure.


such as open storage tanksincluding piping to the first shutoff valve, cannot readilybe pressure tested. The hydrostatic pressure developed with tanks filled to their design capacity would be anacceptable test pressure for such tanks and connected piping.C. REGULATORY
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.
POSITIONI. Inservice inspection requirements for ASME CodeClass 22 components should comply with the ASMEB&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 systemswhich recirculate reactor coolant during normalreactor operation, and are designed for pressure andtempcrature in excess of either 275 psig or 200°Fshall be examined in accordance with therequirements specified in Table ISC-261 ."2. Inspection programs for ASME Code Class 32components should be performed according to thefollowing schedules:
a. All of the components should be pressureIttested and inspected at least once during each 10-yearinspection interval.


b. In addition, all components should be inspected during periods of normal reactor operation or duringsystem performance testing at least once during everyone-third of each inspection interval.
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
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.


3. Inspection requirements for ASME Code Class 3components should include the following:
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.
a. System pressure tests should be performed tothe extent necessary to perform the component examination.
 
Test pressure should be at least:(1) For closed systems,  
110 percent of thedesign pressure.
 
(2) For open storage tanks, the nominalhydrostatic pressure developed with the tanks filled todesign capacity.
 
(3) Open-ended portions of systems may beexempted from pressure testing.b. Visual inspections for evidence of unanticipated component leakage, structural distress.


or corrosion.
or corrosion.


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


{{RG-Nav}}
{{RG-Nav}}

Revision as of 18:29, 13 July 2018

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"'*1*.(L.4`U.S. ATOMIC ENERGY COMMISSION

R GULATORY DIRECTORATE

OF REGULATORY

STANDARDS May 1973 GUIDE INSEF REGULATORY

GUIDE 1.51 IVICE INSPECTION

OF ASME CODE CLASS 2 AND 3 NUCLEAR POW

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.

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.

This guide applies to light-water-cooled reactors.

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

B. DISCUSSION

The ASME Boiler and Pressure Vessel Code (ASME B&PV Code),Section XI, "Rules for Inservice Inspection of Nuclear Reactor Systems."'

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

y. TER PLANT COMPONENTS

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.

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.

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.

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

a. 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.Regulatory Guides are issued /o describe and ,'r1te available lt. the public Attention:

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.

Vlh.hirigit..

D.C. 20U-45.e'llualtng specific problems or pOstulated at to provide gait'enco in Attention:

Chief. Pubic Proceedings Sliit.applicants.

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

Methodt and differont frmt ihoos %st out in The guides are issued in the follosring ton brail drisic.ni:

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," .

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

&nd Plant Protection

1

0. General

'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.

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.

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

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.

or corrosion.

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;

b. Date of inspection;

c. Repair or replacement;

and d. Signature of employee certifying dte inspection was made.1.5 1-2


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