Regulatory Guide 1.49: Difference between revisions

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{{Adams
{{Adams
| number = ML12216A005
| number = ML12298A125
| issue date = 12/31/1973
| issue date = 05/31/1973
| title = Power Levels of Nuclear Power Plants
| title = Power Levels of Water-Cooled Nuclear Power Plants
| author name =  
| author name =  
| author affiliation = NRC/RES, US Atomic Energy Commission (AEC)
| author affiliation = NRC/RES, US Atomic Energy Commission (AEC)
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.049, Rev. 1
| document report number = RG-1.049
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 2
| page count = 1
}}
}}
{{#Wiki_filter:U.S. ATOMIC ENERGY COMMISSION
{{#Wiki_filter:May 1973 U.S. ATOMIC ENERGY COMMISSION
REGULATORY
REGULATORY
DIRECTORATE  
DIRECTORATE  
OF REGULATORY  
OF REGULATORY  
STANDARDS REGULATORY  
STANDARDS GUIDE REGULATORY  
GUIDE 1.49 POWER LEVELS OF NUCLEAR POWER PLANTS Revision 1 December 1973 GUIDE
GUIDE 1.49 POWER LEVELS OF WATER-COOLED
NUCLEAR POWER PLANTS  


==A. INTRODUCTION==
==A. INTRODUCTION==
Section 50.34 of 10 CFR Part 50 requires that each application for a construction permit include a summary description and discussion of the facility with special attention to, among other things, the design and operating characteristics at the projected initial power level (proposed licensed power level).Section 50.34 also requires that the application include an analysis and evaluation of the major structures, systems, and components of the facility which bear significantly on the acceptability of the site, under the site evaluation factors identified in 10 CFR Part 100, at the ultimate power level contemplated by the applicant.
It is the policy of the Atomic Energy Commission to encourage, support, and give priority consideration to activities leading to greater standardization of nuclear power plants. In a statement issued on March 5, 1973, implementing that policy, the Commission stated that the size of all new plants accepted for licensing review (both those proposed for review as standardized plants and those proposed for review in connection with a specific application for a construction permit) would be limited to power levels of less than 3,800 megawatts thermal.Section 50.34 of 10 CFR Part 50 requires that each application for a construction permit include a summary description and discussion of the facility with special attention to, among other things, the design and operating characteristics at the projected initial licensed power level. Section 50.34- also requires that the application include an analysis and evaluation of the major structures, systems, and components of the facility at the projected initial power level and at the ultimate power level which is contemplated by the applicant.


It is the policy of the Atomic Energy Commission to encourage, support, and give priority consideration to activities leading to greater standardization of nuclear power plants. In a statement issued on March 5, 1973, announcing its nuclear plant standardization policy, the Commission stated that the size of all new plants accepted for licensing review (both those proposed for review as standardized plants and those proposed for review in connection with a specific application for a construction permit) would be subject to a maximum* I power limit. 1 This guide describes acceptable maximum power levels for all nuclear power plants.The Regulatory staff study referred to in the Commission Policy Statement stated that only applications for light-water reactors would be accepted for review as standardized plants. The Regulatory staff has now determined that applications for standardized plants will not be limited to light-water-cooled reactors.* Lines indicate substantive changes from previous issue.
This guide describes acceptable maximum power levels for water-cooled nuclear power plants.


==B. DISCUSSION==
==B. DISCUSSION==
The design power levels of nuclear power plants have increased from about 600 megawatts electric in 1965 to slightly above 1300 megawatts electric in 1973.The continual ificrease in the size of these plants has resulted in many plant design modifications and in a large expenditure of AEC staff review effort to assure the maintenance of a consistent level of safety. These numerous plant design variations, coupled with the rapidly increasing number of applications, have contributed to the steady growth in the required licensing review effort to evaluate such applications.
The power levels of water-cooled nuclear power plants have shown a continual increase from about 600 megawatts electric in 1965 to slightly above 1,300 megawatts electric in 1973. The continual increase in the size of these plants has resulted in plant design modifications and a large expenditure of' AEC staff review effort to assure the maintenance of a consistent level of safety. These numerous plant design variations, coupled with the rapidly increasing number of applications, have contributed to the steady growth in the required licensing ieview time to evaluate such applications.


The increase in plant power levels, and the associated design modifications, have made standardization of designs difficult to achieve.The intent of the AEC policy on plant power levels is also to stabilize the maximum size of nuclear plants until sufficient experience is gained with design, construction, and operation of large plants. The first plants in the 1100-megawatt electric class are now in the startup phase. The Regulatory staff believes that a substantial time period should elapse before maximum licensed core thermal power levels are changed.Accordingly, construction permit applications should not be submitted for plants of core thermal power levels greater than 3800 megawatts before January 1, 1979, at the earliest.
Until sufficient experience is gained with the design, construction, and operation of the larger plants, the size of these plants should be limited to current levels.C. REGULATORY
POSITION The projected initial licensed power level of a water-cooled nuclear power. plant for which a construction permit application is filed pursuant to Section 50.34 of 10 CFR Part 50 should be limited to a reactor core power level of 3,800 megawatts thermal or less. The ultimate power level for which an analysis and evaluation ot the major structures, systems. and components is required should be limited to 4.100 megawatts thermal or les


The AEC will issue notice of its intent to consider applications at core thermal power levels greater than 3800 megawatts at least two years prior to acceptance of such applications.
====s. USAEC REGULATORY ====
 
GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public Attention:  
In determining, subsequent of January 1, 1979, the acceptability of any increase in the maximum licensed power level, the operating history of large plants will be carefully reviewed.Some of the analyses in support of the proposed licensed power level are made for a slightly higher assumed power level to allow for possible instrument USAEC REGULATORY  
GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20645, Regulatory Guides are issued to describe and make available to the public Attention:  
Director of Regulatory Standards.
Director of Regulatory Standards.


Comments and suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of Improvements in these guides we encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in of the Commission, U.S. Atomic Energy Commission, Washington, D.C. 20645, evaluating specific problems or postulated accidents, or to provide guidance to Attention:  
Conments and suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of improvements in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in of the Commission, U.S. Atomic Energy Commission, Washington D.C. 20545, evaluating specific problems or postulated accidents, or to provide guidance to Attention:  
Chief, Public Proceedings Staff.applicents.
Chief, Public Proceedings Staff.applicants.


Regulatory Guides am not substitutes for regulations and compliance VA" them is not required.
Regulatory Guides are not substitutes for regulations and compliance with them is not required.


Methods and solutions different from those set out in The guides are issued in the follvoing ton broad divisions:
Methods and solutions different from those set out in The guides are issued in the following ten broad divisions:
the guides will be acceptable if they provide a basis for the findings requisite to the eudiapos or continuance of a permit or license by the Commission.
the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.


1. Power Reactors 6. Products 2. Research and Test Reactors  
1. Power Reactors 6. Products 2. Research and Test Reactors 7. Transpcrtat,on
 
===7. Transportation===
3. Fuels and Materials Facilities  
3. Fuels and Materials Facilities  
8. Occupational Health Published gl=es will be revised periodicelly, ft appropriate.
8. Occupational Health Published guides will be revised periodically, as appropriate, to accommodate  
 
4. Environmental and Siting 9. Antitrust Review comments and to reflect new information or experience.
to accommodate  
4. Environmental and Siting 9. Antitrust Review comments Indto reflect new information or experience.
 
5. Materials end Plant Protection
10. General errors in determing the power level. The Regulatory staff has determined that a margin of two percent of the licensed power level is adequate for this purpose.Analyses of the possible offsite radiological consequences of postulated design-basis accidents made to demonstrate acceptability of the site in accordance with 10 CFR Part 100 should be performed for at least 1.02 times the proposed licensed core power level or may, at an applicant's discretion, be made at a somewhat higher power level to account for the margin which may be provided in turbine-generator designs above rated capacity.
 
The Regulatory staff believes that a reasonable maximum allowance for this additional capacity and for instrument error is provided by a limit of 4100 megawatts thermal on ultimate core power level for Part 100-related analyses.
 
The staff will regard such analyses as supporting operation of the facility at a proposed licensed core power level no greater than 3800 megawatts thermal.C. REGULATORY
POSITION I 1. The proposed licensed power level of all nuclear power plants for which a construction permit application is filed pursuant to Section 50.34 of 10 CFR Part 50 should be limited to a reactor core power level lof 3800 megawatts thermal or less until January 1, 1979, at the earliest.2. Analyses and evaluation in support of the application should be made at an assumed core power level equal to 1.02 'times the proposed licensed power level (with a maximum acceptable value of 1.02 times 3800, or 3876 megawatts thermal) for (a) normal operating conditions, (b) transient conditions anticipated during the life of the facility such as load changes, control rod malfunctions and improper operations, loss of forced coolant flow, loss of load .or turbine trip, loss of normal a-c power, primary system depressurization, etc., and (c) accident conditions necessary to evaluate the adequacy of structures, systems, and components provided for the prevention of accidents and the mitigation of the consequences of accidents.


3. Analyses of the possible offsite radiological consequences of postulated design-basis accidents made to demonstrate acceptability of the site in accordance with 10 CFR Part 100 should be performed for an assum-ed core power level equal to 1.02 times the proposed licensed power level or may, at an applicant's discretion, be made at a higher power level, not to exceed 4100 megawatts thermal. Analyses made at an assumed core power level greater than 1.02 times the proposed licensed power level should be regarded as supporting operation of the facility at a proposed licensed core power level no greater than 3800 megawatts thermal.1.49-2}}
5. Materials and Plant Protection
10. General}}


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

Revision as of 22:07, 27 July 2018

Power Levels of Water-Cooled Nuclear Power Plants
ML12298A125
Person / Time
Issue date: 05/31/1973
From:
Office of Nuclear Regulatory Research, US Atomic Energy Commission (AEC)
To:
References
RG-1.049
Download: ML12298A125 (1)
v • d • e


May 1973 U.S. ATOMIC ENERGY COMMISSION

REGULATORY

DIRECTORATE

OF REGULATORY

STANDARDS GUIDE REGULATORY

GUIDE 1.49 POWER LEVELS OF WATER-COOLED

NUCLEAR POWER PLANTS

A. INTRODUCTION

It is the policy of the Atomic Energy Commission to encourage, support, and give priority consideration to activities leading to greater standardization of nuclear power plants. In a statement issued on March 5, 1973, implementing that policy, the Commission stated that the size of all new plants accepted for licensing review (both those proposed for review as standardized plants and those proposed for review in connection with a specific application for a construction permit) would be limited to power levels of less than 3,800 megawatts thermal.Section 50.34 of 10 CFR Part 50 requires that each application for a construction permit include a summary description and discussion of the facility with special attention to, among other things, the design and operating characteristics at the projected initial licensed power level. Section 50.34- also requires that the application include an analysis and evaluation of the major structures, systems, and components of the facility at the projected initial power level and at the ultimate power level which is contemplated by the applicant.

This guide describes acceptable maximum power levels for water-cooled nuclear power plants.

B. DISCUSSION

The power levels of water-cooled nuclear power plants have shown a continual increase from about 600 megawatts electric in 1965 to slightly above 1,300 megawatts electric in 1973. The continual increase in the size of these plants has resulted in plant design modifications and a large expenditure of' AEC staff review effort to assure the maintenance of a consistent level of safety. These numerous plant design variations, coupled with the rapidly increasing number of applications, have contributed to the steady growth in the required licensing ieview time to evaluate such applications.

Until sufficient experience is gained with the design, construction, and operation of the larger plants, the size of these plants should be limited to current levels.C. REGULATORY

POSITION The projected initial licensed power level of a water-cooled nuclear power. plant for which a construction permit application is filed pursuant to Section 50.34 of 10 CFR Part 50 should be limited to a reactor core power level of 3,800 megawatts thermal or less. The ultimate power level for which an analysis and evaluation ot the major structures, systems. and components is required should be limited to 4.100 megawatts thermal or les

s. USAEC REGULATORY

GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20545, Regulatory Guides are issued to describe and make available to the public Attention:

Director of Regulatory Standards.

Conments and suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of improvements in these guides are encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in of the Commission, U.S. Atomic Energy Commission, Washington D.C. 20545, evaluating specific problems or postulated accidents, or to provide guidance to Attention:

Chief, Public Proceedings Staff.applicants.

Regulatory Guides are not substitutes for regulations and compliance with them is not required.

Methods and solutions different from those set out in The guides are issued in the following ten broad divisions:

the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.

1. Power Reactors 6. Products 2. Research and Test Reactors 7. Transpcrtat,on

3. Fuels and Materials Facilities

8. Occupational Health Published guides will be revised periodically, as appropriate, to accommodate

4. Environmental and Siting 9. Antitrust Review comments and to reflect new information or experience.

5. Materials and Plant Protection

10. General


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