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{{Adams
{{Adams
| number = ML003740132
| 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
| author affiliation = NRC/RES, US Atomic Energy Commission (AEC)
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.49, Rev 1
| document report number = RG-1.049
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 2
| page count = 1
}}
}}
{{#Wiki_filter:
{{#Wiki_filter: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==
==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, 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
* 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 application's for standardized plants will not be limited to light-water-cooled reactors.
* Lines indicate substantive changes from previous issue.Revision 1 December 1973 GUIDE


==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 increase 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.
It is the policy of the Atomic Energy Commission                                    The power levels of water-cooled nuclear power to encourage, support, and give priority consideration to                          plants have shown a continual increase from about 600
 
activities leading to greater standardization of nuclear                              megawatts electric in 1965 to slightly above 1,300
The increase in plant power levels, and the associated design modifications, have made standardization of designs difficult to achieve.
                                                                                    megawatts electric in 1973. The continual increase in the power plants. In a statement issued on March 5, 1973, size of these plants has resulted in plant design implementing that policy, the Commission stated that                                modifications and a large expenditure of' AEC staff the size of all new plants accepted for licensing review                            review effort to assure the maintenance of a consistent (both those proposed for review as standardized plants                              level of safety. These numerous plant design variations, and those proposed for review in connection with a                                  coupled with the rapidly increasing number of specific application for a construction permit) would be                            applications, have contributed to the steady growth in limited to power levels of less than 3,800 megawatts the required licensing ieview time to evaluate such applications. Until sufficient experience is gained with thermal.
 
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.
 
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.
 
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.
 
Comments 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, "eisuating 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 besis for the findings requisite to the issuance or continuance of a permit or license by the Commission.
 
1. Power Reactors C Products 2. Research and Test Reactors
 
===7. Transportation ===
3. Fuels and Materials Facilities
8. Occupational Health Publishad guides will be revised periodically, as appropriate, to accommodate
4. Environmental and Siting 9. Antitrust Review commants and to reflect new information or experienca.


5. Materials and Plant Protection
the design, construction, and operation of the larger plants, the size of these plants should be limited to Section 50.34 of 10 CFR Part 50 requires that each                          current levels.
10. General U.S. ATOMIC ENERGY COMMISSION
REGULATORY
DIRECTORATE
OF REGULATORY
STANDARDS
REGULATORY
GUIDE 1.49 POWER LEVELS OF NUCLEAR POWER PLANTS
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.
application for a construction permit include a summary description and discussion of the facility with special                                             


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.
==C. REGULATORY POSITION==
attention to, among other things, the design and operating characteristics at the projected initial licensed                                The projected initial licensed power level of a power level. Section 50.34- also requires that the                                  water-cooled nuclear power. plant for which a application include an analysis and evaluation of the                                construction permit application is filed pursuant to major structures, systems, and components of the                                    Section 50.34 of 10 CFR Part 50 should be limited to a facility at the projected initial power level and at the                            reactor core power level of 3,800 megawatts thermal or ultimate power level which is contemplated by the                                  less. The ultimate power level for which an analysis and applicant. This guide describes acceptable maximum                                  evaluation        ot    the      major    structures,      systems.  and power levels for water-cooled nuclear power plants.                                components is required should be limited to 4.100
                                                                                    megawatts thermal or less.


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.
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.


C. REGULATORY
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:
POSITION I .The proposed licensed power level of all nuclear Ipower 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 Tof 3800 megawatts thermal or less until January 1, 11979, 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.
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                         


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}}
===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}}


{{RG-Nav}}
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Latest revision as of 22:02, 11 November 2019

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

B. DISCUSSION

It is the policy of the Atomic Energy Commission The power levels of water-cooled nuclear power to encourage, support, and give priority consideration to plants have shown a continual increase from about 600

activities leading to greater standardization of nuclear megawatts electric in 1965 to slightly above 1,300

megawatts electric in 1973. The continual increase in the power plants. In a statement issued on March 5, 1973, size of these plants has resulted in plant design implementing that policy, the Commission stated that modifications and a large expenditure of' AEC staff the size of all new plants accepted for licensing review review effort to assure the maintenance of a consistent (both those proposed for review as standardized plants level of safety. These numerous plant design variations, and those proposed for review in connection with a coupled with the rapidly increasing number of specific application for a construction permit) would be applications, have contributed to the steady growth in limited to power levels of less than 3,800 megawatts the required licensing ieview time to evaluate such applications. Until sufficient experience is gained with thermal.

the design, construction, and operation of the larger plants, the size of these plants should be limited to Section 50.34 of 10 CFR Part 50 requires that each current levels.

application for a construction permit include a summary description and discussion of the facility with special

C. REGULATORY POSITION

attention to, among other things, the design and operating characteristics at the projected initial licensed The projected initial licensed power level of a power level. Section 50.34- also requires that the water-cooled nuclear power. plant for which a application include an analysis and evaluation of the construction permit application is filed pursuant to major structures, systems, and components of the Section 50.34 of 10 CFR Part 50 should be limited to a facility at the projected initial power level and at the reactor core power level of 3,800 megawatts thermal or ultimate power level which is contemplated by the less. The ultimate power level for which an analysis and applicant. This guide describes acceptable maximum evaluation ot the major structures, systems. and power levels for water-cooled nuclear power plants. components is required should be limited to 4.100

megawatts thermal or less.

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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