ML19221A761
| ML19221A761 | |
| Person / Time | |
|---|---|
| Issue date: | 02/28/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0555, NUREG-0555-03.2, NUREG-555, NUREG-555-3.2, SRP-03.02, SRP-3.02, NUDOCS 7907090064 | |
| Download: ML19221A761 (7) | |
Text
Section 3.2 February 1979 ENVIRONMENTAL STANDAPD REVIEW PLAN FOR ES SECTION 3.2 REACTOR STEAM-ELECTRIC SYSTEM REVIEW INPUTS Environmental Report Sections 3.2 Reactor and Steam-Electric System Environmental Reviews None Standards and Guides Paragraph (g) of 10 CFR S51.20, " Applicant's Environmental Report -
Const ruction Permit Stage" Other Responses to requests for additional information Applicant's Preliminary Safety Analysis Report (if tendered with the ER)
REVIEW OUTPUTS Environmental Statement Sections 3.2 Reactor Steam-Electric System Other Environmental Reviews 3.8 Transportation of Radioactive Mater;als 5.3.2 Cooling-System Impacts: Discharge System (Operation) 10.2 Irreversible and Irretrievable Commitments of Resources I.
PURPOSE AND SCOPE The purpose of this environmental standard review plan (ESRP) is to direct the staff's description of the reactor and generator equipment.
The scope of the review directed by this plan includes the type and size of reactor 107 255 70 709007 3.2-1
February 1979 and generator equipment and their major performance parameters. This informa-tion will support subsequent environmental reviews that assess operational impt cts and commitments of resources.
II.
REQUIRED DATA AND INFORMATION The following data or information will usually be required:
A.
Number of units and description of each reactor, including type (e.g., BWR, PWR, HTGR), manufact rer, fuel assembly description, total quantities of uranium, and percentage U-235 enrichment (from the ER).
B.
Planned average irradiation level of spent fuel, in megawatt days / tonne (from the ER).
C.
Description of the turbines and condensers.
For the condensers, include tubing material and total heat transfer.rea (from the ER).
D.
The rated and design core thermal power, the rated and design gross electrical output, and the rated ard design net electrical output (in megawatts).
The rated power is defined as the power level at which each reactor will be operated if licensed, and the design power is defined as the highest power level that would be permitted by plant design. Tne gross electrical output is the power level measured at the output terminals of the generator and expressed i n MWe.
The net unit electrical output is equal to the gross electrical output minus f r.c no.ninal service and auxiliary loads (from the ER).
E.
Simplified flow diagram for tne reactor steam-electri system (f rom the ER).
107 256 3.2-2
February 1979 III.
ANALYSIS PROCEDURE The material to be reviewed is informational in nature, and no specific analysis of the data is required.
The reviewer will compare the proposed design parameters with those of similar operating plants and identify any features of the proposed system that represent a departure from previously reviewed plants.
IV.
EVALUATION Since this material is for description only, the reviewer must ensure that adequate information is available to meet the purpose and scope of this section. The reviewer will identify the reactor steam-electric system manufac-turers and the basic design performance data.
As a rule, it the data are provided as given in Section II, Required Data and Information, that objective will be met.
The reviewer will compare reactor design and performance data with the criteria of subparagraphs (2) (i), (ii), and (iii) of paragraph (g) of 10 CFR g51. 20, and will notify the reviewer for ES Section 3.8 of any departures from these criteria.
V.
INPUT TO THE ENVIRONMENTAL STATEMENT The input to the environmental statement should include a summary descrip-tion of the reactor steam-electric system, a flow diagram, and a table of design and performance parameters. Appendix A to this ESRP is an example of a reactor steam-electric system description for ES Section 3.2.
The reviewer will provide inputs 3r ensure thr.t inputs will be made to the following ES Sections:
A.
Section 3.8.
The reviewer will provide as input to ES Section 3.8 data on the basic reactor, fuel, and irradiation level that are required by paragraph (g) of 10 CFR g51.20.
3.2-3
February 1979 9
B.
Section 5.3.2.
The reviewer will provide as input to ES Section 5.3.2 a description of cooling system materials of construction that could be trans-ported to the aquatic environment.
C.
Section 10.2.
The reviewer will assist the reviewer of ES Sec-tion 10.2 in developing the list of irreversibly committed materials to be used in the reactor steam-electric system.
VI.
REFERENCES None O
a 107 2,3 W
3 3.2-4
Appendix A to ESRP 3.2 February 1970 ENVIh3NMENTAL STANDARD REVIEW PLAN FOR ES SECTION 3.2 REACTOR STEAM-ELECTRIC SYSTEM APPENDIX A SAMPLE FORMAT FOR ES SECTION 3.2 3.2 REACTOR STEAM-ELECTRIC SYSTEM The proposed plant will consist of a single Standardized Nuclear Unit Power Plant System (SNUPPS) and auxiliaries.
The power source will be a pressurized-light-water reactor supplied by Westinghouse Electric Corporation.
The operation of the reactor is shown in Figure 3.2-A-1.
In the primary loop, water under high pressure (so it cannot boil) is pumped through the reactor core where it is heated by contact with fuel rods containing uranium.
The heated water passes through the steam generators where the heat is transferred to the secondary loop, and then r.' urns to the core.
In the steam generators, water in the secondary loop is heated to boiling. This steam drives a turbine-generator system, is liquefied in the condenser, and returns to the steam generators. The condenser is cooled by water drawn from and returned to Lake 2
Ontario. Approximately 80,000 m ut titanium heat transfer surface is exposed to the cooling water.
The reactor has four primary loops and one secondary loop.
The turbine generator system will be manufactured by General Electric Company. Bechtel Power Corporation is the architect-engineer.
At design conditions, the plant will generate 1206 MWe net. electrical power and will reject 2359 MWt waste heat to the environment. More det..iled operating parameters are listed in Table 3.2-A-1.
The initial fuel loading will be 101,000 kg of cnriched uranium dioxide pellets contair.ed in 50,942 tubular f uel rods.
107 259 3.2-A-3
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February 1979 TABLE 3.2-A-1 OPERATING PARAMETERS Rated conditions Core thermal power, MWt Gross electrical generation, MWe Station service requirement, MWe Net electrical output, MWe Waste heat rejected, MWt Efficiency, %
Design conditions Core thermal power, MWt Gross electrical generation, MWe Station service requirement, MWe Net electrical output, MWe Waste heat rejected, MWt Efficiency, %
Fuel assemblies, number Fuel rods per assembly, number Initial enriched uranium loading, kg Initial enrichment range, %
2 Condenser heat transfer area, m 107 261 3.2-A-3