ML19312A205
| ML19312A205 | |
| Person / Time | |
|---|---|
| Site: | 05000495 |
| Issue date: | 11/29/1978 |
| From: | NEW YORK STATE ELECTRIC & GAS CORP., STONE & WEBSTER, INC. |
| To: | |
| References | |
| NUDOCS 7909050272 | |
| Download: ML19312A205 (541) | |
Text
SWESSAR-P1 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PIANT TABLE OF CONTENTS Section Page Foreword Foreword-1
1.1 INTRODUCTION
1.1-1 1.2 GENhRAL PLANT DESCRIPTION 1.2-1 1.2.1 General 1.2-1 1.2.2 Site 1.2-1 1.2.3 Structures 1.2-1 1.2.4 Nuclear Steam Supply System 1.2-2 1.2.5 Instrumentation and Control Systems 1.2-2A 1.2.6 Reactor and Plant Controls 1.2-3 1.2.7 Radioactive Waste Systems 1.2-3 1.2.8 Fuel Handling 1.2-4 1.2.9 Turbine and Turbine Auxiliaries 1.2-4 1.2.10 Electrical Systems 1.2-5 1.2.11 Engineered Safety Features 1.2-5 1.2.12 Other A'axiliary Systems 1.2-7 1.3 COMPARISON TABLES 1.3-1 1.3.1 Comparison with Similar Facility Designs 1.3-1 1.3.1.1 Comparison of Nuclear Steam Systems 1.3-1 1.3.1.2 Con.parison of Engineered Safety Features 1.3-1 1.3.1.3 Comparison of Containment Concepts 1.3-1 1.3.1.4 Comparison of Instrumentation Systems 1.3-1 1.3.1.5 Comparison of Electrical Systems 1.3-1 1-i Amendment 1 bbOO/jf
SWESSAR-P1 TABLE OF CONTENTS (CONT)
Page Section 1.3.1.6 Comparison of Waste Systems 1.3-2 1.3.1.7 Comparison of Other Nuclear Plant Systems 1.3-2 1.3.1.8 Comparison of Structural Design Characteristics 1.3-2 1.4 IDENTIFICATIO!J OF AGENTS AND CONTRACTORS 1.4-1 1.4.1 Stone S Webster Engineering Corporation 1.4-1 1.5 REQUIREMENTS FOR FURTiiER TECHIJICAL INFORMATION 1.5-1 1.6 PATERIAL INCORPORATED bY ltEFERE!JCE 1.6-1 1.6.1 Topical Reports 1.6-1 1.6.2 Other Reference Material 1.6-1 1.7 TERMILOLOGY AND FLOW DIAGRAM SYMEOLS 1.7-1 1.8 INTERFACE WITH NSSS VENDOR AND IfrILITY-APPLICANT SARs 1.8-1 O
L(2CbN 1-li Amendment 1
'//30/74
SWESSAR-P1 LIST OF TABLES Table 1.1-1 SWESSAR Design Power Levels 1.2-1 Deleted 1.3.1.2-1 Comparison of Engineered Saf ety Features 1.3.1.3-1 Comparison of Containment Concepts 1.3.1.4-1 Comparison of Emergency Diesel Generator and Auxiliary Feedwater Pump Signals 1.3.1.4-2 Comparison of Process and Effluent Radiation Monitoring Systems 1.3.1.4-3 Comparison of Area Radiation Monitoring Systems 1.3.1.4-4 Comparison of Airborne Radiation Monitoring Systems 1.3.1.5-1 Comparison of Electrical Systems 1.3.1.6-1 Comparison of Radioactive Liquid Waste Systems 1.3.1.6-2 Comparison of Radioactive Gaseous Waste Systems 1.3.1.6-3 Comparison of Radioactive Solid Waste Systems 1.3.1.7-1 Comparison of Other Reactor Plant Systems 1.3.1.8-1 Comparison of Structural Design Characteristics 1.5-1 Deleted 25 1.5-2 Deleted 1.6-1 NSSS Vendor SARs Incorporated by Reference 1.6-2 hESAR-41 System Modifications 1.6-2 RESAR-3S System Modifications 1.6-2 CESSAR System Modifications 1-iii Amendment 25 af0C /(8 4/30/76
SWESSAR-P1 LIST OF TABLES (CONT) g Table 1.6-2 B-SAR 205 System Modifications 1.7-1 Comparison of Terminology of NSSS Vendor Supplied Systems and Equipment 1.7-2 Comparison of Terminology of Engineered Safety Features Actuation Signals 1.7-3 Building Arrangement Figure Numbers with Corresponding SSW Drawing Numbers 1.8-1 Identification of Design Responsibility 1.8-2 Utility-Applicant Input Required for Complete Safety Analysis Report 1.8-3 Fluid System Interfaces 1.8-4 Location of NSSS Interface Requirements in SWESSAR-P1 1.8-5 Location of Utility-Applicant Interface Requirements in SWESSAR-P1 h 1.8-6 Interfaces Between SSW Fluid Systems 1.8-7 Cross Reference of Design Requirements for Chapter 9 and 10 Systems l-iv Amendment 21 9
2/20/76 66001T
SWESSAR-P1 LIST OF FIGURES Fiqure 1.1-1 Artist's Conception of Station Arrangement 1.2-1 Plot Plan, Sheet 1 1.2-1 Plot Plan, Sheet 2 1.2-2 General Arrangement Normal Switchgear Building 1.2-3 General Arrangement Containment Structure, Sheet 1 1.2-3 General Arrangement Containment Structure, Sheet 2 1.2-3 General Arrangement Containment Structure, Sheet 3 1.2-3 General Arrangement Containment Structure, Sheet 4 1.2-3 General Arrangement Containment Structure, _'heet 5 1.2-3 General Arrangement Containment Structure, Sheet 5 1.2-3 General Arrangement Containment Structure, Sheet 6 1.2.3 General Arrangement Containment Structure, Sheet 7 1.2-4 General Arrangement Annulus Building, Sheet 1 1.2-4 General Arrangement Annulus Building, Sheet 2 1.2-4 General Arrangement Annulus Building, Sheet 3 1.2-4 General Arrangement Annulus Building, Sheet 4 1.2-4 General Arrangement Annulus Building, Sheet 5 1.2-4 General Arrangement Annulus Building, Sheet 6 1.2-4 General Arrangement Annulus Building, Sheet 7 1.2-4 General Arrangement Annulus Building, Sheet 8 1.2-4 General Arrangement Annulus Building, Sheet 9 1.2-4 General Arrangement Annulus Building, Sheet 10 1.2-4 General Arrangement Annulus Building, Sheet 11 g 1.2-4 General Arrangement Annulus Building, Sheet 12 1- ivA g.g Amendment 9 4/30/75
SWESSAR-P1 LIST OF FIGURES (CONT)
Figure 1.2-4 General Arrungement Annulus Building, Sheet 13 1.2-4 General Arrangement Annulus Building, Sheet 14 1.2-4 General Arrangement Annulus Building, Sheet 15 1.2-4 Genera 1 Arrangement Annulus Building, Sheet 16 1.2-4 General Arrangement Annulus Building, Sheet 17 1.2-4 General Arrangement Annulus Building, Sheet 18 1.2-4 Genera) Arrangesnent Annulus Building, Sheet 19 l 1.2-4 Geiseral Arrangement Annulus Building, Sheet 20 17 (W-3S only) 1.2-5 General Arrangemehlt Cbntrol Building, Sheet 1 O
O 1-ivB bbOCf/ Amendment 17 9/30/75
SWESSAR-P1 LIST OF FIGURES (COtfr)
Figure 1.2-5 General Arrangement Control Building, Sheet 1 1.2-5 General Arrangement Control Building, Sheet 2 1.2-5 General Arrangement Cbntrol Building, Sheet 3 1.2-5 General Arrangement Control Building, Sheet 4 1.2-6 General Arrangement Diesel Generator Building, Sheet 1 (W-41) 1.2-6 General Arrangement Diesel Generator Building, Sheet 2 (W-41) 1.2-6 General Arrangement Dierel Generator Building for Two Train Systems (B&W , C-E , W-3S) , Sheet 1 1.2-6 General Arrangement Diesel Generator Building for Two Train Systems (B&W , C-E, W-3S), Sheet 2 1.2-7 General Arrangement Turbine Building, Sheet 1 1.2-7 General Arrangement Turbine Building, Sheet 2 1.2-7 General Arrangement Turbine Building, Sheet 3 1.2-7 General Arrangement Turbine Building, Sheet 4 1.2-7 General Arrangement Turbine Building, Sheet 5 1.2-8 General Arrangement Fuel Building, Sheet 1
- 1. 2 -8 General Arrangement Fuel Building, Sheet 2 1.2-8 General Arrangement Fuel Building, Sheet 3 1.2-8 General Arrangement Fuel Building, Sheet 4 1.2-8 General Arrangement Fuel Building, Sheet 5 1.2-8 General Arrangement Fuel Building, Sheet 6 g 1.2-9 General Arrangement Solid Waste and Decontamination Building, Sheet 1 1.2-9 General Arrangement Solid Waste and Decontamination Building, Sheet 2 1-v bUbb b Amendment 19 12/12/75
SWESSAR-P1 LIST OF FIGURES (CONT)
Figure 1.2-10 Access and Egress Between Buildings, Sheet 1 1.2-10 Access and Egress Between Buildings, Sheet 2 1.2-10 Access and Egress Between Buildings, Sheet 3 1.2-10 Access and Egress Between Buildlings, Sheet 4 ig 1.2-10 Access and Egress Between Buildings, Sheet 5 1.7-1 Flow Diagram Symbols for Equipnent and Instrumen-tation, Sheet 1 1.7-1 Flow Diagram Symbols for Equipment and Instrumen-tation, Sheet 2 1.7-1 Flow Diagram Symbols for Equipment and Instrumen-tation, Sheet 3 1.7-1 Plow Diagram Symbols for Equipnent and Instrumen-tation, Sheet 4 O
O 1-vi Amendment 19 12/12/75 to00:s1
Di SWESSAR-P1
/Q '! CHAPTER 1
{ 37I W INTRODUCTION AND GENERAL DESCRIPTION OF PIANT LIST OF EFFECTIVE PAGES Page, Table (T) , Amendment Page, Table (T) , Amendment or Figure (F) No. or Fiqure (F) No.
1-a/b 38 (19 sheets) 1-i/ii 1 F1.2-S (C-E) (3 sheets) 38 1-iii 25 F1.2-6 (2 sheets) ~
17 1-iv 21 F1.2-b (W) (2 sheets) 1-1vA 9 F1.2-7 (5 sheets) 6 1-1va 17 F1.2.8 (W) (5 sheets) 8 1-v/vi 19 F1.2-8 (W-3S) 17 1.1-1 thru 3 17 (4 sheets)
T1.1-1 35 F1.2-8 (BSW) 19 F1.1-1 Orig (6 sheets) 1.2-1 thru 1.2-2A 18 F1.2-8 (C-E! 13 1.2-3 thru 5 9 (5 sheets) 1.2-6, 6A 17 F1.2-9 (2 sheets) 8 1.2-7/8 17 F1.2-10 (W) (4 sheets) 9 T1.2-1 18 F1.2-10 (W-3S) (4 sheets) 17 F1.2-1 (W) (2 sheets) 8 F1.2-10 maw) 19 F1.2-2 (W) 9 (5 sheetaJ F1.2-3 (W) (7 sheets) 8 F1.2-10 (C-E) 14 F1.2-4 (W) o (4 sheets)
(19 sheets) 1.3-1/2 17 F1.2-5 (W) (4 sheets) 9 T 1. 3.1.2 -1 (W) 17 F1.2-1 (W-3S) 17 (2 sheets)
(2 sheets) T1.3.1.2-1 (W-3S) 27 F1.2-2(W-3S) 17 (2 sheets)
F1.2-3 (W-3S) 17 T1.3.1.2-1 (BSW) 27 (6 sheets) (2 sheets)
F1.2-4 (W-38) 17 T1.3.1.2-1 (C-E) 17 (20 sheets) (2 sheets) 38 T1.3.1.3-1 17 F1.2-5 (W-3S) '11.3.1.4-1 (3 sheets) 19 F1.2-1 (B6W) (2 sheets) 19 T1.3.1.4-2 (2 sheets) 17 F1.2-2 (B&W) 19 T1.3.1.4-3 6 F1.2-3 (BSW) (sheets 1 33 T1.3.1.4-4 (2 sheets) 17 and 2) T 1. 3.1. 5- 1 (W) Orig F1.2-3 (BSW) T1.3.1.5-1 (W-35) 17 (sheets 3 thru 6) 19 T1.3.1.5-1 (B&W) 1 T1.3.1.5-1 (C-E) 3 (F 1. 2-3 (BSW)
\ (sheet 7) 33 T1.3.1.6-1 (2 sheets) 17 F1.2-4 (BSh) 19 T1.3.1.6-2 (2 sheets) 17 (19 sheets) T1.3.1.6-3 (2 sheets) 17 F1.2-5 (B&W) Orig T1.3.1.7-1 (3 sheets) 17 (4 sheets) T1.3.1.8-1 Orig l*4-1 Orig F1.2-1 (C-E) (2 sheets) 11 1.5-1 25 F1.2-2 (C-E) 15 T1.5-1 25 F1.2-3 (C-E) (7 sheets) 13 T1.5-2 25 F1.2-4 (C-E) 13 1-a % C C50 Amendment 38 S/31/78
SWESSAR-P 1 LIST OF EFFECTIVE PAGES (CONT)
Page, Table (T), Amendment Page, Table (?) , Amendment @
or Fiqure (F) No. or Fiqure (F) No.
1.6-1 17 T1.8-3 (C-E) (sheet 1) 27 1.6-2 35 T1.8-3 (C-E) 21 T1.6-1 27 (sheets 2 thru 4)
T1.6-2 (W) 17 T1.8-3 (C-B) (sheet 5) 27 T1.6-2 (W-3S) (2 sheets) 18 T1. 8-3 (C-E) 21 T1.6-2 (BSW) 33 (sheets 6 6 7)
T1.6-2 (C-E) (2 sheets) 27 T1.8-3 (C-E) (sheet 8) 24 1.7-1 1 T1.8-3 (C-E) (sheet 8A) 23 T1.7-162 17 T1. 8-3 (C-E)
T1.7-3 18 (sheets 9 6 10) 21 F1.7-1 (sheets 16 2) Orig T1.8-4 (4 sheets) 25 F 1. 7 -1 (sheet 3) 4 T1.8-5 (sheet 161 A) 35 F1.7-1 (sheet 4) Orig T1.8-5 27 1.8-1 17 (sheets 2, 3) 1.8-2 20 T1.8-5 (sheet 4) 25 T1.8-1 (sheets 1,2, 20 T1.8-6 (8 sheets) 8 2A) T1.8-7 (3 sheets) 8 T1.8-1 (sheet 3) 17 T1.8-1 (sheet 4) 27 T1.8-1 (sheet 5) 5 T1.8-1 (sheet 6) 27 T1.8-1 17 (sheets 7 and 8)
T1.8-1 (sheets 9610) 5 T1.8-1 17 (sheets 11 thru 12A)
T1. 8-1 (sheet 13) 17 T1.8-1 (sheet 14) 5 T1. 8-1 (sheet 15) 27 T1.8-2 (sheet 1) 6
- T1.8-2 (sheets 2S2A) 35 T1.8-2 (sheets 364) 6 T1o8-2 34 (sheets SSSA) is.A 'T 1. 8 -2
' L, 1(sheets 666A) 37 T1.8-2 (sheet 7) 25 T1.8-3 (W) (sheets 1,1A) 21 T1.8-3 (W) 8 (sheets 2 thru 7)
T1.8-3 (W-3S) 28 (sheets 1, 2, 2A)
T1. 8-3 (W-3S) 20 (sheet 3)
T1.8-3 (W-3S) 28 (sheets 4 thru 8)
T1.8-3 (BSW) (sheet 1) 29 T1.8-3 (B&W) 33 (sheets 2 ttc 5) 1-b WOOfi7 Amenament 38 5/31/78
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SWESSAR-P1 CHAPTER 1 INTRODUCI' ION AND GENERAL DESCRIPTION OF PLANT
1.1 INTRODUCTION
By application filed herewith, the Stone & Webster Engineering Corporation (SSW) , Boston, Massachusetts , seeks approvals for the reference design of structures and systems within the SSW scope of design responsibiliy and those modifications to the Nuclear Steam Supply System (NSSS) Vendors Standard Safety Analysis Reports as described in this Reference Safety Analysis Report (SWESSAR-P1) . This application is tendered in accordance with the Atomic Energy Act of 1954 as amended and the regulations of the Nuclear Regulatory Commission (NRC) set forth in Title 10, Part 50, of the Code of Federal Regulations (10CFR50) as amended, and is filed under Appendix 0 to 10CFR50, " Standardization of Design; Staff Review of Standard Designs."
This application indicates a station with two identical plants as shown in the artist's conception in Fig. 1.1-1; however, it is intended to support a design approval for a single plant. This design approval would then support a license application for any number of plants in either single or multiple layouts with the NRC approval contingent upo n the use of the design herein in conjunction with SSW engineering activities.
17 SSW provides engineering, design, and construction services to support an int egrated nuclear power plant design for the electric utility industry. Typically, a utility is the applicant and SSW acts as the applicant's agent to coordinate the various systems comprising the plant to the end that equipment furnished by all vendors, including the NSSS Vendor, functions together in an integrated manner. In this application SSW is the applicant, but in all other respects functions in the customary manner of providing a complete plant design, including the responsibility for integra ;ing all systems and structures. Although a complete plant design is provided in SNESSAR, the NSSS Vendor retains sole responsibility for those systems and components within his scope of design.
SWESSAR-P1 is a licensing document and provides an accurate description of the plant, but its scope is limited to that information necessary for the NRC to perform its statutory review to ensure the health and safety of the public. Any nuclear plant which references SNESSAR-P1 in its license application will be built from engineering specifications and detailed drawings prepared by SSW and the equipment vendors.
This application describes the reference design for nuclear power plants which contain the pressurized water reactor (PWR) of the NSSS Vendors set forth herein. The design includes the NSSS design, independently furnished by the NSSS Vendor, which is 1.1-1 Amendment 17
%C@p 9/30/75
SWESSAR-P1 integrated with SSW structures and systems for the balance of plant (BOP). To the extent detailed in the body of this report, the NSSS SARs enumerated in Section 1.6 are incorporated in SWESSAR-P1 by reference. S&W effort is based on standardizing the design of structures and BOP systems to the maximum extent feasible, consistent with interfacing with several NSSS Vendors.
The common portion of this plant design is described on white pages in this application. In those areas where the design must differ to interface with a particular NSSS, colored pages are used as indicated in the Foreword.
The interfaces between SSW systems and NSSS systems are specifically identified. In some cases the interfaces identified by the NSSS Vendor have been modified to increase the extent of commonality of structures and BOP systems or to provide an U optimized overall plant design. Also identified are those interface requirements imposed on the Utility-Applicant (U-A) .
Interfaces are further described in Section 1.8.
This report describes a plant independent of a particular site.
Site related design criteria have been enveloped to accommodate the majority of sites within the continental United States.
Review of the approved plant design will be unnecessary at the construction permit stage if the particular site selected by the U-A falls within the envelope of site siteria established in Chapter 2 of this report.
The U-A will incorporate SWESSAR-1-1 by reference in Section 1.6.
The U-A will identify the selected NSSS Vendor but need not reference the NSSS Vendor's ShR since this is already incorporated by reference in SWESSAR-Pl. The U-A SAR will provide the information indicated in Table 1.8-2 to complete the requirements for an entire SAR.
The SWESSAR design power levels applicable to this report are given in Table 1.1-1. The plant design licensed core power level is in accordance with Regulatory Guide 1.49 (Section 3A.1-1.49) .
Performance analyses of engineered safety features systems are provided in Chapter 6 and are performed at values based on input from the NSSS Vendors. Those analyses performed at 4,100 MWt have been investigated to assure that they are conservative for plant operation at a licensed core power level of 3,800 MWt. All analyses of the performance of the engineered features systems in Chapter 6 will be performed at power levels in accordance with Regulatory Guide 1.49 in the Final Design Application unless a higher power level is permitted at that time. The analysis of possible offsite radiological consequences given in Section 15.1 are evaluated at a core power level consistent with position C.3 of Regulatory Guide 1.49.
Licensing at a higher power level capability will only be requested if, in the future, the Commission revises its position given in Regulatory Guide 1.49 (Section 3A.1-1.49) . When and if 1.1-2 UG006I Amendment 17 9/30/75
SWESSAR-P1 this higher power level is requested, the design will be fully analyzed at the higher power level and submitted for evaluation by the Commission.
This report has been prepared using the guidance contained in Regulatory Guide 1.70, " Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants," which is discussed in Section 3A.1-1.70. Much of the information provided within the report reflects the relatively long lead time associated with design and construction and is therefore preliminary, provisional, or limited especially where the operating phase is concerned. He'<ever, the Applicant recognizes this preliminary aspect and has based this report on the knowledge that continued coordination with the Nuclear Regulatory Commission will prevail, and that minor refinements will occur from time to time and will be documented in an appropriate manner.
With respect to the preliminary aspect of numbers, graphs, and drawings included within this report, it should be understood that normal tolerance permitted by good engineering practice is intended. Where operating parameters are especially important, such items are included in the technical specifications.
1.1-3 Amendment 17 9/30/75 6t20069-
SWESSAR-P1 TABLE 1.1-1 WSSSAR DESIGN POWER LEVELS BSW C-E W-41 W-3S sated core power (MWt) 3,800 3,800 3,800 3,411 (Licensed output)
NSSS output (MWt) 3,820 1,817 3,817 3,425 ESF design core power PGtt) 3,876 4,100 4,100 3,565 35 Radiological analysis core power (MWt) 3,87 6 4,100 4,100 3,636 Electrical output (MWe) ( 1 ) 1,34 1 1,324 1,325 1,180 (1) Heat balance for rated power (Fig . 10.1-2) 1 of 1 Ame21dment 35 10 / 6/ 7 7
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SWESSAR-P1 1.2 GENERAL PLANT DESCRIPTION 1.2.1 General The PWR Reference Nuclear Power Plant includes a nuclear steam supply system (NSSS) , turbine generator, and auxiliaries. Common facilities for two plants include:
Service building Administration building Auxiliary ' oiler building Portions of auxiliary steam and condensate system (Section 10.4.12)
Water treating facilities Fire protection system (Section 9. 5.1)
Hydrogen recombiners in combustible gas control system (Section 6.2.5)
The general arrangement of two plants is shown in the plot plan, Fig. 1.2-1. If a single plant is built, all the s tructures and systems mentioned above are provided for that plant.
The following subsections briefly describe the plant. Detailed discussion for each system can be found in its respective section of this SAR as noted in the table of contents.
In addition to the basic plant design, two major options are available to the Utility-Applicant. Option A employs a metal siding secondary enclos ure structure. b' hen combined with the annulus building, complete secondary enclosure of the containme?nt 18 is provided. Option B is similar to Option A with the addition of an air mixing system. These options are described in Appendixes A and B, respectively.
1.2.2 Site Information on specific site characteristics will be provided by the Utility-Applicant when an applica tion for a construction permit is filed.
The site related design parameters used for the design of this plant are given in Chapter 2. The ventilation, uir conditioning, and heating systems affected by outdoor conditions will be optimized for specific sites.
1.2.3 Structures The plot plan, Fig. 1.2-1, shows the general arrangement of structures for a two plant station. The major building areas are the containment-annulus building complex, control building, diesel generator building, fuel building, solid waste and decontamination building, and.tLa turbine building.
1.2-1 Amendment 18
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SWESSAR-I-The plant structures are depicted in the following figures:
Normal Switchgear Building Fig. 1.2-2 Containment Structure Fig. 1.2-3 Annulus Building Fig. 1.2-4 Control Building Fig. 1.2-5 Diesel Generator building Fig. 1.2-6 Turbine Building Pig. 1.2-7 Fuel Building Fig. 1.2-8 Solid Waste and Decontamination Building Fig. 1.2-9 Personnel access is shown in Fig. 1.2-10. These figures identify major access corridors and also aid design to ensure that no piping, cables, or equipment will be installed in these corridors.
The containment-annulus building complex is supported on a single reinforced concrete foundation mat. The annulus building contains the engineered safety features equipment, the new and spent fuel storage facilities, auxiliary systems, Seismic Category I water storage tanks, the radioactive liquid and gaseous waste systems, and other equipment.
The containment structure is a steel lined, heavily reintorced concrete structure with a vertical cylindrical wall, he'nispherical dome, and flat base.
Information on the plant structures is given in Section 3.8. h Seismic Category I plant structures, including their foundations, are designed for 0.3g seismic ground acceleration or less and a range of subgrade characteristics as given in Sections 3.7 and 3.8. However, this design may be modified to suit the safe shutdown earthquake and subgrade conditions presented in the Utility-Applicant's SAR. The same structural design methods and criteria presented in Sections 3.7 and 3.8 will be used. The structural arrangaaent above the foundation will not be altered in any case.
To accommodate the wide variety of acceptable site conditions, the top of the nuclear island foundation mat has two alternative elevations. The first is typically 51 feet below finished ground grade as shown in Fig. 1.2-1, and the second is one floor spacing approximately 25 feet higher. The functional building arrangement and analysis of Seismic Category I structurer are independent of foundation elevation.
g Information on the enclosure building (Options A and B) is given in Appendixes A and B, Sections A3.8.4 and B3.8.4, respectively.
9 1.2-2 Amendment 18 6bCl, , 10/30/75
SWESSAR-P1 1.2.4 Nuclear Steam Supply System The nuclear steam supply system (NSSS) utilizes a pressurized water reactor (PWR) consisting of a reactor coolant system (RCS) ,
steam generators, chemical and volune control system, and an emergency core cooling system. The NSSS is provided by Babcock & Wilcox Company (BSW), Ccxnbustion Engineering, Inc.
(F - E) , or Westinghouse Electric Corporation Gd) for a specific site locaticn. Each NSSS is described in a specific standard SAR as noted in Table 1.6-1. This table also indicates the effective date of the standard SAR used to develop the interface information in SWESSAR-Pl.
1.2.5 Instrumentation _and Control Fystems The instrumentation and control for the reactor protection system, engineered safety features actuation system, and other safety related systems, supplied by the NSSS Vendor or SSW neet the requirements of IEEE 279-1971, aCriteria for Nuclear 1.2-2A h.g] };p Amendment 18 10/30/75
SWESSAR-P1 Power Plant Protection Systems." In addition, other applicable criteria are met as described in Chapters 3 and 7.
The nonsafety related instrumentation and controls accomplish reliable control and allow continuous monitoring of the plant status without degradation of saf ety related instrumentation.
Design details are described in Chapter 7.
The application of instrumentation and controls to individual systems is also provided in each section describing an individual system.
1.2.6 Reactor and Plant Controls The reactor is controlled by a coordinated combination of chemical shims and mechanical control rods. The control system allows the plant to accept step and ramp load changes as specified by the NSSS Vendor.
Control of both the reactor and the turbine genera tor is accomplished from the control room, which contains all instrumentation and control equipment required for startup, operation, and shutdown, including both normal and accident conditions. The NSSS controls provide for automatic load programming from a central dispatch system. However, the design permits complete manual operation of the NSSS.
1.2.7 Radioactive Waste Systems The disposal of radioactive wastes from the site is managed by waste systens designed to meet all applicable regulatory requirements, including 10CFR20, 10 CFR50, General Design Criterion 60, and Regulatory Guide 1.21. These systens are described in Chapter 11.
There are three interrelated radioactive waste treatment systems:
radioactive liquid waste, radioactive gaseous waste, and radioactive solid waste.
The radioactive liquid waste system collects, classifies, and processes radioactive waste liquids generated during plant operation and re fueling , either for recycle within the plant or for discharge offsite. The process operations available to treac the liquid wastes are filtration, evaporation, and demineralization . The process descriptions and flow charts illustrate the number and sequence of processing steps to be applied to each type of liquid waste (Section 11.2) .
Radioactive gaseous wastes, consisting of gaseous (hydrogenated) vents and aerated vents containing various levels of radioactivity, are treated before release to the environment.
Continuous degasification and purification of the reactor coolant O letdown minimizes the consequence of any reactor coolant leakage.
This degasification and purification process produces gaseous 1.2-3 Amendment 9 OOOON 4/30/75
SWESSAR-P1 streams, which are passed through charcoal decay beds to provide holdup time for the decay of noble gases. Provisions are made for recycling the decayed gas back to the reactor coolant system.
Aerated streams, produced by other phases of plant operation, are passed through carbon adsorbers for iodine removal. Th*s system is described in Section 11.3.
The radioactive solid waste system provides holdup, packaging, and storage facilities for the eventual offsite shipment and ultimate disposal of solid radioactive waste material. Available process operations are solidification of liquid wastes, holdup for decay, dilution with inert material, and baling for volume reduction. Shielding as required during the processing and shipment of the solid wastes is inclnded in the planned operation of the solid waste system. A process flow chart illustrates the processing and handling sequences for the solid wastes generated on the site (Section 11. 5) .
1.2.8 Fuel Handling The reactor is refueled using standard equipment that handles spent fuel under water from the time it leaves the reactor vessel until it is placed in a shipping cask for removal frcxn the site.
Underwater transfer of spent fuel provides an optically transparent radiation snield, as well as a reliable coolant for removal of decay heat.
The fuel handling system is located in the containment and fuel building. The refueling cavity and canal is located in the containment structure and is flooded only for refueling. The g fuel pool is flooded whenever spent fuel is in the pool. The containment and fuel building are connected by a fuel transfer system that carries the fuel through a transfer tube penetrating the containment structure and by a personnel hatch to be used by refueling personnel.
Handling and storage of both new and spent fuel assemblies are accomplished with equipment and procedures which ensure that all fuel arrays are maintained suberitical.
1.2.9 Turbine and Turbine Auxiliaries The turbine is a tandem-compound, six-flow, 1,800 rpm unit. Two ccxnbination noisture separator-reheaters dry and superheat the steam between the high and low pressure sections of the turbine.
The turbine building and the steam and power conversion system designs presented in SWESSAR are based on detailed design information for General Electric Company and Westinghouse g Electric Corporation turbine-generators compatible with the reference plant power level. Other turbine-generator manufacturers can be acccxnmodated by making building and system modifications in areas related to the specific turbine-oenerator.
1.2-4 Amendment 9 (360C% 4/30/75
SWESSAR-P1 Additional major components are a deaerating surface condenser, two full capacity steam jet air e je ctors , three half-capacity condensate pumps, three third-capacity feedwater pumps, two or three motor-driven auxiliary feedwater pumps, one turbine-driven auxiliary feedwater pump, and three parallel flow paths of feedwater heating, each having six or seven stages. 3 The system provides load following capability as specified by the turbine manufacturer 's recommended loading rates. Turbine bypass and atmospheric steam dump capacity permit 50 percent load 3
rejections without reactor or turbine trip.
1.2.10 Electrical Systems The main generator for the unit is an 1,800 rpm, 3 phase, 60 cycle, hydrogen inner-cooled unit. Main step-up trans formers deliver power to the high voltage switchyard.
The station service system consists of auxiliary transformers, 13,800, 4,160, and 480 V switchgear and buses, 480 V motor control centers, 120 V a-c vital buses, and 125 V d-c batteries and equipment. The normal source of station service power is the main generator; however, a preferred reserve source is available from the high voltage transmission system. This system is shown in Fig. 8.3-1.
In the event of complete loss of the preferred reserve source, emergency power is supplied by onsite diesel engine driven generators. Each diesel generator set is capable of supplying power for engineered safety features and other safety related equipment that must be operated in the event of a loss-of-coolant accident and/or a loss of preferred reserve station power sources.
1.2.11 Engineered Safety Features Engineered safety features are provided to reduce the potential radiation dose to the general public from a design basis accident (DBA) to below the guideline values of 10CFR100. The potential dose is reduced by immediatq, automatic isolation of all containment fluid penetrations that are not required for limiting the consequences of the accident, thereby eliminating potential leakage paths. Long-term potential releases following the accident are reduced by returning the containment to a low pressure within one day, thereby reducing the driving potential for fission product escape. Long-term buildup of hydrogen in the containment atmosphere is prevented by operation of a combustible gas control system.
In addition, the engineered safety features cool the core, maintaining it in a coolable geometry during any postulated loss-of-coolant accident (LOCA). This is accomplished by the emergency core cooling system which is immediately available.
This system, coupled with the thermal, hydraulic, and blowdown 1.2-5 ,WM {l[ Amendment 9 4/30/75
SWESSAR-P1 characteristics of the reactor, prevents excessive metal-water reactions or changes in core geometry that could prevent further cooling and cause core melting.
Equipment for the engineered safety features of the plant is as follows:
- 1. The high head safety injection pumps inject cooling water into the core. This is a high pressure, low capac2.ty system used for small and large break.s in the RCS.
- 2. The accumulators inject cooling water into the reactor pressure vessel (RPV) when the RPV pressure falls below a predetermined value. No external signal or power source is required for operation.
- 3. The low head satety injection pumps inject cooling water into the core. This is a low pressure, high capacity system used for large and small breaks in the RCS.
- 4. The safety injection system (RESAR-3 S only) is an intermediate pressure, high capacity system to inject cooling water into the Cere.
17 5. The emergency boration system (RESAR-41 only) provides negative reactivity insertion to the reactor core after a steam line break.
- 6. The RHR heat exchangers provide long term cooling to the reactor core after a LOCA or a steam line break accident.
Items 1 through 6 above are part of the NSSS Vendor's scope and SAR.
- 7. The containment spray pumps discharge a boric acid sodium hydroxide solution through spray headers into the containment atmosphere for removal of heat and iodine.
- 8. The containment atmosphere recirculation system cools the containment atmosphere directly and promotes atmosphere mixing during accident conditions. During normal operation, this system controls the containment atmosphere temperature.
- 9. The containment isolation system isolates the containment at all fluid penetrations except those required by the engineered safety features systems.
- 10. The containment combustible gas control system consists of redundant hydrogen recombiners that take suction from the containment atmosphere and discharge back into the 1.2-6 b C 3 2. Amendment 17 9/30/75
SWESSAR-P1 containment atmosphere. In addition, the backup containment dilution air subsystem can be actuated manually after the accident to control hydrogen buildup.
1.2.12 Other Auxiliary Systems Safety related auxiliary systems are described below:
- 1. The reactor plant service water systent transfers heat from the reactor plant component cooling water system and other safety related systems to the ultiIr:tte heat sink. This system is normally operating and is required
- 1. 2 -6 A Amendment 17 bGO. 2 73 9/30/75
SWESSAR-P1 at the time of the postulated accident to transfer the accident heat load to the ultimate heat sink.
- 2. The reactor plant component cooling water system is an intermediate cooling system provided to transfer heat from the reactor coolant and other potentially radioactive liquids to the reactor plant service water system. The reactor plant component cooling water system provides cooling water for systems und components required for a safe shutdown.
- 3. The diesel generator fuel oil system is designed to supply fuel oil fer seven days operation of each diesel generator at the time of an accident or loss of power condition.
4 Air-conditioning and ventilation systems for safety related areas control ambient air temperature and provide a suitable environment for personnel and equipment with protection against the spread of radioactive contamination. Areas subject to radioactive release have provisions for particulate and gaseous radiation monitoring, of the ventilation exhaust air.
- 5. The fuel pool cooling system removes residual and decay heat from the spent fuel.
- 6. The supplementary leak collection and release system (SLCRS) is designed to minimize the release of airborne ra dioactive contaminants from the containment structure ;7 following a loss of coolant accident (:LOCA) and from the fuel building following a fuel handling accident.
Auxiliary systems which are not safety related are described below:
- 1. The boron recovery system stores and processes borated radioactive water from the reactor coolant system. The process uses evaporators, filters, and demineralizers to produce primary grade water and concentrated boric acid solution for plant reuse or disposal.
- 2. The vent and drain system collects fluids from various systems and transfers the.a to either the boron recovery system or the appropriata waste system.
- 3. The compressed air systems supply service and instrument air required f or normal operation.
- 4. The fire protection system has the capacity to extinguish any probable fires that might occur at the plant. This system includes a water system, a low pressure CO2 system, and. portable fire extinguishers.
1.2-7 Amendment 17 bukh 9/30/75
SWESSAR-P1
- 5. The fuel pool purification system purifies the water in the fuel pool, the reactor cavity, and the refueling water storage tank.
- 6. The sampling system collects representative liquid and gaseous samples at the sampling sinks for laboratory analysis.
O O
1.2-8 Amendment 17 op e but v70 9/30/75
SWESSAR-P1 Table 1 2-1 is deleted. gg 9
Amendment 18 LuCO% 10/30/75
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