ML20036A063
| ML20036A063 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 04/28/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9305070354 | |
| Download: ML20036A063 (4) | |
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GE Nuclear Encrgy vu n c cnwr (A 9:12 US ru vimue %n a o
April 28,1993 Docket No. STN 52-001 Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated ABWR Review Schedule - DFSER Open Item 1.2.6-1
Dear Chet:
Enclosed is a SSAR markup addressing DFSER Open Item 1.2.6-1.
Please provide a copy of this transmittal to Jerry Wilson.
Sincerely, cy ack Fox Advanced Reactor Programs cc: Norman Fletcher (DOE)
Bernie Genetti(GE))
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1.1 INTRODUCTION
1.1.4 Type of License Required 1.1.1 Format and Content This ABWR SSAR is submitted in support of the application for final design approval (FDA)
The Advanced Boiling Water Reactor Standard and design certification (DC) for the ABWR Safety Analysis Report (ABWR SSAR),is written in Standard Plant.
accordance with Regulatory Guide 1.70. For consistency with NUREG-0800, the ABWR SSAR 1.1.5 Number of Plant Units includes Section 15.8 which addresses anticipated transients without scram and Chapter 18 which For the purpose of this document, only a addresses human factors. In addition, response to single standard plant will be considered.
TM1 related matters is presented in Appendix 1A.
1.1.6 Description of Location The response to severe accident policy statement is provided in Chapter 19. Chapter 20 is This plant can be constructed at any location included to provide a question and response guide.
which meets the parameters identified in Chapter-2.
1.1.2 ABWR Standard Plant Scope 1.1.7 Type of Nuclear Steam Supply The ABWR Standard Plant includes all buildings which are dedicated exclusively or primarily This plant will have a boiling water reactor.
to housing systems and the equipment related to the nuclear steam supply system designed and suppli'ed nuclear system or controls access to this equipment by GE and designated as ABWR.
and systems. There are five such buildings within the scope of the ABWR Standard Plant. These are:
1.1.8 Type of Containment (1) Reactor building (including containment);
The ABWR will have a low-leakage containment vessel which comprises the drywell and pressure (2) Service building; suppression chamber. The containment vessel is a cylindrical steel lined reinforced concrete structure (3) Controlbuilding; integrated with the reactor building. The containment nomenclature is specified in Figure (4) Turbine building; and 1.1-1.
(5) Radwaste building.
1.1.9 Core Thermal Power I2vels The information presented in this ABWR SSAR.
pertains to one reactor unit with a rated power level of 3926 MWt and a design power level of -
In addition to these buildings and their 4005MWt. The station utilizes a single cycle, contents, the ABWR Standard Plant provides the forced-circulation, boiling water reactor (BWR).
OPgg
. supporting facilities shown in Figure l.2-1.-
The heat balance for rated power is shown 'in
- g y* g.7 f#ff R T I. / + 2 Figure 1.1-2. The station is designed to operate at 1.1.3 Engineering Documentation a gross electrical power output of approximately _
1356 MWe and net electrical power output of Engineering documentation for the ABWR
~
approximately 1300 h6Ve.
Standard Plant is listed on Master Parts List (MPL)
No.18NS07A03', This MPL is a controlled list, structured by system, that contains the identification of hardware and software documentation that -
defines the ABWR Standard Plant.
' GE Proprietary Arnendment 9 l31
CPfA) 12.6-1 pg g o f,5 9
Insert 1.1.2 The ABWR evolutionary design provides an essentially complete nuclear power plant except for site-specific elements.
The site-specific elements are included as representative conceptual designs with interface requirements sufficient for the final safety analysis and design-specific probablistic risk assessment in accordance with 10 CFR IStX 52.47 (a) (1) (vii) and (b) (1).
These are:
(1) Ultimate heat sink (2) Offsite power (transmission)
(3) Make up water (preparation)
(4) Potable and sanitary water (5) Reactor service water (6) Turbine service water (7) Lighting and servicing power supply (8) Communications (9) Site security
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REACTOR CONTAINMEN T E
2 REACTOR BUILDING 3
CONTROL BUILDING 4
MA'N STEAMSEEDWATER TUNNEL 8
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TURBINE BUILDING G
SERVICE BUILDING 5
7 RADWASTE BUILDING l
8 IlOUSE BOILER 9
CONDENSAlE STORAGE TANK 10 QfAINJRANSFOng BUNxcR [Lt GLTMK 11 NORMAL SWIICitGEAR 12 OIESEL OIL STORAGE TAN". (3) 11 13 STACK 9
14 EQUIPMENT ENTRY LOCK 15 FIRE PROTECilON WATER 7
STORAGE TANK (2) 3 4
3 6
16 FIRE PROTECTK)N PUMPilOUSE O
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