ML20059A625
| ML20059A625 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 10/22/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9310270011 | |
| Download: ML20059A625 (4) | |
Text
.i GENucle:rEn:rgy Genere![lectric Company 175 Cartner Avenae. San Jose. CA 9S 125 October 22,1993 Docket No.52-001 Chet Posiusny, 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 Schedule - DFSER Open items 1.2.61 and 2.6-1
Dear Chet:
Enclosed are SSAR markups responding to Open items 1.2.6-1 and 2.6-1. Pages 1.1-2 and 3.2-10 replace the markup of Page 3.2-10 of my October 6,1993 letter.
It is my understanding that the tornado missile spectra portion of Open Item 2.6-1 is no longer an issue, therefore, attached Page 2.1-3/4 should close this item.
Please provide a copy of this transmittal to Jerry Wilson.
Sincerely, u b 'fD Jack Fox Advanced Reactor Programs ec:
Alan Beard (GE)
Norman Fletcher (DOE)
Bernie Genetti (GE) 060 I
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23A6100 Gev.2 ABWR studedsareryAurysis aeron (2) Offsite power (8.2.4), transmission (The offsite power transmission network is out of scope starting from the low voltage terminals of the main and resene transformers, reference conceptual design is provided.)
(3) Makeup water (9.2.8), preparation (well and treatment facilities, conceptual) t (4) Potable and sanitary water systems (9.2.4), partial (Portions inside the l
buildings of Figure 1.2-1 are in scope. All other portions are conceptual and outside scope of the standard ABWR design.)
(5) Reactor senice water (9.2.15), rejects heat to the ultimate he.t sink, pardal (Portions inside the buildings of Figure 1.2-1 are in scope. All other portions are conceptual [ pumps, valves, pipes, strainers and other equipment (Figure 9.2-7)] and are outside the scope of the standard ABWR design.)
(6) Turbine service water (9.2.16), rejects heat to the power cycle heat sink, partial (Portions inside the buildings of Figure 1.2-1 are in scope. All other portions are conceptual [ pumps, valves, pipes, strainers and other equipment (Figure-9.2-8)] and are outside the scope of the standard ABWR design.)
i (7) Communications (9.5.2), partial (Communication equipment inside the buildings of Figure 1.2-1 are in scope. All other portions, including connections to offsite networks are outside the scope of the standard ABWR design.)
6 (8) Site security (13.6.2)
(9) Circulating water system (10.4.5), circulates water (Portions inside the buildings of Figure 1,2-1 are in scope. All other portions are conceptual J
(pumps, valves, pipes, strainers and other equipment (Figure 10.4-3)) and are outside the scope of the endard ABWR design. %is system includes the power cycle heat sink which p. ovides a heat sink for the Circulating Water and Turbine Senice Water Systern xooling tower with makeup water and
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chemical control, conceptun l
(10) Heating, ventilating and air conditioning (9.4), partial (Invohing potential need for toxic gas monitors).
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1.1.3 Engineering Documentation Engineering documentation for the ABWR Standard Plant is listed on Master Parts List or I.LS-t (MPL) No.18NS07A03*. This MPL is a controlled list, structured by system, which A cQ m {e,d h 3
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- GE Proprietary 1.12 Introduction - Amendment 32
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ABWR StandardSafety Analysis Report Table 3.2-1 Classification Summary The classification information is presented by System' in the following order:
ltem No.
MPL Number Title t
B Nuclear Boiler Supply System B1 B11 Reactor Pressure Vessel System' B2 B21 Nuclear Boiler System' B3 B31 Reactor Recirculation System C Control and instrument Systems C1 C11 Rod Control and information System C2 C12 Control Rod Drive System C3 C31 Feedwater Control System C4 C41 Standby Liquid Control System C5 C51 Neutron Monitoring System' C6 C61 Remote Shutdown System C7 C71 Reactor Protection System' C8 C81 Recirculation Flow Control System C9 C82 Automatic Power Regulator System C10 C85 Steam Bypass and Pressure Control System C11 C91 Process Computer (includes PMCS and PGCS)
C12 C93 Refueling Platform Control Computer C13 C94 CRD Removal Machine Control Computer D Radiation Monitoring Systems D1
,D11 Process Radiation Monitoring System' D2
.D21 Area Radiation Monitoring System D3 UU23 Containment Atmospheric Monitoring System' (Ty ta \\ c,b wp b p w gr 3 2-t o 4km 3.7 g
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t Master Parts List Number designated for the system.
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- These systems or subsystems thereof, heve a primary function that is safety-related. As
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shown in the balance of this Table, some of these systems contain non-safety-related components and, conversely, some systems whose primary functions are non-safety-2 *f k related contain components that have been designated safety-related.
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.\\-k A 6 w9. 54 own A n E Qg;,;(,* tion of Structures. Components, and 5ystems - Amendment 31 3 g.3g
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F0x-23A6100 Rev. 2 AtWR standard setory Analysis a: port
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Table 2.1-1 Limits imposed on SRP Section ll Acceptance Criteria by
' ABWR Design (Continued)
SRP Section Subject Limits -
2.4.5 Probable Maximum Surge and Probable maximum surge and seiche flooding Seiche Flooding level 30.5 cm below grade.
2.4.6 Probable Maximum Tsunami Probable maximum tsunami flooding level 30.5 cm below grade.
2.4.7 ice Effects None.
2.4.8 Cooling Water Channels and None.
Reservoirs 2.4.9 Channel Diversion None.
t 2.4.10 Flooding Protection Requirements None.
2.4.11 Cooling Water Supply None.
2.4.12 Groundwater Per Table 2.0-1.
2.4.13 Accidental Releases of Liquid None.
j Effluents in Ground and Surface Waters t
2.4.14 Technical Specifications and None.
Emergency Operation Requirement Geology, Seismology and Geotechnical Engineering 2.5.1 Basic Geology and Seismic None.
Information 4
oz 2.5.2 Vibratory Ground Motion Per Table 2.0-1. k OV'a cca e *d-),
EE" g,C.g Na CdM o-i 2.5.3 Surface Faulting b+4eae.3w a s3 4
2.5.4 Stability of Subsurface Materials and Per Table 2.0-1.
Foundations 2.5.5 Stability of Slopes None.
i 2J 3'd Limits imposed on SRP Section 11 Acceptance Criteria by ABWR Standard Plant - Amendment 32
. - -