ML20070Q557
| ML20070Q557 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/31/1989 |
| From: | Lobner P SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY |
| To: | NRC |
| References | |
| CON-FIN-D-1763, CON-NRC-03-87-029, CON-NRC-3-87-29 SAIC-89-1007, NUDOCS 9103290119 | |
| Download: ML20070Q557 (123) | |
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l GRAND GULF 1 50 416 lo Editor: Peter Lobner Author: Peter Lobner Prepared for:
U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Contract NRC 03 87 029 FIN D 1763 O
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Grand Gulf I l TABLE OF CONTENTS 4
i Section hgs i 1 S U MMAR Y D ATA ON PLANT. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2 IDENTIFICATION OF SIMILAR NUCLEAR POWER PLANTS .... 1 q 3 S YSTEM INFORM ATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
- 3.1 Reactor Coolant S ystem (RCS) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 i-3.2 Reactor Core Isolation Cooling (RCIC) System............. .
13
- 3.3 Emergency Core Cooling System (ECCS) ................... 18 i 3.4 Instrumentation and Control (!&C) Systems ................. 35 3.5 Elec tric Power System . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , 40
} 3.6 Control Rod Drive Hydraulle System (CRDHS) ............ 63 e
3.7 Shutdown Service Water System (SSWS) ................... 66 1
4 PLANT INFORM ATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .75 . I i
1-4.I Site and B uildin g S ummary . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ' 75
, 4.2 Facility Layou t Dra wing s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 75 i
$ $ B IB LIOG RAPHY FOR G RAND GULF . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 105-1 J -
APPENDIX A, Definition of Symbols Used in the System and l
t Layou t Drawings . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106 jl -
l APPENDIX B. Definition of Terms Used in the Data Tables ........... I13 e
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Grand Gulf I l
LIST OF FIGURES Figure
- ha 31 Cooling Water Systems Functional Diagram for Grand Gulf 1........... 7 1
3.1 1 Grand Gulf 1 Reactor Coolant System .. . . . .. . . .. . .. .. . . . ... . .. .... .. .... . .. 10 3 1
3.1 2 Grand Gulf 1 Reactor Coolant System Showing Component 1 Loc a ti on s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1. 1. . . . . . . . . . . . .
3.2 1 Grand Gulf 1 Reactor Core isolation Cooling System..................... 15 i
3,2 2 Grand Gulf 1 Reactor Core isolation Cooling System Showing Component Locations.......................................................... I6 3.3 1 Grand Gulf 1 liigh Pressure Core Spray System........ ............... 22 3.3 2 Grand Gulf I High Pressure Core Spray System Shov g Component i
loc a ti on s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23
, 3.33 Grand Gulf 1 Low Pressure Core Spray System........................... 24 3.3 4 Grand Gulf 1 Low Pressure Core Spray System Showing Component IACations........................................................................ 2$
!, 3.3 5 Grand Gulf 1 Residual Heat Removal System, Loop A................... 26 1 3.3 6 Grand Gulf 1 Residual Heat Removal System. Loop A Showing '
! Componen L o c a t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . 27 i
3.3 7 Grand Gulf 1 Residual Heat Removal System. Loop B................... 28 3.3 8 Grand Gulf 1 Residual Heat Removal System. Ieop B Showing Component Locations......................................................... 29 3.3 9 Grand Gulf 1 Low Pressure Injection System loop C...................._ 30 3.3 10 Grand Gulf 1 Low Pressure Injection System loop C Showing -
Component L o c a t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 31 3.5 1 Grand Gulf 14160 VAC Electric Power Distribution System............ 43 3.5 2 Grand Gulf 14160 VAC Electric Power Distribution System Showing Component Locations.......................................................... 44 3.5 3 Grand Gulf 1480 VAC Train A Electric Power Distribution System.... 45 3.5 4 Grand Gulf 1480 VAC Train A Electric Power Distribution System S howin g Compone n t Location s . . . . . . . . _ . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 46 f -3.5 5 Grand Gulf 1480 VAC Trains B and C Electric Power Distribution t System..........................................................=.................a47 ii ' 1/89 .
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Grand Gulf I LIST OF FIGURES (continued)
Eintre hu 3.5 6 Grand Gulf 1480 VAC Trains B and C Electric Power Distribution S ys te m S howin g Compon en t Loca tion s .................................... 48 3.5 7 Grand Gulf 1 125 VDC Electric Power Distribution System ............. 49 3.5 8 Grand Gulf 1 125 VDC Electric Power Distribution System Showing Component Locations.......................................................... 52 3.5 9 Grand Gulf 1 120 VAC Uninterruptible Electric Power Distribution System........................................................................... 55 3.6 1 Simplified Diagram of Portions of the Control Rod Drive liydraulic System That Are Related to the Scram Function............................ 65 3.7 1 Grand Gulf I Shutdown Service Water System, Train A ................. 68 3.7 2 Grand Gulf 1 Shutdown Service Water System, Train A Showing Component Loeattons......................................................... !
69 3.7 3 Grand Gulf 1 Shutdown Service Water System, Train B ................. 70 3,7 4 s
Grand Gulf 1 Shutdown Service Water System, Train B Showing Component Locatlons.......................................................... 71 3.75 Grand Gulf 1 Shutdown Service Water System, Train C................, 72 3.7 6 Grand Gulf 1 Shutdown Service Water System, Train C Showing !
Component Locations.......................................................... 73 !
41 General View of the Grand Gulf Site and Vicinity........................ 76 42 G ra nd G ul f Simpli fied Si te Plan............................................. 77 i 43 Elevation View of Grand Gulf Reactor and Tu (lookin g S outh) . . . . . . . . . . . . . . . . . ............................
. . . . . . . . . . . . . . . . . . .rbine B uildin gs 78 44 Elevation View of Grand Gulf Reactor and Contml Buildings (l ooki n g We s t) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .79 45 Elevation View of Grand Gulf Turbine Building (looking East) ........ 80 4-6 Grand Gulf 1 Reactor Building (Elevation 93'0" to 100'9") and Con trol B uildin g (Elevation 93'9") . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .81 ..
47 Grand Gulf 1 Reactor Buildin;; (Elevation 114'6" to 120'10") and Control B uilding (Eleyation 1 1 l '0") . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .82 ..
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Grand Gulf 1 i
LIST OF FIGURES (continued)
Figure Eagt 48 Elevation 139'2" to 147'7").
Grand Gulf (Elevation Control Building 1 Reactor 133' Building (0"), and Diesel Generator Building (Eleyatlon 133'0")............................................................. 83 49 Grand Gulf 1 Reactor Building (Elevation 139'2" to 147'7"). . .
Control Building (Elevation le 8'0"), and Diesel Generator Building (Eleyatton 1$8'0")............................................................. 84 ,
4-10 Grand Gulf 1 Reactor Building (Elevation 116'0") and Contml Building (Elevation 166'0"), and Diesel Generator Building (Eleyatton 166'0")............................................................. 85 4 11 Grand Gulf 1 Reactor Building (Elevation 117'0") and Control #
Building (Elevation 177'0'), and Diesel Generator Building (Elevat10n 172'0")............................................................. 86 4 12 Grand Gulf 1 Reactor Building (Elevation 184'6" to 189'0") and Control B uilding (Elevation 189'0") . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 87 4 13 Grand Gulf 1 Reactor Building (Elevation 208'10")...................... 88 4 14 Elevation View of Grand Gulf I Diesel Building (looking East) ........ 89
. 4 15 Elevation View of Grand Gulf 1 Diesel Buildin Rooms A and B (looking South).................g, Typical of Diesel
........................... 90 4 16 Elevation View of Grand Gulf 1 Diesel Building, HPCS Diesel Room (l ookin g S ou t h ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 91 ........
4 17 Grand Gulf 1 Cooling Tower Basin (Typical of 2) ....................... 92 4 18 Elevation View of Grand Gulf I Coolin of 2) . . . . . . . . . . . . . . . . . . . . ....................................
. . . . . . . . . . . . . . . . . . . . .g To wer Pumphou 4 19 Grand Gulf 1 Service Water Cooling Tower Pumphouse A -
l (El e va tio n 13 3'0" a n d 15 8'0")............. .. .. . .. ... .. .. .. ..... .. . . . . . ..94 ... .
- 4 20 Grand Gulf 1 Service Water Cooling Tower Pumphouse B
( Ele y a t i on . 13 3 '0 " a n d 15 8 '0"). .. ... .. .. . .. ... . ... .. . .. . . .. .. . .. . . .. . .. . . ... . 95 A1 Key To Symbols in Fluid System Drawings ............................. 109 A2 Key To Symbols In Electrical System Drawings...............,.......... I11 A3 Key To Symbols in Facility Layout Drawings ............................ 112 iv- 1/89 I
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Grand Gulf 1 LIST OF TAllLES
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Figure hgg 31 Summary of Grand Gulf 1 Systems Covered in this Report............. 3 i 3.1 1 Grand Gulf 1 Reactor Coolant System Data Summary i
for Sel ec ted Compon en ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .12 3.2 1 Grand Gulf 1 Reactor Core isolation Cooling System Data S ummary for Seieeted Componenis......... ......................... 17 3.3 1 Grand Gulf 1 Emergency Core Cooling System Data S ummary for belected components . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 3.41 Matrix of Grand Gulf 1 Control Power Sources .......................... 39 3.5 1 Grand Gulf 1 Electric Power System Data Summary for S el ect ed Componen ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 56 3.5 2 Partial Listing of Electrical Sources and Loads at Grand Gulf........... 58 3.7 1 Grand Gulf 1 Shutdown Service Water System Data S ummary for S e1eeted Compone n ts......................................... 74 l
41 O Defm' ition of Grand Gulf I building and 1.ocation Codes................ 96 !
V 42 Partial Listing of Components by Location at Grand Gulf 1............. 99 i
B-1 Compon en t Type Code s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I14 C\ l
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Grand Gulf I CAUTION The information in this report has been developed over an extended period of time based on a site visit, the Final Safety Analysis Report, system and layout drawings, and other oublished information. To the best of our knowledge, it accurately ref ects the plant configuration at the time the information was obtained, however, the information in this document has not been independently verified by the licensee or the NRC, NOTICE This sourcebook will be periodically u xlated with new and/or replacement pages as appropriate to incorporate adc itional information on this reactor plant. Technical ermrs in this report should be brought to the attention of the following:
Mr. hiark Rubin U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Engineering and Systems Technology Mail stop 7E4 Washington, D.C. 20555 With copy to:
Mr. Peter Lobner Manager, Systems Engineering Division Science Applications International Corporation LO210 Campus Point Drive San Diego,CA 92131 (619)458 2673 Correction and other recommended changes should be submitted in the fonn of marked up copies of the affected text, tables or figures. Supporting doct. mentation should be included if possible, t i V
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O GRAND GULF 1 RECORD OF REVISIONS REVISION ISSUE C0hthlENTS 0 1/89 Original report O
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Grand Gulf 1 GRAND GULF SYSTEM SOURCEBOOK i
l This sourcebook contains summary information on the Grand Gulf Nuclear ;
Station. Summary data on this plant are presented in Section 1, and similar nuclear power plants are identified in Section 2. Information on selected reactor plant systems is presented in Section 3, and the site and building layout is illustrated in Section 4. A sibliography of re ports that describe features of this plant or site is presented in Section 5.
Symbols used in the system and layout drawings are defined in Appendix A. Terms used i in data tables are defined in Appendix B.
- 1.
SUMMARY
DATA ON PLANT Basic information on the Grand Gulf 1 nuclear power plant is listed below:
Docket number 50 416 Operator System Energy Resources, Inc.
(a subsidiary of Middle South 0, : ties)
Location Claiborne County, Mississippi j -
Commercial operation date July 1985 Reactor type BWR/6 NSSS vendor General Electric power (MWt/MWe) 3833/1290 i -
Architect engineer Bechtel Containment type Steel and reinforced concrete cylinder (Mark III) i 2. IDENTIFICATION OF SIMILAR NUCLEAR POWER PLANTS The Grand Gulf 1 plant contains a General Electric BWR 6 nuclear steam supply system with a Mark III containment incorporating the drywell/ pressure suppression concept. The plant also has a secondary contalnment structure of reinforced concrete.
- Other BWR 6 plants in the United States are as follows
1 Clinton 1 Perry 1 & 2
- River Bend 1 i
Grand Gulf 1 uses a high pressure core spray system, a reactor core isolation cooling system, a low pressure core spray system, and a multi-mode RHR system. The i
i reactor core isolation cooling and RHR systems include the capability. for steam condensing.
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Grand Gulf 1
- 3. SYSTEh! INFORhl ATION This section contains descriptio:ts of selected systems at Grand Gulf 1 in terms of general function, operation, system success criteria, major components, and support
( system requirements. A summary of major systems at Grand Gulf 1 is presented in Table
- 31. In the " Report Section" column of this table, a section reference (i.e. 3.1,3.2, etc.)is provided for all systems that are described in this report. An entry of "X" in this column means that the system is not described in this report. In the "FSAR Section Reference" column, a cross reference is provided to the section of the Final Safety Analysis Report where additionalinformation on each system can be found. Other sources ofinformation on this plant are identified in the bibliography in Section 5.
Several cooling water systems are identified in Table 31. The functional relationships that exist among cooling water systems required for safe shutdown are shown in Figure 31. Details on the indivicual coohng water systems are provided in the report sections identified in Table 31.
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i Table 3-1. Summary of Grand Gulf I Systems Covered in this Report Generic Plant-Specific Report System Name FSAR Sectum i System Name Section Hererence Reactor IIcat Removal Systems
- Reactor Coolant System (RCS) Same 3.1 5 i
lt
- . Reactor Core Isolation Cooling Same 3.2 5.4.6 (RCIC) Systems
- Emergency Core Cooling Systems Core Standby Cooling Sys: ems
'(ECCS) '
- IIigh-Pressure Injection IIigh-Pressure Core Spray 33
& Recirculation 63 (IIPCS) System i
- Low-pressure Injecuon low Pressure Core Spray (LPCS)
- & Recirculation 33 63 System w
Low-Pressure ( aolant 33 6.3 Injection (LPCI) System (an i operating rnode of *he RIIR sysem)
- Automatic Depressurization 'Same 33 System (ADS) 63 Decaylleat Removal (DIIR) ResidualIIcat Removal 33 System (ResidualIIcat Removal 5.4.7. 63 (RIIR) System (a muhi-mode (RilR) System) system) i
- Main Steam and Power Conversion Main and Reheat Steam System, X 5.4, 10 3 Systems Condensate and Feedwater System, X 5.4, 10.4.7 CirculatingWaterSystem X 10.4.5
- l. ,
! 1 Otherlleat Removal Systems . Steam <ondensing RIIR/RCIC 3.2 j 63 i operation 1
I.
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Table 3-1. Summary of Grand Gulf I Systems Covered in this Report (Continued) i
!-. Generic Plant-Specific Report FSAR Section j . Fvstem Name System Name Section Reference Renetor Coolant Inventory Contrel Systems
- Reactor Water Cleanup (RWCU) Same X 5.4.8 System l
- - ECCS- See Core Standby Cooling Systems - -
, above
- Control Rod Drive Hydraulic System (CRDHS) Same 3.6 4.6 '
Containment . Systems
- - Primary Containment Same (drywell and pressure - X 6.2 suppression chamber)
I- u. ;- Secondary Containment Same X 6.2
- Standby GasTreatment System (SGU) Same X 6.5.3 j - Containment Heat Removal Sy.;tems j - Suppression Pool Cooling System Same(an operating mode of the 3.3 6.2.2 2
' RHR system) ,
_ Containment Spray System Same(an operating mode of the 3.3 6.5.2 -
I RHR system) j - Containment Fan CoolerSystem Containment Cooling System, X 9.4.7-Drywell CoolingSystem X 9.4.8
{ - Containmeat Normal Ventilation Systems Containment Cooling System. X 9.4.7
.a DryweII Cooling System X 9.4.8 j - Combustible Gas Control Systems DrywcIl Purge System.' X 6.2.5 '
Hydrogen Control System, t t. Backup Containment Purge .
]. 3 System ;
- Other Containment Systems - Suppres ra Pool Make-up System X 6.2.7
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Table 3-1. Summary of GrapJ Gulf I Systems Covered in this Report (Continued)
Generic Plant-Specific System ' Name Report FSAR Section Syst_cep c Name Section Reference .!
. Reactor and Reactivity Control Systems
- Reactor Core Same X 4
- Control Rod System Control Rod Drive Mechanisms X 4.6
, - Chemical Poison System Standby Liquid ContmlSystem X 9.3.5 (SLCS)
Instrumentation & Control (I&C) Systens
-- Reactor Protection System (RPS). Same 3.4 7.2 1- - Engineered Safety Feature Actuation Various actuation systems 3.3 7.3 l
System (ESFAS) tn ,
Remote Shutdown System Same 3.4 7.4
- OtherI&CSystems Various othersystems X 7.5, 7.6, 7.7
~
Support Systems Class IE Electric PowerSystem .Same
]. 3.5 8.3 L .-. Non-Class IE Electric PowerSystem Same X i 8.3 T
, - Diesel Generator AuxiliarySystems Same 3.5 3.3,9.5.4 thru 9.5.7 i
- Component Cooling Water (CCW) Same X System 9.2.2 E
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' Table 3-1. Summary of Grand Gulf I Systems Covered in this Repar' (Continued) i Generic , Plant-Specific Report l
' System Nam _c FSAR _ Section '!
System Name Section Reference Support Systems (continued) r
_ Service Water System (SWS) . ;
, Standby Service WaterSystem - 3.7 9.2.1
- Residual IIcat Removal Service Water Standby Service WaterSystem 3.7 9.2.1
- (RIIRSW) System
~
Other Cooling WaterSystems . Turbine Building Cooling X 9.2.9 Water (TBCW) Sys:cm.
Plant Service WaterSystem. 3.8 9.2.8 e Plant Chilled WaterSystem X 9.2.7 f
i -
Fire Pmtection Systems 'Same X 9.5.1 1 i o ~ RoomIIcating, Ventilating,and Air - -IIabitability Systems, X 6.4 '
' Conditioning (IIVAC) Systems IIVACSystems X 9.4 Instrument and Service AirSystems Compressed AirSystem X 93.1
-.. ' Refueling and Fuel Storage Systems - Same X 9.1
- RadioactiveWasteSystems Same X I1-
- Radiation Protection Systems . Same X-i.' 12
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' ESF ELECTRICAL PLANT SEHVICE - SWCHGEAR ROOM WATER SYSTEM COOLER
.L J L J F 3 r 3 DIESEL SSWS COOLING GENERATORS TOWERS L J ( )
STANDBY SERVICE
. WATER BASIN 'bbWS t 'J L J d RHRlEAT
--* EXCHANGERS L J r 3 OTHER-
__, SAFEGUARD HEAT LOADS L J
. h .. SSWS = Standby Sennee WaterSystem o
Figure 3-1. Cooling Water jstems Functional Diagram for Grand Gulf 1
l Grand Gulf 1 3,1 REACTOR COOLANT SYSTEM (RCS) !
3.1.1 System Function
'; The RCS, also called the Nuclear Steam Supply System (NSSS), is responsible for directing the steam produced in the reactor to the turbine where it is used to rotate a generator and produce e eetricity. The RCS pressure boundary also establishes a boundary against the uncontrolled release of n.dioactive material from the reactor core and primary coolant.
3.1.2 System Definlilon The RCS tr.cludes: (a) the reactor vessel, (b) two recirculation loops. (c) t recirculation pumps, (d) 20 safety /tchef valves, and (e) connected piping out to a suitable -
Isolation valve boundary. Sim alified diagrams of the RCS and important system ;nurfaces are shown in Figures 3.1 1 anc,3.12. A summary of data on selected RCS components is presented in Table 3:1 1.
3.1,3 System Oncration During power operation, circulation in the RCS is maintained by one recirculation pump in each of the two recirculation loops and the associated jet pumps internal to the reactor vessel. The steam water mixture flows upward in the core to the steam dryers and separators where the entrained liquid is removed. The steam is piped through the main steam lines to the turbine. The separated liquid retums to the cose, mixes with the feedwater and is recycled again.
About 1/2 of the liquid in the downcomer region of the reactor vesselis drawn off by the recirculation pumps. The discharge of these pumps is returned to the inlet nozzles of the jet ) umps at high velocity. As the liquid enters the jet pumps the slow moving liquid in tie upper region of the downcomer is induced to flow through the jet pumps, producing reactor coolant circit!ation.
i The steam that is ptoduced by the reactor is piped to the turbine via the four main steam lines. There are two main steam isolation valves (MSIVs) in c.tch main steam line Condensate from the turbine is retumed to the RCG as feedwater.
Following a transient that involves the loss of the main condenser or loss of feedwater, heat from the RCS is dumped to the su)pression chamber via safety / relief valves on the main steam lines. A LOCA inside contanment or operation of the Automatic Depressurization SysMm (ADS) also dumps heat to the suppression chamber. Makeup to the RCS is provided by the Reactor Core Isolation Cooling (RCIC) system (see Section i
3.2) or by the Emergency Core Cooling System (ECCS 'see Section 3.3). Heat is transferred from the contalnment to the ultimate heat sink by the Residual Heat Removal (RHR) system operating in the suppression pool cooling mode. Actuation systems provide
3.1.4 System Success Criterin The mitigation, as RCS success criteria can be described in terms of LOCA and transient follows:
An unmitigatible LOCA is not initiated.
If a mitigatible LOCA is initiated, then LOCA mitigating systems at: successful.
If a transient is initiated, then either:
RCS Integrity is maintained and transient mitigating systems are successful, '
or RCS integrity is not maintained, leading to a LOCA like condition (i.e.
stuck open safety or relief valve, reactor coolant pump seal failure), and LOCA mitigating systems are successful 8
1/89
Grand Gulf 1 3.1.5 comnonent information !
A. RCS 4
- 1. Steam flow: 16.5 x 106 lb/hr.
- 2. Normal operating presstre: 1074 psia H. Safety / Relief Valves (20)
- 1. Set pressure: 1165 to 1190 psig
- 2. Relief capacity: 895,000 to 913,000 lb/hr (each)
C. Recirculation Pumps (2)
- 1. Rated Dow: 44,600 gpm @ 765 ft. head (332 psid)
- 2. Type: Vertcalcentrifugal -
4 D. Jet Pumps (24) ,
- 1. Total flow: 34.1 x 106 lb/hr @ 85.51 ft. head -
3.1,6 Sunnort Systems and Interfaces
, A. Motive Power The recirculation pumps are supplied with Nonclass IE power from AC motor generator sets.
B, htSIV Operating Power The lustruraent air system supports norrhal operation of the MSIVs. Valve operation is controlled by redundant AC solenoid pilot valves (Ref.1, Section 5.4.5.2). Both solenoid valves must be deenergized to cause MSIV closure.. <
( This design prevents spurious closure of an MSIV if a single solenoid valve should fail. - MSIVs are designed to fall closed if instrument air is lost or if AC
)
control power is lost to both solenoid pilot valves; This is achieved by a local dedicated air accumulator for each hcSIV and an independent valve closing spnng.
C. Recirculation Pump Cooling The reactor plant component cooling ' water system provides cooling ~ water to the I
- recirculation pump coolers.
3.1.7 Section 3.1 References i' 1. Grand Gulf Final Safety Analysis Report, i ;
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Table 3.1-1. Grand Guli 1 Reactor Coolant System Data Summary for Selected Components -
COMPONENT ID COMP. LOCATION POWER SOURCE VO LTAG E POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
RCIC-638 . MOV RC EP-MCC-16B31 480 SGRM119-8 AC/B HCIC-64A . MOV HCICHM EP-MCC-15B31 480 SGHM119-7 AC/A RCS-168 - MOV RC EP-MCC-16831 480 SGRM119-8 AC/B RCS-18 MOV HC EP-MCC-16B31 480 _
SGHM119-8 AC/B HCS-250A MOV RC EP-MCC-15811 /m SGRM119-9 AC/A RHR-BA MOV RHRRMA EP-MCC-15B31 E30 SGRM119-7 AC/A RHR-98 MOV HC ,
EP-MCC-16831 - 480 SGRM119-8 AC/B G
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Grand Gulf 1 ,,
3.2 REACTOR CORE ISOLATION CGGLING (RCIC) SYSTEM .
- 3. 2.1 - System Function The reactor core isolation cooling system provides adquate core cooling in the event that reactor isolation is accompanied by loss of feedwater tiow. This system provides makeup at reactor operating pressure and does not require RCS depressurization. .
The RCIC system is not considered to be part of the Emergency Core Cooling System (ECCS, see Section 3.3) and does not have a LOCA mitigating function. <
3.2.2 System Definition The reactor core isolation cooling pump and associated valves and piping formakeup vering deh, system water from consists of a steam. driven t the condensate storage tank or the suppression pool to the reactor pressure vessel., The RCIC can riso operate.in conjunction with the RHR system in the steam condensing mode, for high-pressure decay heat removal in this mode, steam from the reactor vessel is condensed in the RHR heat exchan;;er, and delivered to the RCIC pump suction for retum to the RCS.
Simplificc drawings of the reactor core Lsolation cooling system are shown in - '
Figures 3.21 and 3.2 2. - A summary of data on-selected RCIC system components is presented in Table 3.2-1.
3.2.3 System Oneration ,
During normal operation the RCIC is in standby with the steam supply valves to '
the RCIC turbine driven pump closed and the pump suction aligned to the condensate storage tank.
Upon receipt of a reactor pressure vessel (RPV) low water level signal, the turbine pump steam supply valves are opened and makeup water is supplied to the RPV.-
The primary water sup11y for the RCIC is the condensate storage tank (CST). The L' suppression pool is usec. as a backup water supply. Reactor ccre heat is dumped to the suppression pool via the safety / relief valves which cycle as needed to limit RCS pressure.
I The RCIC turbine also exhausts to the suppression pool, i
~' The RCIC can also operate in conjuncuon with the RHR system in th: steam-condensing mode, in which condensed steam is delivered from the RHR heat exchanger outlets to the RCIC pump suction, for return to the RCS. In this mode of operation, reactor decay heat is transferred via the RHR heat exchangers to the shutdown service water system (see Section 3.7) rather than to the suppression pool. The RCIC turbine still exhausts to the suppression pool.
The RCIC system is designed to operate on DC power only for an unspecified length of time. DC power is required for control and to operate most of the motor operated :
valves in the s supply valves 63B(ystem.
and 64A).-The only valves requiring AC power are two normally open stea 3.2.4 - System : Success Criteria-For the RCIC system to be successful there must be at least one' water source -
and supply path to the turbine driven ~
open pump discharge path to theand RCS, pump, an open steam supply path to the turbine, an an open turbine exhaust path to the suppression pool, l
U :)'
-13 1/89.
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Grand Gulf 1 i
3.2,5 comnonent Information i t
A. Steam turbine-driven RCIC pump: _
- l. Rated Flow: 825 gpm @ 2980 ft. head (1192 psid)
- 2. Rated Capacity: 100 %
- 3. Type: centrifugal ,
B. Condensate Storage Tank
- 2. Pressure: atmospheric 3.2,6 Sunnort System and Interfaces A. Control Signals !
- 1. Automatic
- a. The RCIC pump is automatically actuated on a reactor vessel low water -
level signal,
- b. The RCIC pump is automatically tri aped on a reactor vessel high water level signal signal, it may then x necessary to restart the pump manually,
- 2. Remote Manual The RCIC pump can be actuated by remote manual means from the Main Control Room.
B. Motive Power O 1. The RCIC turbine driven pump is supplied with steam from main steam loop A, upstream of the main steam isolation valves.
h 2. The RCIC motor-operated valves are eitner Class IE AC or C' ass IE DC loads that can be supplied from the standby diesel generators or the station batteries, respectively, as described in Section 3.5. The RCIC is capable of operating on DC power alone for an unspecified period of time.
C. Other
- 1. Lubrication for the turbine; driven pump is supplied locally.
/ b water diverted from the RCIC
- 3. . A room ventilation system cooled by the standby service water system (see Section 3.7) provides RCIC room cooling, i
3.2,7 Section 3.2 References .
- 1. . Kolaczkowski, A.M and Payne, A.C., " Station Blackout Accident Analyses I (Part of NRC Task Action Plan A 44)," NUREG/CR 3226,-Sandia National-Laboratories, May 1983,
- 2. Drouin, Mary T. et al., " Analysis of Core Damage Frequency From Internal Events: Grand Gulf 1," NUREG/CR 4550, Sandia National Laboratories, April 1987.
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Figure 3.2-2. Grand Gulf 1 Reactor Core Isolation Cooling System Showing Component Locations i
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- O Table 3.2-1. Grand Gulf 1 Reactor Core isolation Cooling System Data Summary for Selected Components COMPONENT ID . COMP. LOCATION POWER SOURCE VOLTAG E POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
CST TANK CST RCIC-10A MOV HCORM EP-DC-1DA2 175 SGRM119-7 DQ1 RCIC-13A MOV RCCRM EP-DC-1DA2 125 SGRM119 DQ1 RCIC-19A MOV HCORM EP-DC-1DA2 125 SGRM119-7 DC/1 1
RCIC-22A MOV HCORM EP-DCMCC-11DA 125 SWGR15AA DQ1 RCIC-31A MOV RCCRM EP-DC-1DA2 125 SGRM119 DQ1 RCIC-45A MOV HCORM EP-DCMCC-11DA 125 SWGR15AA DQ1 RCIC-46A MOV RCCRM EP-DC-1DA2 125 SGHM119-7 DQ1 RCIC-59A . MOV RCCRM EP-DCMCC-11DA 125 SWGR15AA DC/1 RCIC-63B MOV HC EP-MCC-16831 480 SGRM119-8 AC/B RCIC-64A MOV HCORM EP-MCC-15831 480 SGRM119-7 AC/A G RCIC-P1 TDP RCCRM RCIC-TGV HV RCCRM RCIC-TTV MOV HCORM SUPP POOL TANK RC-E-
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Grand Gulf 1 3.3 EMERGENCY CORE COOLING SYSTEM (ECCb)
O 4
Dj 3.3.1 System Function The ECCS is an integrated set of subsystems that n6rm emergency coolant injection and recirculation functions to maintain reac*nwre coolant inventory and adequate decay heat removal following a LOCA. The FCCS also performs suppression pool cooling and containment spray functions and has a capability for mitigating transients, 3.3.2 System Definitio.n The emergency coolant injection (ECI) function is performed by the following ECCS subsystems:
High Pressure Core Spray (HPCS) System Automatic Depressurization System (ADS)
Low Pressure Core Spray System (LPCS)
Low Pressure Coolant Injection (LPCI) System The HPCS system is provided to supply make up water to the reactor pressure vessel (RPV) ir. the event of a small break LOCA which does not result in a rapid depressurization of the reactor vessel. The HPCS also is capable of providing makeup to RCS following a large LOCA. The HPCS system consists of a motor driven pump, system piping, valves and controls. A dedicated diesel generator supplies electric power to HPCS components.
The automatic depressurization system (ADS) provides automatic RPV depressurization following a small break LOCA or transient so that the low pressure systems (LPCI and LPCS) can provide makeup to the RCS. The ADS utilizes 8 of the 20 safety / relief valves that discharge the high pressure steam to the suppression pool.
The LPCS system supplies make up water to the reactor vessel at low pressure.
V[ t The system consists of a motor driven pump to supply water from the suppression pool to a spray sparger in the reactor vessel above the core.
The low pressure coolant injection system is an operating mode of the RHR system, and provides make up water to the reactor vessel at low pressure. The LPCI system consists of three loops, designated LPCIA, LPCIB, and LPCIC. Each loop consists of a motor driven pump which supplies water from the suppression poolinto the reactor vessel. Loops A and B of the RHR system can be manually realigned as needed to perform suppression pool cooYmg or conta'mment spray as pan ohhebanc emergency cott cooling function. The RHR heat exchangers also can be aligned for steam condensing operation in conjunction with the RCIC system (see Section 3.2). This is not an ECCS function.
Simplified drawings of the HPCS system are shown in Figures 3.31 and 3.3 2. The LPCS system is shown in Figures 3.343 and 3.3-4. A flow diagram of LPCIA is shown in Figures 3.3 5 and 3.3 6, LPCIB is shown in Figures 3.3-7 and 3.3 8, and LPCIC is shown in Figures 3.3 9 and 3.310. Interfaces between these systems and the RCS are shown in Section 3.1. A summary of data on selected ECCS components is presented in Table 3.3-1, 3.3.3 Svstem Ooeration All ECCS systems normally are in standby. The manner in which the ECCS operates to protect the reactor core is a function of the rate at which coolant is being lost from the RCS. The HPCS system is normally aligned to take a suction on the Condensate Storage Tank (CST). The HPCS system is automatically started in response to decreasing RPV water level, and will serve as the primary source of makeup if RCS pressure remains n high. Reactor core heat is dumped to the suppression pool via the pipe break or the safety / relief valves which cycle as needed to limit RCS pressure. A dedicated diesel (ts) 18 tygg t -
Grand Gulf I generator supplies electric power to HPCS components. If the break is of such a size that
- p. the ecolant loss exceeds the HPCS system capacity, then the LPCS and LPCI systems can k '< provide higher capacity makeup to the reactor vessel at low pressure.
The Automatic Depressurization System will automatically reduce RCS pressure if a break has occurred and RPV waterlevelis not maintained by the HPCS system. Rapid depressurization permits flow from the LPCS or LPCI systems to enter the vessel. Water can be taken from the suppression pool by each of these systems for injection into the core.
RHR loops A and B can be aligned for suppression pool cooling, with heat being transferred to the shutdown service water system (See Section 3.7) via the RHR heat exchangers. RHR loops A and/or B can be aligned for suppression pool cooling while any remaining RHR loops continue to function in a LPCI mode.
3.3.4 System Success Criteria LOCA mitigation requires that both the emergency coolant injection (ECI) and emergency coolant recirculation (ECR) functions be accomplished. The ECl system success enteria for a large LOCA are the following (Ref.1):
The high pressure core spray system (HPCS) with suction on the suppression pool or the condensate storage tank (CST), or The low pressure core spray system (LPCS) with suction on the suppression pool,or Any 1 of the 3 low pressure coolant injection loops (i.e. LPCIA, LPCIB, LPCIC) with suction on the suppression pool.
The ECl system success criteria for a small LOCA, are the following (Ref.1):
fs
\
.ie high pressure core spray (HPCS) system with suction on the suppression pool or the condensate storage tank, or The (LPCS)automatic depressurization system (ADS) and the low pressure core spray system, or The automatic depressurization system (ADS) and 1 of 3 loops in the low pressure coolant injection (LPCIA, LPCIB, LPCIC) system.
The success criterion for the ADS is the use of any 1 of 2 ADS trains, it is mossible that the coolant inventory control function for some small LOCAs can be satisfied ay low-capacity high pressure injection systems such as the control rod drive hydraulic system (see Section 3.6).
The ECR success criteria for LOCAs are integrated with the ECI success criteria above. All systems essentially are operating in a recirculation mode when drawing water from the suppression pool.
involve the following:For transients, the success criteria for reactor coolant inventory contr The reactor core isolation cooling (RCIC) system (not part of the ECCS, see Section 3.2), or Small LGCA mitigating systems as described above For the suppression pool cooling function to be successful, one of two RHR trains must be aligned for containment heat removal and the associated shutdown service water train must be operating to complete the heat transfer path from the RHR heat exchangers to the ultimate heat sink.
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19 1/89 l
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Grand Gulf 1-I 3.3,5 Comnonent information A. Motor
- 1. Rateddriven HPCS flow: 550 gem pump @P1 gpm @ 200 psig l177 psig,7115
- 2. Rated capacity: lw%
- 3. Type: centrifugal B. Motor driven LPCS pump P1 1
- 1. Rated flow: 7,000 gpm @ 122 psid (vessel to drywell)
- 2. Rated capacity: 100 %
- 1. Rated flow: 7450 gpm @ 20 psid (vessel to drywell) each -
- 2. Rated capacity: 100 %
- 3. - Type: centrifugal D. RHR Heat Exchangers l A,2A,1B, and 2B
- 1. Heat transfer capability: 184,7 x 106Btu /hr per loop '
- 2. Ratedcapacity: 100 %
- 3. Type: inverted U tube, single pass shell, multi pass tube, vertical mounting E. Automatic depressurization valves (8)
- 1. Rated flow: 800,000 lb/hr @ 1125 psig (each)
F. Pressure Suppression Chamber
- 1. Design temperature: 185 F-
- 2. Maximum operating temperature: 95'F .
- 3. Minimum water volume: 135,291 ft3 G. Condensate Storage Tank -
1.-
Capacity: 170,000 gallon available supply (for use by RCIC and HPCS)
- 2. Pressure: atmosphenc -
3.3.6 Sunnort Systems and Interfaces A'. Control signals
- 1. Automatic - "
a The HPCS pump, LPCS pump, and the LPCI pumps, and all their associated valves function upon receipt oflow water level in the reactor '
vessel or high pressure in the drywell,
- b. - The HPCS pump is automatically tripped on a reactor vessel high water level signal. It may then be necessary to restart the pump manually,
- c. The ADS system is actuated upon coincident signals of the reactor vessel low water level, drywell high pressure, confirmed reactor vessel -
low water level, and a permissive signal indicating LPCS or.LPCI pump -
discharge pressure. There is a 2 minute delay to ensure the HPCS has time to opera.e.
- d. HPCS pump suction is automatically switched to the suppression pool-on high suppression pool water level .or low water level:in the condensate storage tank 20i 1/89
4 Grand Gulf I
((v
]j their function under the LPCI mode.
- 2. Remote manual ECCS pumps and valves and the ADS can be actuated by remote manual means from the main control room.
B. Motive Power
- 1. The ECCS motor-driven pumps and motor operated valves are Class 1E AC loads that can be supplied from the emergency diesel generators, as described in Section 3.5.
- 2. The components of the HPCS are powued from a dedicated diesel generator (Diesel generator IC, see Section 3.5).
C. Other
- 1. Lubricatien and cooling for the ECCS pumps are assumed to be supplied .
locally.
- 2. ECCS pump room ventilation systems are cooled by standby service water (see Section 3.7).
- 3. The shutdown service water system provides cooling water to the RHR heat exchangers, the RHR pump seals and the ECCS pump room coolers (see Section 3.7). ,
3.3.7 Section 3.3 References
- 1. Drouin, Mary T. et al., "Analy',is of Core Damage Frequency From Internal Events: Grand Gulf 1," NUREC/CR-4550, Sandia National Laboratories, April
, 1987.
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j E Figure 3.3-2. Grand Gulf 1 High Pressure Core Spray System l Showing Component Locations j I 1
1 l
r O 4
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i
l LPCSRM l RC l UNKNOWN l l l ;
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Figure 3.3-4. Grand Gulf 1 Low Pressure Core Spray System Showing Component Locations i
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Showing Component Locations i
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Table 3.3-1. Grand Gulf 1 Emergency Core Cooling System Data Summary for Selected Components COMPONENT ID COMP. LOCATION POWER SOURCE VO LTAG E POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
HPCS-1 MOV HPCSRM EP-MCC-17811 480 SWGR17AC AC/C HPCS-10 MOV HPCSRM EP-MCC-17B11 480 SWGR17AC AC/C HPCS-11 MOV HPCSRM EP-MCC-17811 480 SWGR17AC AC/C HPCS-15 MOV HPCSRM EP-MCC-17B11 480 SWGR17AC AC/C HPCS-23 MOV HPCSRM EP-MCC-17811 480 SWGR17AC AC/C HPCS-4 MOV 119AB EP-MCC-17811 480 SWGR17AC AC/C HPCS-P1 MDP HPCSRM EP-BS-17AC 4160 SWGR17AC AQC LPCS-12A MOV LPCSRM EP-MCC-15811 480 SGRM119-9 AC/A LPCS-1 A MOV LPCSRM EP-MCC-15B11 480 SGRM119-9 AC/A LPCS-SA MOV PENRMA220 EP-MCC-15B11 480 SGRM119-9 AC/A LPCS-P1 MDP LPCSRM EP-BS-15AA 4160 SWGR15AA AC/A RHR-21B MOV RHRRMC EP-MCC-16B11 480 SGRM119-10 AC/B RHR-24A MOV RHRRMA EP-MCC-15B31 480 SGRM119-7 AC/A RHR-24A MOV RHRRMA EP-MCC-15B31 480 SGRM119-7 AC/A RHR-248 MOV RHRRMB EP-MCC-16831 480 SGRM119-8 AC/B RHR-24B MOV RHRRMI3 EP-MCC-16831 480 SGRM119-8 AC/B RHR-27A MOV RHRRMA EP-MCC-15831 480 SGRM119-7 *WA RHR-27A MOV RHRRMA EP-MCC-15B31 480 SGRM119-7 AC/A RHR-278 MOV RHRRMB EP-MCC-16831 480 SGRM119-8 AC/B RHR-278 MOV RHRRMB EP MCC-16B31 480 SGRM119-8 AC/B RHR-28A MOV RC EP-MCC-15831 480 SGRM119-7 AC/A RHR-28A MOV RC- EP-MCC-15B31 480 SGRM119-7 ACIA RHR-288 MOV RC EP-MCC-16831 480 SGRM119-8 AC/B h
RHR-28B MOV RC EP-MCC-16831 480 SGRM119-8 AC/B RHR-37A MOV RC EP-MCC-15B31 480 SGRM119-7 AC/A RHR-378 MOV RC EP-MCC-16B31 480 SGRM119-8 AC/B RHR-3A MOV RHRRMA EP-MCC-15B31 480 SGRM119-7 AC/A RHR-38 MOV RHRRMB EP-MCC-16B31 480 SGRM119-8 AC/B
O O D Table 3.3-1. Grand Gulf 1 Emergency Core Cooling System Data Summary ,
fOr Selected Components (Continued)
COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
RHR-42A MOV RC EP-MCC-15831 480 SGHM119-7 AC/A RHR-428 MOV RC EP-MCC-16831 480 SGRM119-8 AC/B RHfi-42C MOV RHP'.iMC EP-MCC-16811 480 SGRM119-10 AC/B RHR-47A MOV RHRfIMA Ef' MCC-15B31 480 SGRM119-7 AC/A FlHR-478 MOV RHf1RMB EP-MCC-16B31 480 SGRM119-8 AC/B RHR-48A MOV RHRRMA EP-MCC15831 480 SGRM119-7 AC/A RHR-488 MOV RHRRMB EP-MCC-16B31 [480 SGRM119-8 AC/B FlHR-488 MOV RHRRMB EP-MCC-16831 480 SGRM119-8 AC/B RHR-4A MOV HHRRMA EP-MCC-15B31 480 SGRM119-7 AC/A RHR-48 MOV RHRRMB EP-MCC-16B31 480 SGRM119-8 AC/B FDiR-4C MOV RHRHMC EP-MCC-16811 480 SGRM119-10 AC/B U RilR-52A MOV RHRRMA EP-MCC-15831 480 . SGRM119-7 AC/A FCiR-52B MOV RHRRMB EP-MCC-16831 - 480 SGRM119-8 AC/B RHR-53A MOV HHRRMA EP-MCC-15831 480 SGRM119-7 AC/A RHR-53A MOV RHRRMA EP-MCC-15831 480 SGRM119-7 AC/A RHR-538 MOV RHRflMB EP-MCC-1683 : 480 SGflM119-8 AC/B RHR-538 MOV RHRRMB EP-MCC-16d31 480 SGRM119-8 AC/B RHR-6A MOV RHRRMA EP-MCC-15831 480 SGHM119-7 AC/A ,
RHR-6B MOV RHilRMB EP-MCC-16831 480 SGHM119-8 AC/B RHR-87A MOV RHRflMA EP-MCC-15B31 480 SGRM119-7 AC/A RHR-87B MOV' RiiRRMB Ep-MCC-16831 480 SGRM119-8 AC/B HHR-8001 A - HX RHRRMA RHR-80018 HX- RHRflMB b
c RHR-8002A HX RHRRMA RHR-80028 HX HHf1RMB RHR-C002A MDP flHRilMA EP-BS-15AA 4160 SWGR15AA AC/A RHR-C002B MDP RHRRMB EP-Ba-16AB 4160 SWGR16AB AC/B RHH-C002C MDP RHRRMC EP-BS-16AB g 4160 SWGR16AB AC/P
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-l Table - 3.3-1. Grand Gulf'1 Emergency Core Cooling System Data Summary for Selected Components (Continued)
COM.)ONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG.
TYPE LOCATION LOAD GRP.
RHR48A MOV RHRRMA EP-MCC-15B31 480 SGRM119-7 AC/A I $1
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3.4 Grand Gulf 1 INSTRUMENTATION AND CONTROL (I&C) SYSTEMS O- 3.4.1 System Function The instrumentation and control systems consist of the Reactor Protectio System (RPS), actuation logic and controls for various Engineered Saf systems, and systems for the display of plant information to the operators. The R ESF actuation systems monitor the reactor plant, and alert the operator to ta ve action before specified limits are exceeded.
(scram) to rapidly shut down the reactor when plant conditions exceed The RPS willinitiate an au one or more systems based on the specific limits or combinations shutdown ca 3 ability is provided to ensure that the reactor can be placed in a safe cond in the event t1at the main control room must be evacuated.
3.4.2 System Definition relays that interface with the control circuits for compone Hydraulic System (see Section 3.6). The ESF actuation systems include in sensor and transmitter units, logic units, and relays that interface with the control for the many different components that can be actuated. Operator ins systems consist of dis summary of data on se.ectecalay ?anels that are powered by 125 VDC or 120 VAC power I&C system components is presented in Table 3 41.A 3.4.3 System Oneration A. RPS O The RPS has four input instrument channels and two output actuation tra The variables:RPS monitors and automatically initiates a scram based on th ,
Neutron monitoring (APRM) system Neutron monitoring (IRM) system Neutron monitoring Reactor vessel high pressure(SRM) system (REFUEL mode only)
- Reactor vessellow waterlevel
- Reactor vessel high water level (RUN mode only)
Turbine stop valve closure
- Turbine control valve fast closure Scram discharge volume high water levelMain steam line isolat Drywell high pressure Main steam line high radiation In addition, the operator can manually initiate a scram. Both output cha must be de-energized to initiate a scram. The failure of a single componen power supply does not prevent a desired scram or cause an unwanted scram.
B,ESF ESF actuation systems have up to four in sensed parameter, and two output trains.put instrument channels for each In general, each train controls equipment powered from different Class IE electrical buses. The ESF sy C that can be automatically actuated include the following ng): (not a complete iN 35 1/g9
1 l
1 Grand Gulf 1 Emergency Core Cooling System l HPCS (h,,/ -
LPCS LPCI/RHR ADS Standby power systems Shutdown service water system Various room cooling systems ECCS equipment room HVAC system Essential switchgear heat removal HVAC system Diesel generator HVAC system Shutdown service water pump room HVAC system Main control room HVAC system Details regarding ESF actuation logic are included in the system description for the actuated system.
C. Remote Shutdown The remote shutdown system provides controls for reactor systems needed to carry out the shutdown function from outside the control room and bring the reactor to a safe shutdown condition in an orderly manner.
Controls and instrumentation for the remote shutdown system are phycically located on two panels. One panel is used for the control and instrumentation of systems powered from the ESF division 1 bus, while the other panel is used for systems powered from the ESF division 2 bus. ii.e two remote shutdown panels are located in a room adjacent to the EJF switchgear rooms located at r3 elevation 111 ft of the control building. The two panels are 9 feet apart, and all (v) cabling associated with the panels and the systems which they operate are separated.
Sufficient instrumentation and controls are provided outside the control room on the seismic Category I remote shutdown panels IN22-P150 and IN22 P151 to:
Achieve hot shutdown of the reactor.
Maintain the unit in a safe condition during hot shutdown.
Achieve cohl shutdown of the reactor.
The controls on the remote shutdown system panels are in parallel with the control room uontrols and, therefore, operate the same equipment. Items of the following systems which are essential to the residual heat removal function during the s4e shutdown period have controls and instrumentation located on the remote
- hutdown panels:
Reactor core isolation cooling (RCIC) system.
Residual heat removal (RHR) systems A and B Shutdown service water (SSW) systems A and B Nuclear boiler system (safety relief valves).
Upon loss of offsite power, the standby diesel generators are automatically started and power is automatically restored to the ESF division 1 and 2 buses.
Manual controls are also available locally at the diesel generator control panels as a backup to automatic initiation, e :
L/ 36 1/89
Grar.d Gulf 1 3.4.4 System Success Criterin A. RPS The RPS uses hindrance logic (normal = 1, trip = 0) in both the input and output logic. Therefore, a channel will be in a trip state when input signals are lost, when control power is lost, or when the channel is temporarily removed from service for testing or mairnenance (i.e. the channel has a fall safe failure mode).
A reactor scram will sur upon loss of control power to the RPS, A reactor -
scram is implemer:ed by the scram pilot valves in the control rod drive hv%iic system (see Section 3,6), Detalls of the RPS for Grand Gulf I have not been detennined.
l E. Other Actuation Systems A single component usually receives a signal from only one actuation system output train. Trains A and B must be available in order to automatically actuate their respective com ponents, . Actuation systems other than the RPS typically -
use hindrance input logic (normal = 1,' trip = 0) and transmission output logic (normal w 0, trip = 1) In this case, an input channel will be in a trip state when input signals are lost, when control power is lost,'or when the channel is temporarily removed from service for testing or maintenance (i.e. the channel has a fall-safe failure mode) Control power is needed for the acmation system ;
output channels to send an actuation iignal Note that there may be some -
actuation subsystems that utilize hindrance output logic, For these subsystems, loss of control power will cause system or component actuetion, as is the case with the RPS. Details of the other actuation systems for Grand Guif I have not been determined.
C, Manually Initiated Protective Actions When reasonable time is available, cettain protective actions may be performed manually operating m,by plant-personnel- The control room op;rators are capable of dividual components using normal control circuitry, or operating groups of components by manually tripping the RPS or other actuation subsystem.-The control room operators also may send qualified persons into the plant to operate components locally or from some other remote control location (i.e., the remote shutdown panel or a rnotor control center). To make l
these judgments, data on key plant parameters-must be available to the l operators.
\
3.4.5 Suonort Systems and-Interfaces l A. ControlPower t 1. RPS The RPS is powered from the 120 V AC RPS system. Backup scram valves are povtered from the 125 VDC system. -
L 2 O:her actuation and control systems-Control power sources for other actuation and control systems are identified in Table 3.4-1.
' 3. OperatorInstrugration- .
Operator instrumentation displays are powered from 120 VAC panels l through transformers from ESF motor control centers. -
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Grand Gulf 1 1 3.4.6 Section 3.4 References
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l 1. Grand Gulf Final Safety Analysis Report, Section 7.4 l
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1 Table 3A 1. Matrix of Grand Gulf 1
- Control Power Sources i
D SYSTEM . } vision l o a
- - ~
1
-) l RCiC HPCS .
ADS A ADSB RHR(LPCI) A RHR (LPCI) B RHR(LFCl)C LPCS DIESEL 1 & AUXILIARIES DIESEL 2 & AUXILIARIES Os DIESEL 3 & AUXILIARIES SSW A SSW8 SSWC f&C GUTBOARD MSIVS INBOARD MSIVS i
O 39 1/89
_ . _ . _ _ _ . . . ~ . . . _ . . _ . _ . . . . . . _ . - . _ . . _ . . . _ . _ . . - _ _ . _ _ _ . . _ . _ _ _ , _ _ - , . _ _ , _ . . . _ _ . . - , . .
Grand Gulf 1 3.5 ELECTRIC POWEll SYSTEM t 3.5.1 System Function The electne power system supplies power to vanous equipment and systems needed for normal operation and/or response to accidents. The onsite Class IE electric power system suppons the operation of safety class systems and instmmentation needed to estatJish and maintain a safe shutdown plant condition following an accident, when the nomial electric power sources are not available.
3.5,2 System Definition The onsite Class lE electric power system consists of three independent 4160 and 480 VAC trains, denoted A, B, and C. Train C is dedicated to components of the HPCS system. Each AC power division has a standby diesel generator which serves as the AC power source when both the preferred and alternate sources of offsite power are unavailable. The En :ineered Safety Features (ESP) AC divisions require DC Power from the associated ESF 3C buses for circuit breaker control power, diesel generator field Rashing, and the diesel fuel oil boostei nump.
The 125 VDC power syste., )nsists of three independent divisions denoted !.
2, and 3. Each division has two separate battery chargers which normally supply the load and a bank of batteries which funcuon as a backup. Each ESF DC battery bank consists of 60 lead calcium type cells connected in series to produce the rated output of 125 VDC.
The lh0 VAC essentir.1 power system consists of redundant distribution panels fed through transformers connected to separate ESF motor control centers.
The 120/240 VAC unintermptible power system consists of various AC buses with transformers and DC buses with inverters. This system supplies power for services necessary for the normal operation and reliability of the plant but are not required for plant safety.
O Simplified one line diagrams of the electric power system are shown in Figures Q 3.51 to 3.5 9. A mimary of data on selected electric power system components is presented in Table 3.51. A partial listing of electrical sources and loads is presented in Table 3.5 2.
3.5.3 System Ooeration During nomial operating conditions, the Class lE AC power system is supplied from the 500 kV offsite power system via the 500 kV switchyard and Service Transformer Number 11. The alternate source of offsite aower is the 115 kV Line to Port Gibson which is supplied via ESF Transformer Number ,1 and is physically and electrically separated from the 500 kV switchyard.
The three standby diesel generators are started automatically upon loss of ultage on tne associated standby 4160 VAC bus, low reactor water level, high drywell pressure signal of 2 psig, or a LOCA signal. The diesel generators can also be started manually. Diesel generator l A is connected to 4160 VAC bus 15AA, diesel generator IB is connected to 4160 VAC bus 16AB, and the HPCS diesel generator IC is connected to 4160 VAC bus 17AC. Bus 15AA feeds the 480 VAC buses 15BAl,15BA2,15BA3, 15BA4,15 BAS, and 15BA6, which in turn feed various train A motor control centers (MCCs). Bus 16AB feeds the 480 VAC b!.ses 16BB1,16BB2,16BB3,16BB4,16BB5, and 16BB6, which in tum feed various train B MCCs. Bus 17AC feeds the 480 VAC bus 17801 which supplies the MCC 17Bil. Details of the 4160 and 480 VAC systems are shown in Figures 3.5-1 through 3.5 6.
The 125 VDC inde independent electrical divisions. pender: Class IE power systems consist of three These systems are shown in detail in Figures 15 7 and 3.5 8. The DC power portion of each division consists of a main DC motor cont.ol center I
o that distributes power to: (a) a 125 VDC distribution panel and (b) various DC loads that are powered directly from the MCC. Two battery chargers powered from 480 VAC 40 1/89
Orand Gulf 1 ,
- MCCs nonnally supply power to all DC 'oads and maintain th front line systems. Each ESF battery bank can supp the equired DC loads for eleven hours after a loss of AC power if unnecessary to s are shed. When all loads are connected, the batteries in divisions I and 2 will last a minimum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and the batteries in division 3 will last a minimuru of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
The 120 VAC Class IE power system supplies power to instrumentation systems. Nonnat power is supplied to the 120 VAC system from the 480 VAC MCCs via regulated not available.isolation transfonners. Drawings of the essential instrument power system were The 120/240 VAC uninterruptible power system is shown in Figure 3.5 9.
This system frequency is desi;;ned to provide a source of power which satisfies the voltage and variation
,imit requirements of the station computers. A high degree of power continuity is pc.2vided, with the ability to transfer to an alternate AC source of power with sufficient speed so the operation of the computers and instruments are not affected.
Nonnally, th, uninterruptible AC power system receives its power from an inverter batter static switch arrangement which is fed by the station 125 VDC non Class IE buses.y and non Class IE battery chargers which are connected to one of the Class lE- ,
t Any failure in the equipment from the 125 VDC supply circuit enables the static switch to transfer the power source automatically to an altemate source fed from a 480 voltl Class lE AC bus through a transformer. However, when a LOCA occurs, the Class lE feed from the load center that feeds the chargers is tripped.
Redundant safeguards equipment such as motor driven pumps and motor operated valves are supplied by different buses or MCCs. For components receiving electne power either directiv of indirectly from 4160 bus 15AA. l Load bus group
- 16. A% "AC/B" contains components powered ilther directly or indirectly from 4160
)
from 41u0 bus 17AC Components receiving DC power are "DC/l" to "DC/3", based on the battery source.
3.5.4 System Success criterin i.
I Basic system success criteria for miti;;ating transiena and loss of coolant accidents are defined by front line systems, whLeh then create demands on suppor
, systems. Electric power system success criteria are defh.ed as follows, without takin credit forcross ties that may exist between independent load groups:
(also needed fordiesel starting)Each Class lE DC load group is sup Each Class 1E AC load group is isolated from the non Class lE system and is
- supplied from its respective emergency power source (l.c. diesel generator)
Power distribution paths to essennal loads are intact '
Power to the battery chargers is restored before the batteries are exhausted 3.5.5 Comnonent Information )
(
A. Standby diesel generators 1 A, IB h Continuous power ratingt 7000 kW
- 2. Rated voltage: 4160 VAC
- 3. Manufacturer: Delaval 41 1/89 l
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D.1IPCS diesel generator IC f 1. Continuous power rating: 3300 kW
- 2. Rated voltage: 4160 VAC
- 3. Manufacturer: General Motors i
C. Station batteries I A, IB,1C, and ID
- 2. Rated voltage: 125 VDC
- 3. Design capacity: Division 1&2 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> minimum Di ision 3 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> minimum 3.S.6 Suonort Systems and Interfaces A. Control Signals
- 1. Automatic The standby diesel generators are automatically started on loss of voltage on their associated bus, low reactor water level, hlgh drywell pressure signal of ,
2 psig, or on a LOCA signal !
- 2. Remote manual The diesel generators can be started, and many distribution circuit breakers i can be operated from the main control room.
D. Diesel Generator Auxiliary Systems '
The following auxiliaries are provided for each emergency diesel generator: *
- Cooling p
s -
The shutdown service water system (see Section 3.7) provides for diesel cooling, Fuelin; An ind ependent day tank is provided for each diesel. The day tanks for the Division 1 and 2 diesel generators can su) port 1 1/2 hours of diesel operation at design load, and ti.e day tank for t ic Division 3 diesel generator can support 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of diesel operation. Long term fuel tanks are located ;
underground below the diesel generator rooms.
Lubrication Each diesel generator has a self-contained lubrication system.
- Starting An independent starting air accumulator is provided for each diesel generator.
Control wer Each die el generator is dependent on 125 VDC power from a station bsttery for control power.
Diesel room ventilation fans provide room cooling during diesel operation. ;
Combustion air intake, exhaust, and crankcase ventilation l
Standby generator excitation subsystem C. Switchgear Room Ventilation The essential sv.itchgear rooms have fan cooler units that are cocled by the Shutdown Service Water System (SSWS, see Section 3.7). :
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NOTE: tlNES aAAY NOT RE PRESENT TRLE CA8tE ROUTesG 8ETWEEN ROGRAS Figure 3.5-2. Grand Gulf 14160 VAC Electric Power Distribution System Showing Component Locations
i.
s 1
i OESE L TO ESF TO ESF YOESF GmE nafm st TRAfvSF OnadER TRANSFOHn4 R TRANSFORRE R NO12 880 21 er7 si
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eso vac sus tSeas eso vac aus isBAS 480VAc eust$3A4 aso vac sus 158A2 eso vac Hus vsn43 EP-SS 15ELW ano vac eus tsamt
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Figure 3.5-3. Grand Gulf 1480 VAC Train A Electric Power Distribution System i i
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i 10 E SF w su TO E SF TO ESF W WN I' TRAGO #t R TRAh9tDeAE R TRMGFOp%R 940 82 f40 21 NO 11 it ;L
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Figure 3.5-4. Grand Gulf 1480 VAC Train A Electric Power Distribution System
{ Showing Component Locations j
4
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' Figure 3.5-5. Grand Gulf 1480 VAC Trains B and C Electric Power Distribution System i
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u l ..c y .... g Osf Sit 66.8uf>WL701413 04 54 t TO E SF - TOEg TO f 5 G eE RSitst 12 105 5F 1017 1059 TRAN9 Gu( A TRAmsFCNed.R TRfm90FMEE *1 TraussM3e(R YpeusgaeaR THaswSFOHaaR
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' = = == == ==
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==== sus seems eeB wAC 30$ De8Se l 5 ete wac SUS 9588E } l ese vac SUS *e.e3 I I l l l l [ em . l lI est.w.ac
. .e .,Sus l seess
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ese vac ascc tre,s een wac ear seses ese wac ear seass ,
g P GCC 17998) d P 6 =A513 l een vac w4 eener l ene v4 eax esses ese vac es.c seer, esewaceux seem, ' ese vac ear ,es ,
g 3 $P RE;C 900393 l g P em.C 16999; Po e i . ...r.c 1 1 . . = . l 4 w .... u 1 iw..mn.1
. ore ins =xamx=T mx cams.o.,s.canws.Roo s Figure 3.5-6. Grand Gulf 1480 VAC Trains B and C Electric Power Distribution System Showing Component Locations
l i
?
Z 480 VAC MCC 15BA6 480 VI.C MCC 158A3 (EP-BT-t tOA) - i (EP-MCC-15BA6) (EP-MCC-158A3)
. }
p (Ef" 4T,-1DA4) y (EP-DC-IDAS) i t
.I P [] Is i
[
125 VDC BUS 11DA [
, (EP-DCMCC-11DA) [
.e-is !
i 125 VDC DISTRIBUTION PANEL IDA2 (EP-DC-1DA2}
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Figure'3.5-7. Grand Gulf 125 VDC Electrical Power Distributian System (Page 1 of 3) '
i I
s
. - _ _ _ a __ - _ _ __ __ . ._ - .. -__ _ _ - . _ - _ .
._. __.______.m.._. _ - - . . . _ _ . _ _ - _- __ ._ . . - - - _ _ - . - . . . _ _ ..
i l
I i
Div 2125 vDC !
BATTERY (EP-BT-11DB)
- # AC C 16886 6 VAC EC 16883 (EP-MCC-16BB6) (EP-MCC-16BB3)
I i
i g (EP-DC-1DB4) g (EP-DC-1DBS) i E i I
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i 125 VDC BUS 11DB (EP-DCMCC-11DB) I t
n
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i Figure 3.5-7. Grand Gulf 125 VDC Electrical Power Distribution System (Page 2 of 3) j
.. -. . - _ .. . _. - - ~ ~ _ - - .~ _ . - - - . - . . . - . - . - -. ._. .
i'
/ '
l DIV 3125 VDC BATTERY !
t i
480V MCC 13811 480V MCC 1780- __ (EP-BT-1 t DC'; ;
, (EP-MCC-17801)
I :
e il SZ (EP-DC-1DCS) E (EP-DC-1DC4) t 5- l v.
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e i
125V VDC BUS 11DC
=
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3' Figure 3.5-7. Grand Gulf 125 VDC Electrical Power Distribution System'(Page 3 of 3) 4
.I
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O i l BTRMD1 l SGRM119-9 l l Z 480 VAC MCC 15BA6 480 VAC MCC 15BA3 (EP-BT-11DA) -
(EP-MCC-15BA6) (EP-MCC-15BA3) i 1
t i
y (EP-DC-1DA4) y (EP-DC-1DAS) i i
i .
, II O II l
125 VDC BUS 11DA j j u 14 (EP-DCMCC-11DA)
.I 2
4 4
i l
125 VDC DISTRIBUTIOff PAtJEL IDA2 (EP-DC-1DA2) 4 .
) l SWGR15AA l
, l SGRM119-7 l 4
C g t4OTE Li?JES MAY tJOT REPRESEP4T TRUE CABLE ROUTitJG BETWEEtt ROOuS
! Figure 3.5-8. Grand Gulf 125 VDC Electrical Power Distribution System Showing Component Locations (Page 1 of 3) 1, i
i
. . . _ . . _ _ _ . _ _ _ .__....m _ _ _ _ _ _ _ . . . . . ~ _ _ _ _ _ _ . _ _ _ _ . . _ _ _ _ _ _ - - _ _ __ __ _ _ _ _ _ _ _ ___ __
l l BTRMD2 l 1 l SGRM119-10 l l DIV 2125 VDC BATTERY l (EP-BT-11DB) 2 480 VAC MCC 16886 480 VAC MCC 16883 l
~
i n (EP-DC-1DB4) p, (EP- DC-1DBS) i O j i
i II O II i
i 125 VDC BUS 1108 (EP-DCMCC-1108) l SWGR16AB l FOTE LINES MAY POT REPRESErJT TRUE CABLE ROUTING BETVEErJ ROO$ts
- 5 o
1 Figure 3.5-8. Grand Gulf 125 VDC Electrical Power Distribution System 1
Showing Component Locations (Page 2 of 3) l l
1 i
t l' UNKNOWN l l SWGR17AC l l BTRMD3
( i 1
DIV 3125 VOC ,
BATTERY 480V MCC 13811 480V MCC 17801 (EP-MCC-17801)
_- (EP-BT-11DC)
I i
t
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I p, (EP-DC-1DCS) E (EP-DC-1DC4) i i
i i
- m u
i [] II I I E
12SV VDC BUS 11DC (EP-DCMCC-11DC) e 1
' I i- TO DivtSION 3 LOADS r l
i DGRMC l
< s i
3 FK.TE: 4.INES MAY FOT REPRESENT TRUE CABLE ROUTING BETWEEN ROOuS l
i Figure 3.5-8. Grand Gulf 125 VDC Electrical Power Distribution System
} S'iowing Component Locations (Page 3 of 3) i-i 1-
4 !
3- ~g -% /
u t
I q 480w asCC 34842 325 VOC DC as(E 1 TOE samtascCteac tn voc OcescCt100
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T ......_T T-eNERTER Cae8ET pnrERTE R CA9mf T 120 Pao VAC upsNTERRUPTR E FouuE R t DesTReUTsursPAmiEL TY75 .
12G240 VAC ops 3ellRRUPf R.E P0ugE R ,
32SJeO VAC UlWFsTEREttFT&E PUthE R Ot3TH RJTOstPAntL tY79 OtSTR!OUTION PAfulL ty14 1
d
, v.
480V haCC t$831 480tr MCC 75849 eacw asOC tess31 esmr 88(f war. asey escr t$se2 525 E OC E @
RPS M C 8FS M G 1
= = 480Vr?20V M = 41DVr12CV ,
inv r7 " 7' '
ses RPS -
I sc - Is G 48crt2S2ecV M M tryyt ~
j ll C814 SET A 13 Cata O SEf 8 %
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RPS CHANNEL A PANEL 1C71PDDS ,-
RPS CMAredL 8 PAreEt 9C7tP00;F
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c sed RTE R CAD *E T C ;
i I
12.rao VAc treesrE ampf a E P(m a
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OESTEMikJTEMPAREL 9779 Figure 3.5-9. Grand Gulf 1 120 VAC Uninterruptible Electrical Power Distribution System '
)
y Table 3.5-1. Grand Gulf 1 Electric Power System Data Summary for Selected Components i COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG.
TYPE LOs y TROM LOAD GRP.
DG-018A MOV DGRMA EP-MCC-15611 480 SGRM1 .-9 ADA DG-0188 MOV DGFVJB EP-MCC-16811 480 SGRM119-10 AC/B ,
EP-BS-15AA BUS SWGR15AA EP-DG-11 4160 DGIUJA AQA EP- BS-15AA BUS SV.GR15AA OFFSITE 4160 AQA EP-BS-15BA1 BUS SGRM119-9 IR-15PA1 480 SGRM119-9 AQA EP-BS-15BA3 BUS SGRM119-9 TR-2A91 480 SGRM119-9 ADA EP-BS-15BA6 BUS SWGR15AA T R-15PA6 480 SWGR15AA AC/A EP-BS-16AB BbS SWGR16AB EP-DG-12 4160 DGFUJB ACB EP-BS-16AB BUS SWGR16AB OFFSIT E 4160 AC/B 4
EP-BS-16BB1 BUS SGRM119-10 T R-16PB1 480 SGRM119-10 ACB EP-BS-16BB3 BUS SGRM119-10 T R-16PB3 480 SGRM119-10 ACB u
o EP-BS-16BB6 BUS SWGR16AB TR-16PB6 480 SWGR16AB AC/B EP-BS-17AC BUS SWGR17AC EP-DG-13 4160 DGFVAC AC/C EP-BS-17AC BUS SWGR17AC OFFSITE 4160 AOC EP-BS-17801 BUS SWGR17AC TR-17P01 480 SWGR17AC ACC EP-B T-11 DA BATT BIRMD1 125 C01 EP-B T-11DB BATT BIRMD2 125 DC/2 EP-BT-11 DC BATT BTRMD3 125 DC3 EP-CB-C15AA CB SWGR15AA EP-DG-11 4160 DGRMA AC/A EP-CB-C16AB CB SWGH16AB EP-DG-12 4160 DGRMB AC/B EP-CB-C17AC CB SWGR17AC EP-DG-13 4160 DGFVAC AGC EF-DC-1 DA2 PNL SGRM119-7 EP-DCMCC-11DA 125 SWGR15AA DQ1 EP-DC-1 DA4 Iru SWGR15AA EP-BS-15BA6 480 SWGR15AA 001 EP-DC-1 DAS Iru SWGR15AA ' EP-BS-15BA3 480 SGRM119-9 DQ1 EP-DC-1DB4 ITN SWGR16AB EP-BS-16BB6 480 SWGR16AB DC/2 EP-DC-1 DB5 IPN SWGR16AB EP-BS-16BB3 480 SGRM119-10 DC2 EP-DCMCC-11DA MCC SWGR15AA EP-DC-10A5 125 SWGR15AA DQt EP-DCMCC-11DA MCC SWGR15AA EP-DC-1 DA4 125 SWGR15AA DC/1
t Table 3.5-1. Grand Gulf 1 Electric Power System Data Summary i for Selected Components (Continued)
COMPONENT ID. COMP. LOCATION POWER SOURCE VOLTA GE POWER SOURCE EMERG.
l :
l TYPE LOCATION LOAD GRP.
EP-DCMCC-11DA - MCC SWGR15AA EP-DT-11DA 125 BIRMD1 DC/1 EP-DCMCC-11DB MCC SWGR16AB EP-DC-1DBS 125 SWGR16AB DQ2 EP-DCMCC-11DB MCC SWGR16AB EP-DC-1DB4 125 SWGR16AB DCr2 EP-DCMCC-11DB MCC' SWGR16AB EP-8 T-11DB 125 BIRMD2 DC/2 i EP-DCMCC-11 DC MCC DGFNC EP-DC-1DC4 125 SWGR17AC DC/3 '
EP-DCMCC-11DC MCC DGFNC EP-BT-11DC 125 8IRMD3 DC/3
, EP-DG-11. DG DGFMA 4160 ACIA I EP-DG-12. DG DGRMB 4160. AC/B EP-DG-13 DG DGFMC 4160 ACC EP-MCC-15811 MCC- SGRM119-9 EP-BS-15BA1 480 SGRM119-9 AC/A EP-MCC-15831 MCC. SGRM119-7 EP-BS-15BA3 480 SGRM119-9 AC/A O- EP-MCC-15861 ~ MCC SWGR15AA EP-BS-15BA6 480 SWGR15AA AC/A EP-MCC-16811 MCC SGRM119-10 EP-BS-16BB1 480 SGRM119-10 AC/B EP-MCC-16B31 MCC SGRM119-8 EP-BS-16BB3 480 SGRM119-10 AQB EP-MCC-16B61 MCC SWGR16AB EP-BS-16BB6 480 SWGR16AB AC/B EP-MCC-17811 MCC SWGR17AC - EP-BS-17801 480 SWGRf 7AC AC/C EP-TR-15PA1 TRAN SWGR15AA EP-BS-15AA 480 SWGR15AA . AQA ;
EP-TR-15PA6 TRAN SWGR15AA EP-BS-15AA 480 SWGR15AA AC/A -
EP-TR-16PB1 TRAN SWGR16AB EP-BS-16AB 483 SWGR16AB AQB
- EP-TR-16PB3 TRAN SWGR16AB EP-BS-16AB 480 SWGR16AB i
AC/B '
EP-TR-16PB6 ' TRAN SWGR16AB EP-BS-16AB 480 SWGR16AB AC/B -
EP-T R-17P01 TRAN. SWGR17AC EP-BS-17AC 480 SWGR17AC AC/C EP-TR-2A91 IRAN : SWGH15AA EP-BS-15AA 480 SWGP15AA ' AC/A e
._~ - . . _ - . - . . . . .. - ~ . - - -- . - . - . - . . - . . - . . - - . .
TABLE 3.5 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT ORAND OULF 1 1 POWER VOL T AGE EMERG POWER SOVHCE LOAD LOAD COMP COMPONE NT SOURCE LCAD GRP LOCATION SYSTEM COMPONENT ID TYPE LOCATION EP OS 16AA 4160 AC, A bwGR16AA ECCS LPCS P1 MDP LPCSRM EP bS 16AA 4160 AC/A SWGR16AA ECCS RHR-CQQ2A MDP RHRRN%
EP-BS 16AA 400 AC/A SWGR15AA EP EP TR 16PA) TRAN bWGR15AA EP bS-16AA 480 AC/A SWGR15AA EP EP TR 15PA6 T RAN' SWGR15AA EP BS 16AA 480 AC/A S WGR 15AA EP EP TR 2A91 TRAN SWGR t5AA EP BS 16AA 4160 AC/A SWGK16AA SSW S$W C001A MDP BASINA EP BS 16BA1 480 AC/A SGRM119 9 EP EP.MCC 16Bl . ACC SGRM119 9 1
. EP BS 16BA3 480 DC/1 SGRM119 9 EP EP DC 1DAS INV SWGR16AA EP BS-16BA3 480 AC/A LGRM119 9 EP EP MCC 1683 MCC SGRM119 7 1
EP BS 16BA6 480 DC/1 SWGR16AA EP EP DC 10A4 INV SWGR16AA ip BS 1'.* BA6 400 AC, A SWGR16AA EP EP MCC 1506 ECC SWGR16AA 1
EP BS 16AB 4160 MCiB SWGR16AB ECCS RNR C002B MDP RHRRMB EP BS-16AB 4160 AC/B SWGRt6AB ECCS RMR-C002C MDP RHRAMC EP BS 16AB 480 AC/D SWGR16AB EP EP TR 16PB1 TRAN SWGR16A$
'. EP BS 16AB 480 AC/B SWGR16AB EP EP TR 16PB3 TRAN SWGR16AP EP BS 16AB 480 AC B bWGR16AB EP EP TR 16PB6 TRAN SviNAB EP BS 16AB 4160 AC/6 $WGR16AB S$W SSW 00010 MDP i'695$
EP BS 16BB1 480 AC<B 'SGRM11910 EP EP MCC 1681 MCC SblM11910 1
EP BS 16BB3 400 DC/2 SGRM11910 EP EP DC 1DB6 INV SWGR16AB EP BS 16BB3 400 AC/B SGRM11910 EP EP MCC 16B3 MCC SGRM119-6 1
EP BS 16BB6 480 DC/2 SWGR16AB EP EP DC IDR4 INV SWGR16AB EP BS 16BB6 400 AC/D SWGR16AB EP EP MCC 16D6 MCC SWGR16AB 1
EP BS 17AC 4160 AC/C SWGRi?AC ECCS HPCS P1 MDP hPCSRM EP BS 17AC 480 AC/C SWGR17AC EP EP TR-17P01 TRAN SWGR17AC EP BS 17801 480 AC/C SWGR17AC EP EP MCC 1781 MCC SWGR17AC 1
EP BS 17001 480 AC/C SWGR17AC SSW SSW C002C MDP BASINA EP BT 110A 125 DC/1 BTRMD1 EP EP DCMCC-11 MCC SWGR15AA DA EP-BT 11DB 125 DC/2 BTRMD2 EP EP DCMCC 11 MCC SWGR16AB OB' EP BT 1100 125 DC/3 BTRMD3 EP EP DCMCC 11 MCC DGRMC DC EP.DC 1DA2 125 DC/1 SGRM119 7 RCiG RCIC-10A MOV RCICRM EP DC 1DA2 125 DC/1 SGRM119 7 RCIC RCIC 13A MOV RCICRM
-58 'N l
TABLE 3.5 2. PARTIAL, LISTING OF ELECTRICAL SOURCES AND LOADS AT ORAND OULF 1 (CONTINUED)
POWER ' VOLTAGE EMERG POWER SOURCE LOAD LOAD COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENTID TYPE LOCATION EP DC 1DA2 125 DC/1 SGRM119 7 RCic RCIC IDA MOV RC4CRM EP DC 1DA2 125 En SGRM11b7 RCIC RCIC 31 A MOV RCICRM EP DC1DA2 125 DC/1 SGRM119 7 RClO RCiG-46A MOV RCiCRM
~E F DC IDA4 125 DC/1 SWGR15AA EP EP DCMCC 11 MCC SWGR15AA
~- DA EP DC IDAb ' 125 DC/1 SWGR15AA EP EP DCMCC 11 WC SWGR15AA DA EP DC IDB4 125 DC/2 SWGR16AB EP EP DCM0011 MCC SWGR16AB DB EP DC 1DBS 125 DC/2 SWGR16AB EP EP-DCMCC 11 MCC SWGR16AB DB EP DC IDC4 125 DC/3 SWGR17AC EP EP DCMCC 11 MCC DGRMC DC EP DCMCC 11 125 DC/1 SWG415AA EP EP DC 10A2 PNL SGRM119 7 DA EP DCMCC 11 125 DCil SWGR15AA RCIC RCIC 22A MOV RCICRM DA EP-DCMCC 11 125 DC/1 SWGR15AA RCIC RCIC-45A MOV AC4CRM DA EP DCMCC 11 125 DC/1 SWGRISAA RCiG RCIC 59A MOV ~ RCICRM DA EP DG 11 4160 AC/A DGRMA EP EP BS 15AA BUS SWGR16AA EP DG 11 4160 AC/A DGRMA EP E P-CB-C 15AA CB SWGR15AA EP DG 12 4160 AC/B DGRMB EP EP PS 16AB BUS SWGR 16AO EP DG 12 4160 AC/B DGRMB EP EP-CErC 16AB CD SWGR16AB EP-DG-13 4160 AC/C DG WC EP EP BS-17AC BUS SWGR17AC EP DG 13 4160 AC/C DG.'WC EP EP CB-017AC CB SWGR17AC EP MCC 1581 480 AC/A SOM119 9 ECCS LPCS-12A t MOV LPCSAM EP MCC 15B1 480 AC/A SGRM119 9 EWS LPCS-1 A 1
MOV LPCSRM EP MCC-1581 480 AC/A SGRM119-9 ECCS LPCS 5A t MOV FF,NRMA220 EP MCC 1501 480 AC/A SGRM119 9 EP 1
DG-018A MOV DG3MA EF.MCC 1581 480 AC/A SGRM119 9 RCS RCS 250A 1
MOV RC EP MCC-16B3 480 AC/A SGRM119 7 ECCS RHR 24A MOV RHRRMA 1
EP MCC 1583 480 AC/A SGRM119 7 ECCS RHR 24A i
MOV RHRRMA EP MCC 15B3 480 AC/A SGRM119 7 ECCS RHR 27A 1
MOV FHRAMA EP MCC 1583 480 ACiA SGRM119 7 ECCS RHR 27A 1
MOV RHRRMA EP MCC 15B3 480 AC<A SGRM119 7 ECCS 1
RHR 28A MOV RC EP MCC 1583 480 AC/A SGAM119-7 ECCS RHR 28A 1
MOV RC EP MCC 1583 480 AC/A SGRM119 7 ECCS RHR 37A t
MOV RC 7 MCC 1583 480 AC/A SGRM119 7 ECCS RHR 3A - MOV RHRRMA V
59 1/89
_ _ - - . - . . . - . ~ . - - . . _ - - . ~ . - . . ._. _.-- _ ...- .- -. --~..-. - - _ - _ .-
i TABLE 3.5 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS AT ORAND OULF 1 (CONTINUED) 4
~
POWER YOLTAGE EMERG POWER SOURCE LOAD LOAD CCMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMPONENT fD TYPE LOCATION EP MCC 16B3 480 AC/A bGRM119 7 ECCS RHR 42A MOV RC 1
EP MCC 16b3 480 AC/A SGRM1'9 7 ECC8 RHR 47A MOV RHRRMA 1
EP MCC 15B3 480 AC/A SGRM119 7 ECCS RHR4A MOV RHRAMA 1
EP MCC 1683 460 AC/A SGAM119 7 ECCS RHR-62A MOV RHRAMA 1
EP.MCC 15B3 480 AC/A SGRM119 7 ECCS RHR 63A MOV RHRRMA 1
EP MCC 16B3 480 AC/A SGRM119 7 ECCS RHR 63A MOV RHRAMA 1
EP MCC 1563 480 AciA SGRM119 7 ECCS RHR 6A MOV RHRRMA 1
~
l EP MCC 16B3 480 AC/A SGRM119 7 GCCS RHR 87A MOV RHRRMA 1
EP MCC 1583 400 AC/A SGRM119 7 ECCP > 4R46A MOV RHRAMA 1
EP MCC 1663 480 AC/A SGRM119 7 RCIC RCIG 64A MOV RJCRM 1
EP MCC 16B3 480 AC/A SORM119 7 RCS RCIC 64A MOV RCICRM 1
EP MCC IbB3 480 AC/A SGRM119 7 RCS RHR-8A MOV RHRRMA 1
EP MCC 16B3 480 AC/A SGAM119 7 SSW SSW 001 A MOV BASINA 1
EP MCC 1683 480 AC/A SGRM119 7- SSW $$W 006A MOV BASINA i
1 EP MCC 15B3 480 AC/A SGRM119 7 SSW SSW 006B MOV BASINB l EP MCC 1683 480 AC/A SGRM119 7 SSW- SSW 014A MOV 93AB t
EP MCC 16B3 480 AC/A SGRMl19 7 SSW SSW 014A MOV 93AB 1
EP MCC 16B3 480 Ad!A SGRM119 7 SSW SSW.068A MOV W3AB l 1 l EP MCC 16BI 480 AC/B SGRM11910 ECCS RHR 2tB MOV l 1 RHRRMC l EP MCC-1681 480 AC/B SGRM11910 ECCS RHR 420 -
1 MOV RHRRMC EP MCC 1681 480 AC/B SGRM11910 ECCS RHR4C MOV 1
RHRRMC EP MCC 1681 480 AC/B - SGRM11910 EP 0G 0188-1 MOV- OGRMB-EP MCC-1663 480 AC/B SGRM119-8 ECCS RHR-24B MOV 1
RHRRMB EP MCC 16B3 480 AC/B SGRM119-8 ECCS RHR 24B MOV 1
RHRAMB EP MCC-1683 480 AC/B SGRM119 8 ECCS RHR 27B MOV RHRRMB 1
EP MCC 16B3 480 AC/B SGRM119-4 ECCS RHR 270 MOV 1
RHRRMB-
~
EP MCC 16B3 480 AC/B SGRM119 4 ECCS RHR 268 MOV RC t
EP MCC 1683 480 AC/B SGRM119-8 EC( S RHR 288 MOV RC 1
EP-Mcc 1683 480 AC/B SGRM119-8 ECCS RHR 378 = MOV RC-1 EP MCO 16B3 480 AC/B SGAM119 8 ECCS RHR 38 - MOV. RHRAMB 1
EP MCC 1683 480 AC/B SGRM119 8 ECCS RHR 42B MOV RC 1
60 1/89
_ . . . _ . _ . _ _ ~ _ . _ _ _ . _ _ ... _ .._ .. _ _ _ _ . _ _ . . _ _
4 TABLE 3.5 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND l.OADS AT ORAND QULF 1 (CONTINUED) i POWER VOLTAGE EMERG POWER SOURCE LOAD LOC COMP COMPONENT SOURCE LOAD GRP LOCATION SYSTEM COMP
EP MCC 16B3 480 AC< B SGAM119 8 ECCS RHR 480 MOV RHRRMB i
EP-MCC 16B3 480 AC/B SGRM11W4 ECCS RHR 480 MOV RHRAMB t
EP MCC-16B3 460 ACiB SGAM119-8 SSW SSW-001B MOV 1
BASINB EP MCC-1683 480 AC/B SGAM119-8 SSW SSW 0068 MOV t BASINB EP MCC 1603 480 AC/B SGRM1194 SSW SSW 006A MOV 1
BASINA EP MCC 16B3 480 AC/B SGRM119-8 SSW SSW 014B MOV 1
93AB EP MCC 1683 480 AC/B SGRM i194 SSW SSW 014B 1
MOV 93AB EP MCC 1683 480 AC/B SGRMt 194 SSW SSW 068B i
MOV 93AB EP MCC 1781 480 AC/C SWOR17AC ECCS HPCS 1 t MOV HPCSAM EP MCC 1781 480 - AC/C SWGRi?F ECCS HPCS 10 i
MOV HPCSRM EP MCC 1181 480 AC/C SWGRt 7AC ECCS
, 1 HPCS-11 MOV HPCGAM EP MCC-17Bt 480 AC/C SWGR17AC ECCS HPCS 15 1
MOV HPCSRM EP MCC-1781 480 AC/C SWGR17AC ECCS HPCS 20 i MOV HPCSRM EP-MCC 1781 480 AC/C SWGR17AC - ECCS HPCS i i MOV 119 AB -
EP McC 1781 480 AC/C SWGR t TAC SSW SSW 011C t MOV BASINA EP MCC16B31 480 AC/A SGRM119 7 ECCS RHR 48A MOV RHRRM,A i
OFFSITE 4160 AC/A EP EP BS-ISAA BUS- SWGRILAA I j OFFSITE 4160 AC/B EP EP BS-16AB _ BUS, SWGR16AB -
1 OFFSITE 4160 AC/C EP EP BS 17AC . BUS SWGR17AC .
, 61 U89
_ . . . . . , _ _ . _ _ , .. ._ _ . _ . _ . _ - . _._....-._.-_._._.__...._.-.,-_....,a
l TABLE 3 5 2. PARTIAL LISTING OF ELECTRICAL SOURCES AND LOADS !
i AT ORAND OULF 1 (CONTINUED) ;
l POWER VOLTAGE EMERG PCWER boVROE LOAD LOAD COMP i COMPONLNT SOURCE LOAD GRP LOCATION SYSTEM COMDO.4ENT 10 TYPE LOCATION TR 15kA) 460 AC/A 7
$94M119 9 EP EP BS 15BA1 BUS LGRM1194 TR 16PA6 480 ACiA SWGR16AA EP EP BS 16BA6 BUS 'SWOR1bAA TR 10PB1 4BD ACiB SGRMt 7,0 gp EP 0516BB1 BUS SGRM11910 T R it PB3 440' ACiB $GRMtT910 EP CP BS 16BB3 BUS SGRuii9 io TR 16Pb6 460 AC< B SWGR16AB EP EP BS 16806 BUS 6WGR16AB IR 17P01 460 AC/C SWOR17AC EP EP BS 17B01 BUS SWGR17AC lR 2A91 400 AC/A SGRM119 9 EP EP BS 16BA3 BUS SGRM119-9 i
l F'
x 62 1/89
Grand Gulf 1 3.6 CONTROL HOD DRIVE llYDRAULIC SYSTEM (CRDilS) 3.6,1 System Function
(' The CRDHS supplies pressurized water to operate and cool the control rod drive mechanisms during normal operation. This system implements a scram command from the reactor protection system (RPS) and drives control rods rapidly into the reactor.
The CRDilS also can provide makeup water to the RCS.
3.6.2 System Definition The CRDHS consists of two high head, low. flow CRD supply pumps, piping, filters, control valves, one hydraulic control unit for each control rod dnve mechanism, and instrumentation. Water is supplied from the condensate treatment system or the condensate storage tanks. The CRDHS also includes scram valves, scram accumulators, and a scram discharge volume.
Details of the scram ponion of typical BWR CRDHS is snown in Figure 3.6-1.
3,6,3 System Oneration During normal operation the CRDHS pumps provide a constant flow for drive mechanism cooling and system pressure stabilization. Excess water not used for cooling is discharged to the RCS. dontrol rods are driven in or out by the coordinated operation of the direction control valves. Insertlou speed is controlled by flow through the insert speed control valve. Rod motion may be either stepped or continuous.
A reactor scram is implemented by pneumatic scram valves in the CRDHS, An inlet scram valve opens to abgn the insert side of each control rod drive mechanism (CRDM) to the scram accumulator. An outlet scram valve opens to vent the opposite side of each CRDM to the scram discharge volume. This coordinated action results in rapid insertion of control rods into the reactor, p The control rod drive accumulators are necessary to scram the control rods x within the required time. It should be noted that each drive has an internal ball check valve which allows reactor pressure to be admitted under the drive piston, if reactor pressure is above 600 psi, the ball check valve ensures rod insertion in the event that the scram accumulator is not charged or the inlet scram valve fails to open. The insertion time, however, will be slower than the scram time with a properly functioning scram system.
Although not intended as a makeup system, the CRDHS can provide a source of cooling water to the RCS during vesselisolation. In BWR/6 plants, RCS makeup at high pressure is performed by the RCIC (see Section 3.2) and EPCS (see Section 3.3) systems. The maximum RCS makeup rate of the CRDHS is about 165 gpm with both pumps operating (Ref.1).
1.6.4 System Success Criterin For the scram function to be accomplished, the following actions must occur in tha CRDHS:
A scram &nal must be transmitted by the RPS to the actuated devices (i.e.,
pilot valves)!n the CRDHS.
The pneumatio inlet scram valve and outlet scram valve must open in the hydraulic costrol units (HCUs) for the individual control rod drives. This is accomplbned by venting the instrument air supply to each valve as follows:
Born scram pilot valves in each HCU must be deenergized, or Either backup scram pilot valve must be ,rgized.
A high pressure water source must be available from the scram accumulator in eeh HCU.
A b'drMic wnt path to the scram discharge volume must be available and
' (m
\
suftWent collection volume must exist in the scram discharge volume.
63 1/89
Grand Gulf 1 A specified number of control rods must res core (specific number needed is not known) ponds and insert into the reactor 3.6.5 comoonent information A. Control rod drive pumps (2)
' 1. Rated capacity: 100% (for control rod drive function)
- 2. Type: centrifugal D. Condensate Storage Tank
- 1. Capacity: 300,000 gal C. Scram Accumulator
- 1. Normalpressure: 1750 psig D. Scram Discharge Volume
- 1. Nonnalpressure: Atmospheric 3.6.6 Suonort Systems and Intetfaggs A. Control Signals
- 1. Automatic The RPS transmits scram commands to solenoid pilot valves which control the pneumatic scram valves
- 2. Remote Manual
- a. A reactor scram can be initiated manually from the control room ^
- b. The CRDilS c9n be operated manually from the control room to insert and withdraw rods, or to inject water into the RCS B. Motive Power
- 1. The control rod drive pumps are Class IE AC loads that can be supplied from the emergency diesel generator as described in Section 3.5.
3.6.7 VA A Model of the CRDIIS The CRDHS was not explicitly included in the VAA model. The CRD hydraulic control units, scram valves, and scram dischar reactor containment (area RC). As discussed in Section 4, this3.ge area volume is included areinlocated the- in the area transform for the tractor protection system (event RPS D). No credit is taken for the makeup capability of the CRDHS.
3,6,8 Section 3.6 - Rercrences 1, Drouin, Mary, T. et al., " Analysis of Core Damage Frequency from Internal-Events: Grand Gulf 1, "NUREG/CR 4550, Sandia National Laboratories, April,1987.
O c-64 1/89 e
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_,, - - m. -l l w+ , mwm} vnam OTHE R NCLrs 100TM 4 HCtts ' j HvonAcuc ConToot tweT (TvPacau l Cm e Figure 3.6-1. Simplified Diagram Of Portions Of The Coni.us Rod Drive Hydraulic System That Are Related To The Scram Function
I Grand Gulf 1 3.7 SilUTDOWN SERVICE WATER SYSTEM (SSWS) 3.7.1 System Function i The Shutdown Service Water System provides cooling water from the ultimate heat sink to various heat loads in the plant required for safe shutdown. The SSWS completes the decay heat transfer path from the RIIR system to the ultimate heat sink. Train B of the SSWS also can be aligned to supply water to the RHR system for low pressure core flooding if needed. 3.7.2 System Definition The SSW system consists of three separate trains, euch containing vae motor driven pump and distribution pipin it serving the heat loads assigned to that train, Simplified drawings of the three SSWS trains are shown in Fi;;ures 3.7-1 to 3.7 6. A summary of data on selected SSWS components is presented in Ta sle 3.71. 3.7.3 System Oneration The SSWS pumps normally are shut down, and heat loads in the SSWS are supplied with cooling water via interties with the plant service water (PSWS). The SSWS operates only during reactor shutdown, reactor Lsolation, and post LOCA. The pumps draw water from the SSW cooling towers, which serve as the ultimate heat sink. SSWS trains A and B can be cross-connected to each other. SSWS train C is dedicated to serving heat loads associated with the HPCS, and is not cross connected with the other SSWS trains. When the SSWS is automatically actuated, the pumpt :ne staned a.sd the intenie line with the PSW system is isolated. 3.7.4 System Success Crlierta , The success enteria for the SSWS are defined on a per train basis. For each l train of the SSWS, the SSW pump must operate, the intertie between the SSWS and the PSWS must be isc, lated, and the flow paths to the various heat loads must be open, j 3.7.5 Comnonent Information l A. Shutdown Service Water, Divisions I and II
- 1. Rated flow: 12,000 gpm @ 220 ft. head (95 psid)
- 2. Rated capacity: 100 %
- 3. Type: verticalcentrifugal B. Shutdown Service Water Pump, Division 111
- 1. Rated flow: 1,300 gpm @ 175 ft head (76 psid) -
, 2. Rated capacity: 1004
- 3. Type: verticalcentrifugal
! 3.7.6 Sunnort Systems and Interfaces l A. Control Signals 1 1. Automatic Upon receipt of a LOCA or loss of offsite power signal, all cocling tower fans, SSW pumps, and HPCS service water pumps will start. At the same ' time, the plant service water lines to the standby service water components that are required durinn normal operation are isolated automatically, and the respective SSW system lines are opened to those components. 66 1/89
. _ _ _ - ~ ~ _ _ . - _ _ _. . .
Grand Gulf 1
- 2. Remote manual O The SSW pumps can be actuated by remote manual means from the vntrol room.
t ' ] i B. Motive Power . . b The SSW pumps are Class 1E AC loads that can be supplied from the standby - diesel generators as described in Section 3.5. C. Pump Cooling and Pump Room Cooling Cooling water is diverted from the SSWS supply header to provide cooling _ water for the beanngs of the respective SSWS pump, r.nd for the SSWS rcom - ccoler, a
'{
3,7.7 Section 3.7 - References - !,
- 1. Drouin, Mary T. et al., " Analysis' of Core Frequency from Internal Events: '
Grand Gulf 1/' NUREG/CR-4550, Sandia National Laboratories, April,1987. - _ 1 l. h. L
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estST L&wafK.e .h Figure 3.7-3. Grand Gulf 1 Shutdown Service Water System, Train B k, '
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l 71 1/89
~
b I I ' HPCS DESEL 185A t GENERATORJACKET WATER COOLER M 186A i STANDBY 3 r TO STAND 8Y SETWCE ' ' &' -
. HPCS DESEL GENERATORJACKET SERVCE WATER . WATER COOLER A R 12 13 1858 186B BASIN A g J SSW of1C COOLNG SSW C002-C FROM TOWER STANDBY SERvCE WATER FROM STAND 8Y r ,
6^ 4 SEWEE WA . HPCS ROOM COOLER t 108 .19 $4 ( ,g ~
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- . e-1
' Figure 3.7-5. Grand Gulf 1 Shutdown Service Water System, Train C 4
I' t 4 -
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. m< -
m . . . ~ . . - - . - - . - - . - - -- - - - - l YARD DGRMC YARD
-l l
'Y HPCS OfESEL 1185A :;- t GENEPATORJACKET WATER COOLER J
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e (l BASIN A l- . I i co e j Figure. 3.7-6. Grand Gulf 1 Shutdown Service Water System, Train C ! i Showing. Component Locations
-~ . . . . .
. , . f
( \
- Table 3.7-1. '
Grand Gc:i 1 Shutdown Service Water System Data Summary for Selected Components l E
= COMPONENT ID COMP. LOCATION POWER SOURCE VOLTAGE POWER SOURCE EMERG.
? TYPE LOCATION LOAD GRP. ;
- SSW-001 A _MOV BASINA - EP-MCC-15831 480 SGRM119-7 AC/A I
SSW-0018 MOV BASINB EP-MCC-16B31 480 SGRM119-8 AC/B l- SSW-005A MOV BASINA EP-MCC-15B31 480 SGRM119-7 AC/A
- SSW-0058 MOV- BASINB EP-MCC-16831 480 SGRM119-8 AC/B 6
- . SSW-006A MOV BASINA EP-MCC-16831 480 SGRM119-8 AC/B
- SSW-0038 MOV BASINB EP-MCC-15B31 480 SGRM119-7 AC/A SSW-011C MOV GASINA EP-MCC-17B11 480 SWGR17AC AC/C i SSW-014 A MOV 93AB EP-MCC-15831 480 SGRM119-7 AC/A SSW-01' A MOV 93AB EP-MCC-15831 480 SGRM119 ' AC/A
[ SSW-014 B MOV 93AB 'EP-MCC-16831 480. SGRM119-8 AC/B SSW-0148 MOV 93AB. EP-MCC-1SB31 480 SGRM119-8 , AC/B Y SSW-068A MOV- 93AB EP-MCC-15B31 460 SGRM119-7 AC/A i 5 SSW-0688 . MOV 93AB. EP-MCC-16831 480 SGRM119-8 AC/B SSW-C001A MDP BASINA EP-BS-15AA 4160 SWGR15AA AC/A $ SSW-C0018 ' MDP BASINB EP-BS-16AB 4160 SWGR16AB AC/B g SSW-C002C - MDP BASINA EP-BS-17801 480 SWGR17AC AC/C
- i s
{ N 7
$. I I.
- i
'l
Grand Gulf 1
- 4. PLANT INFORMATION b 4.1 SITE AND BUILDING
SUMMARY
The Grand Gulf I site is located in Clairbc.ae County, Mississippi on the east side of the Mississippi River approximately 25 miles south of Vicksburg and 37 miles north nonheast of Natchez, Mississippi. The site contains a single 3WR/6 plant. The second unit planned for the site is on indefinite hold. A genero4 view of the site is shown in Figure 4 1 (from Ref.1) and a more detailed site plan is shov n ii Nure 4-2. The containment building is surrounc;ed by the. auxil , building. The spent fuel storage pool, HPCS, RCIC, LPCS, LPCI (RRR), P.ad reactor water cleanup systems are located on various elevations of the auxiliary butiding. Personnel airlocks for entering containment are on the 119 and 208 foot elevation of the auxiliary building.
'fo the west of the auxiliary building is the dieni generator building. Diesel generators 11,12, and 13 are located in separate rooms on the 132 ft, elevation of the diesel generator building. Long-term fuel tanks are located underground.
To the north of the auxiliary building is the contrM building. The control room is located on the 166 ft elevation of the control euilding between the lower cable spreading room on the 148 ft. level and it - ;'er cable wre' ding Oom or d:e 189 ft level. On the 111 ft elevation of the control a a it, the elect, power distribution equipment for all AC and DC divisions. The turbine building o. located on the east side of the auxiliary and control building. The switchyard is located fw ther to the east. The condensate storage tank (CST) is located just south of auxiliary building and the firewater pump house is !ccated southwest of the CST. Note that Grand Gutt v .ts originally planned as a two unit plant, with some shared facilities in the control, diesel generator /HVAC, and radwaste buildings. The
- O dett' led layouts of these buildings in areas that would have used Unit 2 equipment and l Q systems are not known.
- 4.2 FACILITY LAYOUT DRAWINGS Figures 4-3 through 4-17 are section views and simplified layout drawings of l the Grand Gulf 1 reactor building, auxiliary building, control building, diesel generator, l
and cooling tower basin and pumphouse. Some outiying buildings are not shown in these drawings. Major rooms, stairways, elevators, and doorways are shown in the simplified layout drawings, however, ma7 interior walls have been omitted for clarity. Labels printed in uppercase correspond to the location codes listed in Table 41 and used in the component data listings and system drawings in Section 3. Some additionallabels are included for information and are printed in lowercase type. A "a q of components by location is presented in Table 4-2. Components included in i dt a 2 are those found m the system data tables in Section 3, therefore this table is only c p 6 J listing of the components and equipment that are located in a particular room or area of the plant.
- 4. 3 SECTION 4 REFERENCES
- 1. Heddleson, F.A., " Design Data and Safety Features of Commercial Nuclear Power Plants.", ORNL NSIC-55, Volume III, Oak Ridge National Laboratory, Nuclear Safety Information Center, April 1974.
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Table 41. Definllion of Grand Gulf 1 Building and [3 Location Codes O Codes Descriotions
- 1. 93AB 93' elevation of the Auxiliary Building
- 2. I19AB 119' elevation of the Auxiliary Building
- 3. 139AB 139' elevation of the Auxiliary Building
- 4. 148CSRM Cable Spreading Room, located at the 148' elevation of the Control Building
- 5. 189CSRM Cable Spreading Room, located at the 198' elevation of the Control Building
- 6. AUXSTMTUN Auxiliary Steam Tunnel, located on 140' elevation of Auxiliary Building - east side of Reactor Containment
- 7. BTRMD1 Battery Room Division I, located on the 11l' elevation of the Control Building
- 8. BTRMD2 Battery Room Division II, located on the 11i' elevation of the Control Building O
g
'y 9. BTRMD3 Battery Room Division III, located on the 11l' elevation of the Control Building
- 10. BASINA Basin A, located in the Standby Service Water Pumphouse
- 11. BASINB Basin B, located in the Standby Service Water Pumphouse
- 12. BZWAY Breeze Way - areas between Auxiliary Building and Diesel Generator Rooms (Pipe Chase just outside of Diesel Generator Rooms)
- 13. CR Control Room, located on the 166' elevation of the Control Building
- 14. CST Condensate Storage Tant located in the Yard Area - For Unit 1, the CSTis located south of the Auxiliary Building of Unit 1.
- 15. DGRMA Diesel Generator Room A, located in Diesel Generator Building
- 16. DGRMB Diesel Generator Room B, located in Diesel Generator Building
- 17. DGRMC Diesel Generator Room C, located in Diesel Generator Building
- 18. EHSDRM Emergency Hot Shutdown Room, located on the 11l' elevation of the Control Buildmg
( ) \ / 96 149
-_.._ mm - ~
1 l
.t i
Table 4-i. Definition of Grand Gulf 1 Building and L ( Location Codes (Continued) 4 i r Codes Descriotions '
- 19. HPCSRM High Pressure Core Spray Room, located on the 93' elevation of the Auxiliary Building
- 20. LPCSRM Low Pressure Core Spray Room, located on the 93' elevation of the Auxiliary Building
- 21. PENRMA220 I Penetration Room A220, located on the 119' elevation of the !
Auxiliary Building - west side of Reactor Containment . I I 22. PENRMI All6 Penetration Room 1 A116, located on the 93' elevation of the i l Auxiliary Building - west side of Reactor Containment . I I
- 23. RCICRM Reactor Core Isolation Cooling System Pump Room, located on i the 93' elevation of the Auxiliary Building - east side of the .
Reactor Containment i l ' l .24. RC Reactor Containment i
- 25. RHRRMA Residual Heat Removal System "A" Pump Room -located on the 93' elevation of the Auxiliary Building- east side of the Reactor Containment
- 27. RHRRMB Residual Heat Removal System "B" Pump Room , located on the 93' elevation of the Auxiliary Building - east side of the Reactor Containment
- 28. RHRRMC _ Residual Heat Removal System "C" Pump Room , located on the 93' elevation of the Auxiliary Building - west side of the Reactor Containment
- 29. SWGR15AA 4160V Switchgear 15AA Room, located on the 11l' elevation of the Control Building - houses Switchgear 15B A6, MCC 15B61, and DC Switchboard 11DA
- 30. SWGR16AB 4160V Switchgear 16AB Room, located on the 111' elevation of the Control Building - houses Switchgear 16BB6, MCC 16B61, and DC Switchboard 1IDB
- 31. SWGR17AC 4160V Switchgear 17AC Room, located on the 11l' elevation of the Control Building - houses MCC 17811 and MCC B01
- 32. SGRM119 9 480V Switchgear Room, located on the 119' elevation of the Auxiliary Building (Area 9)- houses MCC 15B11, Load Center
. ISBAl, and Load Center 15BA3 O
97 1/S9
. .._ _ . __ _ _ _ _ _ _ .. _ _.. _ _ _ _ _ ._._ . - _ _ ~ _ _ _
t Table 41. Definition of Grand Gulf 1 Building and l Location Codes (Continued) l Codes Descriptions
- 33. SGRM11910 480V Switchgear Room, located on the 119' elevation of the-Auxiliary Building (Area 10) - houses MCC 16Bil, Load' Center 16BB3, and Load Center 16BB1
- 34. SGRM19 7 480V Switchgear Room, located on the 119' elevation of the Auxiliary Building (Area .7) - ' houses MCC 15B31 and .
MCC15B42 l
- 35. SGRM119 8 480V - Switchgear Room, located on the 119' elevation of the Auxiliary Building (Area 8) - houses MCC B31 and .MCC 16B42
- 36. TLSF Spent Fuel Pool operating floor, located on the 208' elevation of the Auxiliary Building lO l
l l l-O 98 -1/89 i
-. w- / - - ~ . . _ , . . , , ...y,y,.my,, --,..,..,,w yy. ..-.y., m __s,. . , , , , . , . . . . ,- r ,-4*, - - . ,,
TABLE 4 2. PART;t.L LISTING OF COMPONENTS BY LOCATION AT GRAND GULF 1
\g LOCATION SYSTEM COMPONENT 10 COMP TYPE 119AB ECCS HPCS 4 MOV 93AB SSW SSW 014A MOV 93AB SSW SSW 0140 MOV 9JA8 SSW SSW-014A MOV 93AB SSW SSW 068A MOV 93AB SSW SSW 0148 MOV 93AB SSW SSW 0688 MOV BASINA SSW SSW 001 A MOV
( BAStNA SSW SSW 005A MOV BA$iNA SSW SSW-006A MOV BASINA S$W SSW C001 A MOP l BASiNA SSW SSW-011C MOV 8ASINA SSW SSW C002C MDP BAS.N B SSW SSW-0018 MOV
\ BASINB SSW SSW 0058 MOV BASIN 8 SSW SSW 0068 MOV
~
8ASIN8 SSW 6SW C0018 MOP BTRM01 EP EP-BT 110A BATT7 BTRM02 EP EP BT 1100 BATT BTRMO3 EP EP BT 11DC BATT CST ECCS CST TANK CST RCIC CST TANK OGRA% EP EP OG 11 OG OGAMA EP OG-018A MOV l DGRM8 EP EP OG-12 OG OGAM8 EP OG-0188 MOV DGRMC EP EP-0G 13 OG DGRMC EP EP-DCMCC 1100 MCC DGRMC EP EP DCMCC-1100 MCC HPCSRM ECCS HPCS1 MOV O-99 1/89
TABLE 4 2. PARTIAL LISTlHG OF COMPONENTS BY LOCATION AT GRAND GULF 1 (CONTINUED) 1 ( v ,/ LOCATION SYSTEM COMPONEN T 10 COMP TYPE nPCSRM ECCS HPCS 15 MOV HPCSAM ECCS HPCS 23 MOV HPCSRM ECCS HPCS 10 MOV HPCSRM ECCS HPCS 11 MOV HPCSAM ECCS HPCS P1 MOP ~ LPCSRM ECCS LPCS-1 A MOV LPCSRM ECCS LPCS 12A MOV LPCSRM ECCS LPCS-P1 MOP PENRMA220 ECCS LPCS-5A MOV RC ECCS SUPP POOL TANK RC ECCS SUPP POOL TANK RC ECCS SUPP POOL TANK RC ECCS RHR-42A MOV AC ECCS RHR-428 MOV ,[g N ECCS RHR-28A MOV \ RC ECCS RHR 288 MOV RC ECCS SUPP POOL TANK RC ECCS RHR-28A MOV RC ECCS RHR-37A MOV RC ECCS RHR-378 MOV RC ECCS RHR-28B MOV N RCiG SUPP POOL TANK RC RCiG RCIC-638 MOV RC RCS RCS-18 MOV RC RCS RCS-250A MOV f$ RCS RHR-90 MOV RC RCS RCS-168 MOV RC RCS RCIC-638 MOV RClGRM RCIC RC(C-10A MOV RCICRM RCC RCIC-31A MOV
/",
e V im us9
TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION AT GRAND GULF 1 (CONTINUED) O\ LOCATION SYST8iM COMPONEN T 10 COMP TYPE MICRM MIC RCIC-19A MOV RCICRM RCIC RCIC-22A MOV RCICRM NC RCIC-59A MOV RCICRM NC RCaC-13A MOV NICRM RCC RCIC-P1 TOP RCICP.M RCIC RCic-TTV MOV RCICRM RCIC RCIC-64A MOV RCaCRM RCC RCC-TGV HV RCICRM RCC RCIC-45A MOV ACICRM RCC RCIC-46A MOV RCICRM RCS ACIC-64A MOV
~
RHRAMA ECCS RHR-24A MOV RHRAN% ECCS RHR48A MOV RHRAMA ECCS RHR 3A MOV
\ RHRAMA ECCS RHR-87A MOV RNRRMA ECCS RHR 52A MOV RHRAMA ECCS RNR-27A MOV RHRAMA ECCS RHR 47A MOV RHRRMA ECCS RHR 53A MOV RHRRMA ECCS RHR 4A MOV RHRAN% ECCS RHR-6A MOV RHRAMA ECCS RHR-C002A MOP RNRAMA ECCS RHR-2/A MOV-W RAMA ECCS RH 4-53A MUV RHRRAM ECCS RHR 6001A HX RNRAMA ECCS RHR 48A MOV RHARNw ECCS RHR-24A MOV-RHRRMA ECCS RHR 8002A HX RHRRMA RCS RHR-6A MOV -
RNARM8 ECCS RHR 248 MOV [ v 101 1/$9
TABLE 4 2. PARTlAL LISTING OF COMPONENTS BY LOCATION AT GRAND GULF 1 'CONTINL,ED)
,FN \ LOCATION SYSTEM COMPONEN T IO COMP \
TYPE RMRAM8 ECCS RHR-488 MOV RMRRM8 ECC3 RHR-38 MOV RHRRMS ECGS RHR-878 MOV RMARMB ECCS RHR 528 MOV RMRRMB ECCS RHR-278 MOV RHRRMS ECCS RHR478 MOV RHRAM8 ECCS RNR 538 MOV RHARMB ECCS RHR 48 MOV RNRAM8 ECCS RHR-68 MOV RHRAMB ECCS RHR-C0028 MOP RHRRM8 ECCS RHR 538 MOV RHRRMB ECCS RHR-278 MOV RNRAM8 ECCS RHR 80018 M RHRAM8 ECCS RHR-488 MOV {O ( RHRAM8 ECCS RHR-248 MOV RHRAM8 ECCS RHR-8002B HX RNRAMC ECCS RHR-218 MOV RHRAMC ECCS RHR-4C MOV RHRRMC ECCS RHR42C MOV RNRAMC ECCS RHR-CW2C MOP SGRM11910 EP- EP BS-168B3 BUS l SGAM11910 EP EP BS 16881 OUS SGRM11910 EP EP MCC-16811 MCC i SGRM119-7 EP EP MCC-15M1 MCC SGRM119 7 EP EP-OC-10A2 PNL SG AM 119-8 EP EP MCC-16831 MCC SGRM 119-9 EP EP-BS 150A1 BUS SGRM119 9 EP EP BS-15BA3 BUS SGAM119 9 EP EP-MCC 15811 MCC SWGR15AA EP EP-BS 15AA BUS i O l l 1/89 102 i
TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION AT GRAND GULF 1 (CONTINUED)
\
t
\v/ LOCATION SYSTEM COMPONENT 10 COMP TYPE SWGR15AA EP EP CB-C15AA C8 SWGR15AA EP EP TR 15 pat TRAN SWGRISAA EP EP TR 2A91 TRAN SWGRISAA EP EP DCMCC 110A MCC SWGA15AA EP EP DC-10A4 (NV SWGR15AA EP EP DC IDAS INV SWGRtSAA EP EP TR 15PA6 TRAN
~
SWGR15AA EP EP BS 15BA6 OUS SWGR15AA EP EP-MCC 15B61 MCC SWGRISAA EP EP BS-15AA BUS SWGR15AA EP EP-DCMCC-11DA MCC SWGR15AA EP EP DCMCC-IIDA MCC SWGR16AS EP EP BS 16AB BUS SWGR16AB EP EP CB C16AB CB bg SWGR16AB EP EP TR 16PB3 TRAN SWGR16AB EP EP-TR 16P81 TRAN
~SWGR16AB EP EP 0CMCC-110B MCC SWGRt6AB EP EP DC 1C B4 INV SWGR16AB EP EP OC-1085 INV SWGR16AB EP EP TR 16P86 TRAN SWGR16A8 EP EP BS 16086 BUS
\ SWGR16AB - EP EP MCC-16861 MCC SWGR16AB EP EP BS-16AB BUS 1 SWGR16AB EP EP DCMCC-110B MCC 1 SWGR16AB EP EP DCMCC 1108 MCC SWGR17AC EP EP BS 17AC BUS SWGRI 7AC EP EP C8-017AC CD SWGR17AC EP EP 8S-17 Bot Bus SWGR17AC EP EP TR 17P01 TRAN SWGR17AC EP EP MCC-176',1 MCC b') r
\s 103 1/89
m -
- m. . ~ . - - . , s -.. ----a ,
TABLE 4 2. PARTIAL LISTING OF COMPONENTS BY LOCATION AT GRAND GULF 1 (CONTINUED) O LOCATION SYSTEM COMPONENilO COMP TYPE SWGR 17AC EP EP BS-17AC BUS k. l l l l 104 1/89
Grand Gulf 1
- 5. BIBLIOGRAPilY FOR GRAND GULF O) 5 V 1. NUREG 0777 " Environmental Statement Related to the Operation of the Grand Gulf Nuclear Station, Units 1 and 2", USNRC
- 2. NUREG 0831 " Safety Evaluation Report Related to the Operation of the Grand Gulf Nuclear Station, Units 1 and 2", USNRC 3 NUREG-0934 " Technical Specifications for Grand Gulf Nuclear Station, Unit 1", USNRC
- 4. NUREG/CR 0383 " Tornado Damage at the Granc' Gulf, Miss., Nuclear Power Plant Site: Aerial and Ground Surveys", Texas Tech. University and University of Chicago, October 1978 i 5. Cummings, J.C., et.al., " Review of the Grand Gulf Hydrogen Igniter System", NUREG/CR-2530, Sandia National Laboratories, March 1983
- 6. NUREG/CR-4550, Volume 6, " Analysis of Core Damage Frequency From Internal Events: Grand Gulf Unit 1", Sand!a National Laboratories and Science Applications International Corp., April 1987
- 7. NUREG/CR-4551, Volume 4, " Evaluation of Severe Accident Risks and the Poteatial for Risk Reduction: Grand Gulf Unit 1", Sandia National Laboratories and Science Applications International Corp., April 1987
- 8. NUREG/CR 4700, Volume 4, " Containment Event Analysis for Postulated l '\g Q Severe Accidents: Grand Gulf Unit 1", Sandia National Laboratories and Science Applications International Corp., April 1987 i
l (O a t 105 1/89
Grand Gulf 1 APPENDIX A DEFINITION OF SYMIlOLS USED IN THE SYSTEM AND LAYOUT DRAWINGS A 1. SYSTEM DRAWINGS A 1.1 Fluid System Drawings
- The simplified system drawings are accurate representations of the major flow paths in a system and the important interfaces with other fluid systems. As a general rule, small fluid lines that are not essential to the basic operation of the s these drawings. Lines of this type include instrumentation lines,istem vent lines, drain are not shown in lines, and other lines that are less than 1/3 the diameter of the connecting major flow path. There usually are two versions of each fluid system drawingt a simplified system drawing, and a comparable dewing showing component locations. The drawing conventions used in the j fluid system drawings are the following:
Flow generally is left to right. Water sources are located on the left and water " users" (i.e., heat loads) or discharge paths are located on the right. One exception is the return flow path in closed loop systems which is right to left. Another exception is the Reactor Coolant System (RCS) drawing which is
" vessel centered", with the primary loops on both sides of the vessel.
Horizontal lines always dominate and break vertical lines.- i Component symbols used in the fluid system drawings are defined in Figure ' A- 1. . 4 , Most valve and pump symbols are designed to allow the reader to distinguish among similar components based on their support system requirements (i.e., electric power for a motor or solenoid, steam to drive a turbine, pneumatic or hydraulic source for valve operation, etc.) Valve symbols allow the reader to distinguish among valves that allow flow- ' .in either direction, check (non return) valves, and valves that perform an overpressure protection function. No attempt has been made to define the specific type of valve (i.e., as a globe, gate, butterfly, or other specific type of valve).- Pump symbols distinguish between centrifugal and positive displacement-pumps and between types of pump drives (i.e., motor, turbine, or engine). 1 Locations are identified in terms of plant location codes defin6d in Section 4 of i this Sourcebook. 4 Location is indicated by shaded " zones" that are not intended to represent ' the actual room geometry. . _ Locations of discrete components represent the actual physical location of the component. Piping locations between discrete components represent the plant areas through which the pi underground pipe runs). ping passes (i.e. including pipe tunnels. and Component locations that are not known are indicated by placing the components in an unshaded (white) zone. The primary flow path in the system is highlighted (i.e., bold white line)in the location version of the fluid system drawings. j 106 1/89 4
Grand Gulf 1 A 1. 2 Electrical System Drawings 5 The electric power system drawings focus on the Class IE portions of the plant's electric power system, Separate drawings are provided for the AC and DC portions of the Class IE system. Thre often are two versions of each electrical system drawing; a simplified system drawing, and a comparable drawing showing component locations. The drawing conventions used in the electncal system drawings are the following: Flow generally is top to bottom In the AC power drawings, the interface with the switchyard and/or offsite grid is shown at the top of the drawing. In the DC power drawings, the batteries and the interface with the AC power system are shown at the top of the drawing. Vertical lines dominate and break horizontal lines. Component symbols used in the electrical system drawings are defined in Figure A 2, Locations are identified in terms of plant location codes defined in Section 4 of this Sourcebook. Locations are indicated by shaded " zones" that are not intended to represent the actual room geometry. Locations of discrete components represent the actual physical location of the component. The electrical connections (i.e., cable runs) between discrete components, as shown on the electrical system drawings, DO NOT represent the actual cable routing in the plant. Component locations that are not known are indicated by placing the ( discrete components in an unshaded (white) zone. A2. SITE AND LAYOUT DRAWINGS A 2.1 Site Drawings A general view of each reactor site and vicinity is presented along with a simpilfied site plan showing the arrangement of the major buildings, tanks, and other features of the site The general view of the reactor site is obtained from ORNL-NSIC-55 (Ref,1), The site drawings are approximately to scale, but should not be used to estimate distances on the site, As-built scale drawings should be consulted for this purpose, Labels printed in bold uppercase correspond to the location codes defined in Section 4 and used in the component data listings and system drawings in Section 3. Some additional labels are included for information and are pnnted in lowercase type. A 2.2 Layout Drawings Simplified building layout drawings are developed for the portions of the plant that contain components and systems that are described in Section 3 of this Sourcebook, Generally, the following buildings are included: reactor building, auxiliary bu.. Jing, fuel building, diesel building, and the intake structure or pumphouse. Layout drawings generally are not developed for other buildings, Symbols used in the simplified layout drawings are defined in Figure A-3 Major rooms, stairways, elevators, and doorways are shown in the simplified layo-b drawings however, many interior walls have been omitted for clarity. The building layout 107 1/89
, ,, ,,,e ~ **~ ' ^ ^
Grand Gulf I drawings, are approximately to scale, should not be used to estimate room size or distances. As built scale drawings for should be consulted his purpose, s Labels printed in uppercase bolded also correspond to the location codes [Q defined in Section 4 and used in the component data listings and system drawings in Section 3. Some additionallabels are included for information and are printed in lowercase type. A3. APPENDIX A REFERENCES
- 1. Heddleson, F.A., " Design Data and Safety Features of Commercial Nuclear Power Plants.", ORNL NSIC 55, Volumes 1 to 4 Oak Ridge National Laboratory, Nuclear Safety Information Center, December 1973 (Vol.1),
January 1972 (Vol. 2), April 1974 (Vol. 3), and March 19"'5 (Vol. 4) A l i i l l (D U 108 1/89 l , - -
l _LJ MANUAL V ALVE . XV __F' MANU AL NON RETURN __ (OP E N8C L OS E D) VALVE ICV (OPEN' CLOSED) 4 4 O _ MOTOR OPERATED VALVE MOV MOTOR OPER ATED _ (O P E NIC L O S E D) 3 WAY VALVE . MO\ (CLOSED PORT MAY V ARY) W
,_ _ SOLENOID-CPER ATED VALVE . 80V .
ROLENCID OPER ATED (O P E N /C LO S E D) 3 WAf VALVE , SOY (CLOSED PORT MAY V ARY) _ _ HYDRAULIC VALVE . HV _ H)DP AULIC NON RETURN (OPE N AC LOS E D) 4 4 VALVE HCV (OPEN' CLOSED) L PNEUMATIC VALVE . NV F' . PNEUMAllC NON RETURN (OPEN/ CLOSED) VALVE NCV (OPEN CLOSED) CHECK VALVE ,CV d SAFETY VALVE . SV (CLOSEC) Y O POWER OPER AT'ED REllEF VALVE, J SOLEN / IO PILOT TYPE PORV M POWER OPER ATED RELIEF VALVE. (CLOSED) PNEUMATICALs f OPER ATED . PORY OR DUAL FUNCTION S AFETYlRELIEF VALVE SRV (CLOsto) CENTRIFUQ AL CE NTR1700 AL MOTOR DRIVEN PUMP
- MOP TUR8INE DRIVEN PUMP . TDP
\ /
I
. POSITIVE DISPLACEMENT -
MOTOR DRIVEN PUMP . MDP POSITIVE DISPL ACEME N T TUR8INE DRIVEN PUMP
- TOP I
\ /
I O d Figure A-1. Key To Symbols in Fluid System Drawings 109 1/89
.- - . . - . - ~ . - . - . . .
=
PWR:BWR MAIN CONDENSER e COND RE ACTDR YESSEL . RV r w > Q -
- HEAT EXCHANGER e HX MECH ANICAL DR AFT COOLING TDWER STFAM TO WATER CR WATER TO 4 TEAM HEAT h "
AIR COOLING UNIT a ACU EXCHANGER (LE. FEEDWATER g HE ATER, DR AIN COOLER, ETC.) . HX C OR TANK =TK gaaoaaaa SPR AY NO2ZLES . SN ' V RUPTURE DISK = RD _ FILTER
- FLT ORIFICE OR
< Figure A-1. Key To Symbols in Fluid System Drawings (Continued) 110- 1/89 i
)
__m. . _ . . . . . _ _ _ . _ .~_.m..__... . _ . _ . . , - . ~ . ._ .......__....... - --..._ _.... _ __...__ _-.. _ _ ___... _. l l
- A.C. DIESEL CENER ATOR . DC B ATTERY . B ATT i OR A.C. TURBINE CENERATOR = TO l
i
^
I - OR l CIRCUIT OREAKER CB [ h g ( 3.. 11 OR 15 ..(3 INTERLOCKED (O P E NICLO S E D) circuli DRE AKERS C8 . 1 SWITCH . SW o AUTO M ATIC OR v OR OTHER TYPE OF TRANSFER SWITCH . ATS OlSCONNECT DEVICE OR (OPEN/ CLOSED) MANUAL TRANSFER SWITCH . MTS l SWITCHOE AR BUS . BUS { (BUS N AME) l MOTOR CONTROL CENTER MCC NN OR M "" TR ANSFORMER TRAN OR OtSTRIBUTION P ANEL PNL l i BATTERY CHAROER (RECTIFIER) . BC KZ INVERTER . INV I 1
~
OR RELAY CONTACTS FUSE .FS 7 (OPEN! CLOSED) - I
, EtECTRic MOTOR . MTR ,,,,,,,,,,,,,,,,,
4 l 111 W 4
j O STAIRS l 5 0=cown g SPIRAL STAIRCASE l LADDER ( U = Up D = Dewn ELEVATOR g HATCH OR OPEN AREA GRATING DECK (NO FLOOR) i ! -O- PERSONNEL DOOR +
- EQUIPMENT DOOR l
__ :( EE _5 h?lLROAD TRACKS :< FENCE LINE r 4 :< O TANK / WATER AREA i l 1-I- 4 Figure- A-3. Key To Symbols in Facility Layout Drawings O 112 1/89
Grand Gulf 1 APPENDIX B
\
DEFINITION OF TERMS USED IN TIIE DATA TABLES
- Terms appearing in the data tables in Sections 3 and 4 of this Sourcebook are defined as follows:
SYSTEM (also LOAD SYSTEM) All components associated with a particular system description in the Sourcebook have the same system code in the data base. System codes used in this Sourcebook are the following: Qxiq ! Definition RCS Reactor Coolant System RCIC Reactor Core Isolation Cooling System ECCS Emergency Core Cooling System (including HPCS, LPCS, LPCI,and ADS) I&C Instrumentation and Control Systems EP Electric Power System SW Shutdown Service Water System COMPONENT ID (also LOAD COMPONENT ID) The component identification (ID) code in a data table matches the component ID that appears in the corresponding system drawing. The component ID generally begins'with a system preface followed by a component number. The system preface is not necessarily the same as the system code described above. For component ids, the system preface corresponds to what the plant calls the component (e.g. HPI, RHR). An example is HPI-730, denoting valve number . O 730 in the high pressure injection system, which is part of the ECCS. The component number is a contraction of the com>onent number appearing in the plant piping and-instmmentation drawings (P& ids) anc electrical one line system drawings. LOCATION (also COMPONENT LOCATION and POWER SOURCE LOCATION) - Refer to the location codes defined in Section 4. COMPONENT TYPE (COMP TYPE)- Refer to Table B-1 for a list of component type codes. i POWER SOURCE - The component ID of the power source is listed in this field (see COMPONENT ID, above). In this data base, a " power source" for a particular component
- ~ (' ::. a load or a distribution component) is the next higher electrical distribution or generating component in a distribution system. A single component may have more than-one power source (i.e. a DC bus powered from a battery and a battery charger).
i POWER SOURCE VOLTAGE (also VOLTAGE)- The voltage "seen" by a load of a power source is entered in this field The downstream (output) voltage of a transformer, mverter, or battery charger is used. ! EMERGENCY LOAD GROUP (EMERG LOAD GROUP)- AC and DC load groups (or electrical divisions) are defined as appropriate to the alant Generally, AC load groups are identified'as AC/A', AC/B, etc. The emergency loac group for a third of a kind load - (i.e. a " swing" load) that can be powered from either of two AC load groups would be identified as AC/AB DCl oad group follows similar naming conventions. iO 'U 113 1/89 r -
, , ,r- , -w-w,. , , , , ., r,w--.-. ..,,,,-m+- -,,-ww,r**vs ev- w em
TABLEH1. COMPONENT TYPE CODES 4 L CO MPONENT COMP TYPE VALVES: Motor-operated valve MOV Pneumatic (air operated) valve NV or AOV Hydaulle valu HV Solenoid-operr(ed valve SOV Manual valve XV Check valve -CV Pneumatic non return valve NCV' Hydraulic non return valve HCV Safety valve SV Dual function safety / relief valve - SRV Power-operated rehef valve . PORY (pneumatic or solenoid-operated) i PUMPS: Motor driven pump (centrifugal or PD) MDP Turbine-driven pump (centrifugal of PD) TDP Diesel driven pump (centrifugal of PD) DDP OTHER FLUID SYSTEM COMPONENTS: Reactor vessel RV Steam generator (U-tube or once-through) SG , Heat exchanger (water to-water HX, HX-1 or water to air HX) Cooling tower CT Tank ' TANK or TK l Sump _ SUMP l Rupture disk RD l Orifice - ORIF Filter or strainer FLT Spray nozzle SN Heaters (i.e pressurizer heaters) HTR VENTILATION SYSTEM COMPONENTS: Fan (motor driven, any type) FAN. Air cooling unit (air to water HX, usually ACU or FCU including a fan) Condensing (air conditioning) unit COND '! ' EMERGENCY POWER SOURCES: Diesel generator DG
- - Gas turbine generator GT Battery BATT 114 1/89
TABLE B.1, COMPONENT TYPE CODES (Continued) , COMPONENT COMP TYPE ^ ELECTRIC POWER DISTRIBUTION EQUIPMENT: Bus or switchgear- BUS Motor control center MCC Distribution panel or cabinet PNL or CAB Transformer TRAN or XFMR Battery charger (rectifier) BC or RECT Inverter INV Uninterruptible oower supply (a unit that may UPS include battery, sattery charger, and inverter) Motor generator MG Circuit breaker CB Switch ' SW ' Automatic transfer switch -ATS Manual transfer switch MTS i
\
l l 4 O l 115 1/89 u I; .. . .- _. -_.-_.u.--. _ . . , . -, _ , _ _ . ..u . .- . _.,;..___,-,~..-...a- _ - - - - . - - . _ . ~ . , - - - - .}}