ML20044H355
| ML20044H355 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 06/02/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9306080230 | |
| Download: ML20044H355 (11) | |
Text
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GENuclear Energy Geocia!Eiectnc Cornpany 175 Curtner Avenue. San Jose. CA 95125 June 2,1993 Docket No. STN 52-001 Cnet Postusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation l
Subject:
Markup of Chapter 9 of the AinVR SSAR
Dear Chet:
These markups are the result of telephone conversations between W. F. Burton (NRC) and G. E. Miller (GE).
Sincerely, l
/
JNP Jack Fox
. Advanced Reactor Programs cc: G. E. Miller (GE)
Norman Fletcher (DOE) 9
$0 0
'h 93060B0230 930602 ADOCKOS2Og1 PDR.
A
1ABWR numu Standard Plant un UHS rnakeup ad blowdown volumes (if (4) Demineralized water shall be provided at a
. applicable) are indicnd by flow totalizers located minimum flow rate of approximately 600 gpm in the makeup and blowdown lines.
at a temperature between 50 to 100 F.
9.2.5.10 Tests and Inspections (Interface (5) The MWP system is not connected to any Requirements) systems having the potential for containing radioactive material.
j The COI applicant shall prepare and perform a preoperational test program and tests during (6) - The MWP system provides 200 gpm of filtered normal operations in accordance with the water to meet maximum anticipated peak requirements of Chapter 14.
demand periods for the Potable and Sanitary Water System.
INM N -
9.2.6 Condensate Storage Facilities
. FR 0^^N O
and Distribution System 9.2.83 System Description (Conceptual Design) f, The functions of the storing and distribution The MWP system consists of both mobile and of condensate are described in Subsection 9.2.9.
permanently installed water treatment systems.-
9.2.7 Plant Chilled Water Systems The permanently installed system consists of a well, filters, reverse osmosis modules and The functions of the plant chilled water demineralizers which preparc demineralized water.
system are performed by the systems described in from well water. The demineralized water is sent to Subsections 9.2.12 and 9.2.13.
- storage tanks untilit is needed. Pumps are provided to keep the makeup water distribution system 9.2.8 Makeup Water (MWP) System (MUWP) pressurized at all times. The components (Preparation) of the MWP system are listed in Table 9.2-15 and the system block flow diagram is in Figure 9.2-10.
This subsection provides a conceptual design of the makeup water preparation system as required While it is planned to install both permanent by 10CFR52. The interface requirements for this divisions, only one division may be installed if' plant system are part of the design certification.
water requirements and economic conditions
')
indicate that the second division will not be needed.
9.2.8.1 Safety Design Bases (Interface Requirements)
Mobile water treatment systemt will be used before the permanent system is installed and later if The MWP system has no safety related water requirements exceed the capacity of the function. Failure of the system does not permanent system or if economic condition make use compromise any safety-related system or compo-of mobile equipment attractive compared to operat-nent, nor does it prevent a safe shutdown of the ing and maintaining the permanent system.
plant.
9.2.83.1 Well System 9.2.8.2 Power Generation Design Bases (Interface Requirements)
A well, well water storage tank and two well water forwarding pumps are provided which can produce (1) The MWP system consists of two d:<isions ca-sufficient water to meet the concurrent needs of the pable of producing at least 200 gpm of makeup water preparation system and the potable L dcmineralized water each.
and sanitary water system.
(2) Storage of demineralized water shall be at least 200,000 gallons.
1 (3) The quality of the demineralized water shall meet the requirements in Table 9.2-2a.
j Amendment 23 9.21.5 m.
- m..
. ~.. -. -.
AB M 23A6100AH Standard Plant arv. s
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M (5) All tankerpumps, piping, and other equip-f(6) All pumps shall be located at an elevation
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ment shall be made of corrosion resistant such that adequate suction head is present
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l materials, at all levels in a purified water storage tanks.
(6) The system shall be designed to prevent any radioactive contamination of the purified (7) Instruments shall be provided to indicate water.
purified water storage tank level in the main control room.
j (7) The interfaces between the MUWP system and all safety related systems are located in (8) Continuous analyzers are located at the the control building or reator building demineralized water makeup system and-atany which are Seismic Category I, tornado-deminerelized-water-storage 4ank. These are missile resistant and flood protected supplemented as needed by grab samples.
structures. The interfaces with safety.
Allowance is made in the water quality related systems are safety-related valves specifications for some pickup of carbon which are part of the safety related dioxide and air in any demineralized water systems. The portions of the MUWP system, storage tank. The pickup of corrosion I which upon their failure during a seismic products should be minimal because the MUWP event can adversly impact structures, piping is stainless steel.
systems, or components important to safety, shall be designed to assure their integrity (9) Intrusion of radioactivity into the MUWP l under seismic loading resulting from a safe system from other potentially radioactive shutdown earthquake.
systems are prevented by one or more of the following:
(8) Safey related equipment located by portions of the MUWP system are in Seismic Category I (a) check valvesin the MUWPlines structures and protected from all system f
impact.
(b) air (or syphon) breaks in the MUWP lines 9.2.10.2 System Description (c) the MUWP system lines are pressurized while the receiving system is at The MUWP system P&ID is shown in Figure 9.2-5.
essentially atmospheric pressurc.
s l ' This system includes the following-g&f
-T (d) piping to the user is dead ended.
4 3
/( f Any purified water storage tank shall be) provided outdoors with adequate freezel (10)
There are no automatic valves in the j
protection and adequate diking and other MUWP system. During a LOCA, the y
means to control spill and leakage, safety-related systems are isolated from
.7 the MUWP system by automatic vr.lves in (2) Two MUWP forwarding pumps shall take suction the safety-related system.
from any purified water storage tgnks. They shall have a capacity of 7g.n /hr and aj 9.2.10.3 Safety Evaluation discharge head of 8 kg/cm.
/
Operation of the MUWP system is not required (3) Distribution piping, valves, instruments and to assute any of the following conditions:
controls shall be provided.
1 (1) integrity of the reactor coolant pressure (4) Any outdoor piping shall be protected from boundary; freezing.
(2) capability to shut down the reactor and (5) All surfaces coming in contact with the maintain it in a safe shutdown condition; or purified water shall be made of corro-sion-resistant materials.
Amendment 27 9.2-3
ABWR I
-mm Standard Plant anv n 9.2.11.3.2 Safety Evaluation of Equipment electrical equipment and instrumentation and controls as well as to mechanical equipment and Equipment served by the RCW system is listed piping):
in Tables 9.2-4a, b, and c.
The tables contain five operating modes:
(1) flooding, spraying, or steam release due to pipe rupture or equipment failure:
(1) normal operation; (2) pipe whip and jet forces resulting from pos-(2) shutdown at 4 hr; tulated pipe rupture of nearby high energy pipes; (3) shutdown at 20 hr.;
(3) missiles which may result from equipment (4) hot standby (No LOPP);
failure; (5) hot standby (LOPP): and (4) fire; and (6) post-LOCA.
(5) failures of any rion-Category I equipment (pertains to Scismic Category I equipment).
The flow rates and heat loads are given for each equipment in each operating mode.
Radiation monitors are provided to sample the RCW cooling water. Upon detection of radiation in the event of a LOCA, most of the nonessen-leak age in one of the systems, that system is tial cooling water uses are isolated by proper isolated by operator action from the control isolation valves. The instrument air system, room, and the total cooling load can be met by service air system, control rod drive pump oil the other two systems. Consequently, radio-cooler and the reactor water cleanup system pump active contamination released by the RCW system coolers remain in service until the operator to the environment does not exceed allowable removes them from service. The nonsafetynelated limits defined by 10CFR100.
portion of the system is automatically isolated in the event of a rupture in the nonsafety re-The safety-related parts of the RCW system lated subsystem. The surge tank water level is are designed to Seismic Category I and ASME monitored. A level switch is activated by a Code,Section III, Class 3, Quality Assurance B significant Icak, sending an isolation signal to and Quality Group C requirements. The design close two valves. One valve on the supply line also meets IEEE-279 and IEEE-308 requirements.
and one valve on the discharge line are used, Isolation valves for nonsafety-related service with suitable power and controls from divisional water systems also meet the above requirements.
sources to assure isolation in the event of any single active failure. Single isolation valves The nonessential portion of the RCW system is are used on the basis that an active failure of designed to the ANSI B31.1 Power Piping Code and one isolation valve disables only that system of the requirements of Quality Group D.
which it was a part.
A The desis# rressure endiemverature orthe 2
The RCW system is designed to withstand a RCW system and piping are 14 kg/cm g (200 single active failure without losing its capabi-psig) and 70 C (158 F) maximum.
lity to participate in the safe shutdown of the reactor following a LOCA or DBA. Table 9.2 5 System low point drains and high point vents gives the result of a system failure analysis of are provided as required, active and passive components.
All divisions are maintained full of water Redundant trains of the RCW system are separa-when not in service except when undergoing main-ted and protected to the extent necessary to tenance.
assure that sufficient equipment remains oper ating to permit shutdown of the unit in the event of any of the following (separation is applied to Amendment 14 9.2-5
i.
j ABWR 2346iooxii Standard Plant nrv n (3) The system shall be designed and constructed the reacto:7uilding as shown in Figure 1.2-12.
in accordance with Seismic Category 1, ASME Equipment is listed in Table 9.2-8.
Each code,Section III, Class 3 requirements.
cooling coil has a three-way valve controlled by a room thermostat. Alternately, flow may be (4) The system shall be powered from Class 1E controlled by a temperature control valve, buses.
Condenser cooling is from the corresponding division of RCW.
(5) The IIECW system shall be protected from missiles in accordance with Subsection Piping and valves for the HECW system, as 3.5.1.
well as the cooling water lines from the RCW system, designed entirely to ASME Code, Section (6) Design features to preclude the adverse III, Class 3, Quality Group C, Quality Assurance effects of water hammer are in accordance B requirements. The extent of this with the SRP section addressing the classification is up to and including drainage resolution of USI A-1 discussed in block valves. There are no primary or secondary N U R EG-0927.
containment penetrations within the system. The HECW system is not expected to contain These features shallinclude:
radioactivity.
(a) an elevated surge tank to keep the High temperature of the returned cooling system filled; water causes the standby refrigerator unit to start automatically. Makeup water is supplied (b) vents provided at all high points in the from the MUWP system, at the surge tank. Each system; surge tank has the capacity to replace system water losses for more than 100 days during an (c) after any system drainage, venting is emergency. The only i;on safety-related portions assured by personnel training and of the HECW d: visions are the chemical addition procedures; and tank and the piping from the tank to the safety related valves which isolate the safety related (d) system valves are slow acting.
portions of the system.
6 (7) The HECW system shall be protected from Also, see Subsection 9.2.17/ for COL license failures of high and medium energy lines as information requirements.
discussed in Section 3.6.
9.2.13.3 Safety Evalustion 9.2.13.2 System Description The llECW system ir a Seismic Category 1 The HVAC emergency cooling water system system, protected from flooding and tornado consists of subsystems in three divisions.
missiles. All components of the system are Division A has one refrigerator and pump and designed to be operable during a loss of normal Division B and C have two refrigerator units, two power by connection to the ESF buses. See pumps, instrumentation and distribution piping Tables 8.31 and 8.3-1 Redundant components and valves to corresponding cooling coils. A are provided to ensure that any single component chemical addition tank is shared by all HECW failure does not preclude system operation in divisions. Each HECW division shares a surge Divisions B and C. The system is designed to tank with the corresponding division of the RCW meet the requirements of Criterion 19 of system. The refrigerator capacity is designed to 10CFR50. Each chiller is isolated in a separate O
cool the diesel generator zone and electrical room.
equipment room in its division.
If a LOPP event occurs, there are provisions l
The system is shown in Figure 9.2-3.
The for a stop signal to the HECW pumps to trip the refrigerators are located in the control bitilding breakers or for sequencing the HECW pumps back as shown in Figures 1.2-20 and 1.2-21. This onto the emergency bus during the alloted time system shares the RCW surge tanks which are in frame (load block 3) which is 15 seconds after Amendment 27 9.2-9 1
ABWR 23A6:00A>i Sandard Plant Rev.n i
i TABLE 9.2-4a REACI'OR BUILDING COOLING WATER DIVISION A Ernergency Normal (LOCA) (Sup-Operating Mode /
Operatmg Shutdown at a
',hutdown at 20 llot Standby 110: Standby pression Pool Components Conditions hours hours (noloss of AC)
(lossof AC) at 97 C ESSENTIAL liest now lic41 How IIcat flow flcat Flow Ileat flow IIcat flow (Note 1)
Emergency Die-3.2 229 32 229 sel Generator A R]lR lleat 25.8 1199 83 1199 6.1 1199 213 1199 Ikchanger A
'C lleat 1.7 279 1.7 279 1.7 279 1.7 29 1.7 279 23 279 Exchanger A j
Others (essen-
.76 145 86 145
.91 145
.81 145
.98 145 1.0 145 tial)(Note 2)
NON-ESSENTIAL l
RWCU llest 48 159 159 159 4.8 159 5.0 159 Exchanger Inude Drywell 1.4 320 1.4 320 1.4 320 1.4 320 0.81 320 (Note 3)
Others (non.
0 63 100 0.63 100 OA3 100 0 63 100 0.20 59 0.18 59 essential)
(Note 4)
Total load 93 1003 30.4 2202 12.9 2202 9.3 1003 18 2390 28 1911 NOTES:
0 l
(1) Heat x 10 kilocal/h;flowx m /hr, sums may not be equaldue to rounding.
, fCAMS), RHR motor and seal coolers.
(2) HECWrefrigerator, room coolers (FPCpump, RHR, RCIC, (3) Dr>well(A & C) and RIP coolers.
(4) Instmments and service air coolers: R WCUpump cooler, CRD pump oil, and RIP Mg sets.
Amendment 27 9.2-17
ABWR 23462m4H Standard Plant Rw n TABLE 9.2 4b REACTOR BUILDING COOLING WATER DIVISION B Ernergency Normal (LOCA)(Sup-Operating Mode /
Operating Shutdown at 4 Shutdown at 20 Ilot Standby Hot Standby pression Pool Components Conditions hours boun (no loss of AC)
(loss of AC) at 97 C ESSENHAL lleet Row IIcat now IIcat now fleat nuw IIcat Flow Ileat now (Note 1)
Ernergency Die-3.2 229 3.2 229 sel Generator B RilR liest 25 8 1199 8.3 1199 6.1 1199 21.3 1199 Exchanger H C licat 1.7 279 1.7 279 1.7 279 1.7 229 1.7 229 2.3 279 Exchanger D u
Ot hen (essen-1.2 422 1.4 422 1.4 422 1.2 422 1.4 422 1.6 422 tial)(Note 2)
NON-ESSENHAL RWCU lleat 48 159 159 159 4.8 159 4.8 159 Exchanger Inside Drywell 0.7 279 1.5 2W 1.29 279 1.29 279 0.6 279 (Note 3)
Ot hen (non-0.7 159 0.35 159 0.35 159 035 159
.08 9.1 9.1 essential)
(Note 4)
Total lmad 9.7 1298 30 6 2500 17.9 2500 9.3 1998 17.7 2576 28.3 2163 NOTES:
b to 3
l (1) Heat x kilocalfh; flow m /hr, sums may not be equal due to rounding.
n (2) HECWrefrigerator, room coolers (FPCpump, RHR, HPCF, SGTS, FCS, C4MS), HPCFand RHR m otor andmechanicalsealcoolers.
(3) Drywell(B) and RIP coolers.
(4) Reactor Building sampling coolers; LCW sump coolers (in drywell and reactor building), RIP l
MG sets and RWCU pump coolers.
i Amendment 27 9.2-18 i
m
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-AB M 23A6100All Signdard Plant REV. B i
TABLE 9.2 4c REACTOR BUILDING COOLING WATER 1
DIVISION C Emergency Normal (LOCA)(Sup -
Operating Mode /
Operstmg Shutdown at 4 Shutdown at 20 110 Standby liot Standby pression Pool i
Components Conditions hours hours (noloss of AC)
(loss ot AC) at 97 C ESSENTIAL lleat Plow liest Dow fleat now liest Dow liest now Ileat '
Flow (Note 1)
Emergency D' 3.2 229
' 3.2 229 sel Generator [C RilR ileat 24.8 1l99 8.3 1199 6.1 1199 21.3 t:* 4 Exchanger h Others (essen.
1.5 631 1.6 631 1.6 631 1.5 631 1.5 631 1.7 631 taal)(Note 2)
NON ESSENTIAL Others (non-4.3 422 4.6 422 1.8 422 4.3 422
.13 50
.18 50 essential)
(Note 4) 2 llb 1llb Total lead 64 1053 32 2252 11.6 2252 6.4 1053 10.8 26.4 W-1 NOTES:
b 10 3
l (1) Heatx kilocal/h m /h;flowxg/m, sums may not be equal due to rounding.
A (2) HECW refrigerator, room coolers motor coolers, and mechanical seal coolers for RHR and HPCF' F CS
- h M TSt m W er-(3) Instrument and service air coolers, CRD pump oil cooler, radwaste components, HSCR condenser, and turbine building sampling coolers.
4 l
i Amendnwat 27 9.2-19 5d
. - _ =... _...-
ABWR 2346tooxii Standard Plant REv.n TABLE 9.2-4d DESIGN CHARACTERISTICS FOR REACTOR BUILDING COOLING WATER SYSTEM COMPONENTS RCW Pumps (Two per division)
RCW (A)/(B)
RCW (C) 1420 3 3
Discharge Flow Rate
.Elii8 m /h/ pump 1237 m /h/ pump 2
2 Pump Total Head 5.8 kg/cm 53 kg/cm 2
2 Design Pressure 14 kg/cm 14 kg/cm Design Temperature 71 C 71 C RCW Heat Exchangers (Three per division)
RCW (A1/(B)
RCW (C) 6 6
Capacity (for each 11)x10 kilocal/(
106x10 kilocal[h heat exchanger)
A, RCW Surge Tanks Capacity 16 cubic meters (total, each)
Design Pressure Static Head
- Design Temperature 71 C RCW Chemical Addition Tanks Design Pressure 14 kg/cm Design Temperature 71 C RCW Piping Design Pressure 14 kg/cm Design Temperature 71 C Amendment 27 9.2-19.1
a ABM 23461oorn Standard Plant Rev.n
)
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J Table 9.2-13 REACTOR SERVIC WATER SYSTEM CM"M
)
RSW Pumps (Two per division)
Discharge Flow Rate, per pump 1800 m /h -
PumpTotal Head 3.5 kg/cm Desip Pressure 8.1 kg/cm Desip Temperature 50"C RSW Piping and Valves Desip Pressure 11 kg/czn Desip Temperature 50 C 1
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Amendment 27 9.2 25d 1
Water level sensors are located in the RCW surge tank standpipes. Low water level sig-nals from both the surge tank and the standpipe stop any operating pumps in that division.
A signal from LOCA, high suppression pool temperature or high RCW water temperature overrides the low water levels signals and puts all pumps in that division in operation.
i O
During a Station Blackout (SBO), the IIECW refrigerators, pumps and instrumentation will be powered by the AAC system which will become available in ten minutes. Provi-sions will be made to ensure prompt restan of the refrigerators as discussed in Subsection 9.2.17.6 The response to SBO is discussed in Chapter 1, Appendix IC. During the SBO, little heat will be generated in the areas cooled by HECW because only battery powered equipment will be operating. These areas are the main control room, the control building essential electrical equipment rooms and the reactor building essential electrical equipment rooms.
The HVAC fans in these areas are powered by Class IE buses. When AAC power be-comes available, these fans will be powered and will start supplying outside air and ex-hausting any hot air from these areas. When chilled water becomes available, cooled air will be circulated in these areas to restore normal temperature.
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