ML20058L832
| ML20058L832 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 05/07/1993 |
| From: | Fox J GENERAL ELECTRIC CO. |
| To: | Poslusny C Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9305130016 | |
| Download: ML20058L832 (8) | |
Text
"
GENucle6rEnergy i
GeneralDectac Company l
175 Curt'er Astnue San Jose. CA 95'?5 i
[
May 7,1993 Docket No. STN 52-001 i
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Chet Poslusny, Senior Project Manager l
Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal -
Office of the Nuclear Reactor Regulation i
Subject:
Submittal Supporting Accelerated ABWR Review Schedule - Reactor Water
[
Cleanup System Excess Water Discharge Paths
Dear Chet:
[
Enclosed is a SSAR markup showing alternate path to discharge excess water to the main j
condenser rather than to the suppression pool. This was discussed with Butch Burton and Jim Lyons at our April 13 - 15,1993 meeting in San Jose, California Please provide a copy of this transmittal to Butch Burton.
l Sincerely, Yef ack Fox Advanced Reactor Programs cc: Norman Fletcher (DOE)
Bernie Genetti (GE)
Ed Nazareno (GE).
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i JN138 9305130016 930507'
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- MlM nA61ooAs Standard Plant nrv c 5.4.8.1 Design Basis loop "B". The cooled effluent of the NRHXs goes through the CUW pumps to the two The CUW system:
filter-demineralizers for cleanup. CUW system discharge is split to feedwater lines "A" and (1) removes solid and dissolved impurities from "B".
A bypass line around the filter the reactor coolant and measures the reactor demineralizer units is also provided. The water conductivity in accordance with system P&lD is depicted in Figure 5.4-12.
Regulatory Guide 1.56," Maintenance of Water Purity in Boiling Water Reactors";
The total capacity of the system, as shown on the process flow diagram in Figure 5.4-13 is (2) provides containment isolation that places equivalent to 2% of rated feedwater fiow. Each the major portion of the CUW system outside pump, NRHX, and filter-demineralizer is capable the RCPB, limiting the potential for of 50% system capacity operation, with the one significant release of radioactivity from the RHX capable of 100% system capacity operation. D primary system to the secondary containment; The operating temperature of the (3) discharge excess reactor water during filter-demineralizer units is limited by the ion startup. shutdown, and hot standby conditions exchange resins; therefore, the reactor coolant to the radwaste or(fuppression poof, must be cooled before being processed in the MS/n cadeAfW filter-de:nineralizer units. The regenerative (4) provides full system flow to the RPV head heat exchanger transfers heat from the tubeside spray as required for rapid RPV cooldown and (hot process inlet) to the shellside (cold rapid refueling; and process return). The shellside flow returns to the reactor. The non-regenerative heat (5) minimizes RPV temperature gradients by exchanger cools the process further by maintaining circulation in the bottom head of transferring heat to the reactor building the RPV during periods when the reactor cooling water system. A temperature sensor is internal pumps are unavailable.
provided at the outlet of the NRHX to monitor and automatically isolate the filter-deminer-The CUW system is automatically removed from alizer units if temperature goes above the service upon SLCS actuation. This isolation high-high setpoint. High high temperature prevents the standby liquid reactivity control condition is also annunciated in the main material from being removed from the reactor water control room. Following the high temperature by the cleanup system. The design of the CUW isolation, the filter Jemineralizer bypass valve $-
system is in accordance with Regulatory Guide 1.26 is automatically opened, and Regulatory Guide 1.29.
The filter-demineralizer design is vendor 5.4.8.2 System Description specific. A typical design of the filter-demin-er.lizer is discussed below. The filter-The CUW is a closed-loop system of piping, demineralizer units are pressure precoat-type circulation pumps, a regenerative heat exchanger, filters using powdered ion-exchange resins.
non-regenerative heat exchangers, reactor water Spent resins are not regenerated and are sluiced pressure boundary isolation valves, a reactor from the filter-demineralizer unit to a backwash water sampling station, (part of the sampling receiving tank from which they are transferred system) and two filter-demineralizers. During to the radwaste system for processing and blowdown of reactor water swell, the loop is open disposal. To prevent resins from entering the to the radwasteguppression poop The single reactor in the event of failure of a filter
}$/aer ~ loop has two parailcl pumps taking common suction demineralizer resin support, a strainer is cards 5d through a regenerative heat exchanger (RHX) and installed on the filter-demineralizer unit.
two parallel non-regenerative heat exchangers Each strainer and filter-demineralizer vessel (NRHX) from both the single bottom head draia line has a control room alarm that is energized by and the shutdown cooling suction line of the RHR high differential pressure. Upon further increase in differential pressure from the alarm point, the filter demineralizer will 5 4-25 Amndan
ABM uxsioosa Standard Plant REV C In t'he event of low flow or loss of flow in the The suction line (RCPB portion) of the CUW system, the precoat is maintained on the septa by system contains two rrotor-operated isolation a holding pump. Sample points are provided in the valves which automatically close in response to common influent header and in each effluent line signals from the leak detection and isolation of the filter.demineralizer units for continuous system. LDS isolation signal for CUW consists indication and recording of system conductivity. of low reactor water level, high ambient main High conductivity is annunciated in the control steam tunnel area' temperature, high mass The influent sample point is also used as differential flow, high ambient CUW equipment room.
the normal source of reactor coolant grab area temperature, and activation of SLCS pump.
samples. Sample analysis also indicates the Subsection 7.3.1.1.2 also describes the above effectiveness of the filter-demineralizer units.
isolation signals and are summerized in Table 5.2-6..
This isolation prevents loss of reactor f
Each filter-demineralizer vessel is installed coolant and release of radioactive material from in an individual shielded compartment. The the reactor, prevents removal of liquid l compartments do not require accessibility during reactivity control material by the cleanup operation of the filter-demineralizer unit. system should the SLCS be in operation. The Shielding is required due to the concentration of RCPB isolation valves may be remote manually radioactive products ia the filter-deminerali-operated to isolate the system equipment for
('zers. Service space is provided for the maintenance or servicing. Discussion of the filter-demineralizer septa removal. All inlet, RCPB is provided in Section 5.2.
( outlet, vent, drain, and other process valves are located outside the filter-demineralizer A remote, manually-operated gate valve on the compartment in a separate shielded area together return line to the feedwater lines in the steam with the necessary piping, strainers, holding tunnel provides long term leskage control.
pumps and instrument elements. Psocess equipment Instantaneous reverse flow isolation is provided and controls are arranged so that all normal t>y check valves in the CUW piping.
operations are conducted at the panel from outside the vessel or valve and pump compartment shielding CUW system operation is controlled from the walls. Access to the filter-demineralizer main control room. Filter demineralizing compartment is normally permitted only after operations, which include backwashing and removal of the precoat. Penetrations through precoating, are controlled automatically from a l compartment walls are located so as not to process controller or manually from a local compromise radiation shielding requirements. panel.
Primarily, this affects nozzle locations on tanks so that wall penetrations do not *sec* the tanks. 5.4.8.3 System Evaluation Generally, this means piping through compartment
/ walls are above, below, or to the side of The CUW system, in conjunction with the filter-demineralizer units. The local control condensate treatment system and the fuel pool j panel is outside the vessel compartment and cooling and cleanup system, maintains reactor process valve cell, located convenient to the CUW water quality during all reactor operating modes 4 system. The tank which receives backwash are (normal, hot standby, startup, shutdown, and
/ located in a separate shielded room below the refueling).
filter-demineralizer units.
The CUW system has process interfaces with The filter-demineralizer vents are piped to the the RilP, control rod drive, nuclear boiler, backwash receiving tank. Piping vents and drains radwaste, fuel pool cooling and cleanup (FPC),
are directed to low conductivity collection in reactor building cooling water systems, RPV, and g
radwaste. System pressure relief valves are piped ppremon confrThe CUW suction is from the to radwaste. Refer to Figure 5.4-13 for a typical HR *B* shutdon suction line and the RPV bottom configuration.
head drain. The CUW system main process pump
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The CW main suction line is provided with a flow restrictor inside containment for flow monitoring and break flow restricting functions.
l The flow restrictor has a maximum throat diameter of 135 mm. The RPV l
bottom head drain line is connected to the CW main suction line by a
" tee". The center line of the " tee" connection is at an elevation of at least 460 mm above the center line of the variable leg nozzle of the RPV wide range water level instrument (or at least 389 mm above the top of active fuel). In the unlikely event of unisolated CW line break RPV water level will be maintained at the elevation of the " tee" connection.
A more detailed discussion regarding CW unisolated line break is provided in Section 19.9.1.
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,4g REV C mot.or cavities are purged by wate[from the pressure block valves is designed to Ouality control rod drive system. CUW systim return flow Group D.
is directed to either the nuclea/ boiler system (feedwater lines), directly tojhe RPV through A tabulation of CUW system equipment data, the RPV head spray,(uppression pop or adwaste including temperature pressure and flow capacity through the CUW dump line. CUlv filter-is provided in Table 5.4 6.
J demineralizer backwash is to the backwash receiving tank (BWRT) located in the FPC (BWRT 5.4.9 Main Steamlines and Feedwater Piping accommodates backwash from the CU3the FPC, and i
j the suppression pool cleanup system). The 5.4.9.1 Safety Design Bases non-regenerative heat exchanger is cooled by the reactor building cooling water system. Other in order to satisfy the safety design bases, I
utility or support interfaces exist with the the main steam and feedwater lines are designed instrument air system and the condensate and as follows:
plant air systems for the filter-demineralizer backwash.
(1) The main steam, feedwater, and associated drain lines are protected from potential The type of pressure precoat cleanup system damage due to fluid jets, missiles, reaction used in this system was first put into operation forces, pressures, and temperatures
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in 1971 and has been in use in all BWR plants resulting from pipe breaks.
brought on-line since then. Operating plant experience has shown that the CUW system, de-(2) The main steam, feedwater, and drain hnes signed in accordance with these criteria, are designed to accommodate stresses from provides the required BWR water quality. The internal pressures and carthquake loads ABWR CUW system capacity has been increased to a without a fmilure that could lead to the nominal of 2% of rated feedwater from the release of radioactivity in excess of the i
original 1% size. This added capacity provides guideline values in published regulations.
additional margin against primary system intrusions and component availability. The (3) The main steam and feedwater lines are nonregenerative heat exchanger is sized to
.acces-sible for inservice testing and maintain the required process temperature for inspection.
100% system flow. During periods of water i
rejection to thepu pression poofdr radwaste, (4) The main steamlines are analyzed for dynamic MUW system flow may be reduced slightly to loadings due to fast closure of the turbine Md*
compensate for the loss of cooling flow through stop valves.
MMN the RPV return side of the regenerative heat exchanger.
(5) The main steam and feedwater piping from the reactor through the seismic interface The CUW system is classified as a nonsafety restraint is designed as Seismic Category 1.
[ system. The RCPB isolation valves are classified as safety related. System piping and components (6) The main Steam and feedwater piping and c within the drywell up to and including the smaller connected lines are designed in
[ outboard containment isolation valves, and accordance with the requirements of Table interconnecting piping assembly, are Seismic 3.2-1.
/eCategory I, Quality Group A.
All other non-safety equipment is designed as Nonscismic, 5.4.9.2 Power Generation Design Bases Quality Group C. Low pressure piping in the backwash and precoat area downstream of the high (1) The main steamlines are designed to conduct steam from the reactor vessel over the full range of reactor power operation.
Amendment 5 4-27
MWR 2=i=^e Standard Plant nrw n TABLE 3.21 CLASSIFICATION
SUMMARY
(Continued) i Quality I
Group Quality i
Safet4 Loca-Classi-Assurance Seismic Princinal Comnonent*
Class llan fication Reauirement' Catenorv Notes G1 Reactor Water Cleanup System (Continued) 4.
Pipinginduding supports and 1
C SC A
B 1
(g) valves within and induding outermost containment isolation 4
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valvesfii pump suctioib i
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Pump suction and discharge N
SC C
E (g) piping induding supports and valves from containment isola-
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tion valves back toghut-offg gy7 valvegrif feedwater ime connectiorgh b
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valves to radwaste and rupptcp 7-MmMh cen/en5W g 7[Non-regenerative heat exsanger N SC C
E (g) i tube inside and pipinginduding supports and valves carrying process water gg Non-regenerative heat exchanger N SC D
E i
shcIl and pipinginduding supports carrying dosed cooling water g Filter /demineralizer N
SC D
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precoat subsystem p [ Filter demin holding pumps N
SC C
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induding supports - valves and pipingincluding supports Amendment 3.2-19
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ABM ua6iman i
j Standard Plant Rev n 1
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TABLE 3.2-1 i
CLASSIFICATION
SUMMARY
(Continued)
Quality Group Quality Safet4 Loca-Classi d Assurance Seismic i
g Princioni Commonent, CIAH 1!2n fication Reauirement Catenorv Notes l
G1 Reactor Water Cleanup System (Continued)
)J I [ Sample station N
SC D
E jf. [ Electrical modules and cable N
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with no safety-related function i
l /J M Electrical modules and cable 3
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