ML20114A045
| ML20114A045 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 08/04/1992 |
| From: | Kirberg S GENERAL ELECTRIC CO. |
| To: | GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 9208070258 | |
| Download: ML20114A045 (5) | |
Text
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. m GE Nuclear Energy
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- f,(.00{ l August 4,1992 i
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I TO: DISTRIBUTION
$' FROM: L Kirberg IId
- aBWR/SSAR Support Center (408)925 1343
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SUBJECT:
Amendment 21-Reprinted Pages to Correct Disconnects / Discrepancies included are copies of non-proprietary page corrections which are to replace those mailad earlier in the Amendment 21 transmittal. The enclosed pages are reprinted
- back-to-back to correct the di3conrect/ discrepancy. No text changes are included in this mailing.
- Following is a list of reprinted non-proprietary pages
I Insert Comment 5.2-25, 26 Pages printed back-to-back to correct page sequence.
5.2-27,28 4
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9208070258 ?20804 1 i\
PDR ADOCK 0520 A
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".4.8.1
, line of the RHR loop *B'. The cooled effluent of the NRHXs goes through the CUW pumps to the
- The CUW system: two filter-demineralizers for cleanup. CUW system discharge is split to feedwater lines "A*
(1) removes solid and dissolved impurities from and 'B". The system P&lD is provided in Figure the reactor coolent and mea s the reactor 5.4-12.
water conductivity in accordance with Regulatory Guide 1.56, ' Maintenance of Water The total capacity of the system, as shown on Purity in Boiling Water Reactors"; the procets flow diagram in Figure 5.4-13 is l equivalent to 2% af rated feedwater flow. Each (2) provides containment isolation that places pump, NRHX, and filter-demineralizer is capable the major portion of the CUW system outside of 50% system capacity operation, with the or.e
. the RCPB, limiting the potential for RHX capable 100% system capacity operation.
significant release of adioactivity from the primary system to the secondary The operating temperature of the containment; filte. -demineralizer units is limited by the ion exchange resins; therefore, the reactor coolant (3) discharge excess reactor water during must be cooled before being processed in the startup, shutdown, and hot standby filter-demineralizer units. The regenerative conditions to the main condenser or radwaste heat exchanger transfers heat from the tubeside or suppression pool; (hot process inlet) to the shellside (cold process return). The she:Iside flow returns to (4) provides full system flow to the RPV bead the reactor. The non-regenerative heat spray as required for rapid RPV cooldon and exchanger cools the process further by
, rapid refueling; and transferring heat to the reactor building cooling water system.
(5) minimizes RPV temperature gradients by maintainiag circulation in the bottom head The filter-demineralizer units are pressure of the RPV during periods when t% reactor precoat-type filters using oowdered ion-exchange internal pumps are unavailable, resins. Spent resins are not regenerated ad are sluiced from the filter demineralizer unit The CUW system is automatically removed from to a bacxwash receiving tank from which they are service upon SLCS actuation. This isolation transferred to the radwaste system for pro-prevents the standby lin-id reactivity control cessing and disposal. To prevent resins fram material from being remt ,cd from the reactor entering the reactor in the event of failure of water by the cleanup system. The design of the a filter demineralizer resin support, a strainer CUW system is in dance with Regtdatory Guide is installed on the filter demineralizer unit.
1.26 and Regulatory %de 1.29. Each strainer and tilter-demineralizer vessel has a ccntrol room alar n that is energized by 5.4.8.2 System D-scription high diff rential pressure. Upon further increase in differential pressure from the alarm The CUW is a closed-loop system of piping, point, the fitter demineralizer will circulation pumps, a regenerative heat exchanger, auto m atica11y isolate.
non regenerative heat exchangers, reactor water pressure boundary isolation valves, a reactor The backwash and precoat cycle for a water sampling station, (part of the sampling filter-demineralizer unit is automatic to system) and two precoated filter-demineralizers. minimize the need for operator intervention.
During blowdown of reactor water swell, the loop The filter-demineralizer piping conf (,aration is is open to the radwaste or suppression pool. The complete and crud traps are eliminated. A single loop has two parallel pumps taking common bypass li;.e is provided around the filter-suction through a regenerative heat exchanger demineralizer units.
(RHX) and two parallel non-regenerative heat exchangers (NRHX) from both the single bottom head drain line and the shutdown cooling suction Amendment 21 5A-25
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ABM _
234stms. ,
Standard Plant REV. A ' ;
t In the event of low flow or loss of flow in .demineralizer compartment is normally permitted -
the system, the precoat is mainta.ined on the only after removal of_ the precoats Penetrations ;
septa by a holding pump. Sample points are through compartment walls shall be located so as -
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provided in the common influent header and in not to compromise radiation shielding - .
each effluent line of the filter demineralizer requirements, Primarily, this affects nozzle '
.l units for ccatinuous indication and recording of locations on tanks so that wall penetrations do _ l system conductivity. - High conductivity is not 'see* the tanks. Generally, this_ ncans j annunciated in the control room. The influent piping through compartment walls should be . .
sample point is also used as the normal source of aboye, below, or to the s'de of . l f
reactor coolant grab samples. Sample analysis filtendemineralizer units. The local control also-indicates the effectiveness of the panel shall be outside the vessel compartment i filter demineralizer units, and process valve cell, lo_cated convenient to f the CUW systern. The tank which receives t I
The suction line (RCPB portion) of the CUW backwash shall be located in a separate shielded '
system contains two motor operated isolation room below the filter demincralizer units.
valves which automatically close in response to _
signals from the leak detection and isolation The filter demineralizer vents are piped to system, actuation of the standby liquid control the backwash receiving tank. Piping vents and l system, and high filter demineralizer inlet drains arc directed to Ic,w conductivity i temperature. Subsection 7.3.1.1.2 describes the collection in radwaste. System pressure relief _
leak detection and _i_ solation system setpoints valves are piped to radwaste. Refer to Figure
- that are summarized in Tables 5.2-6 and 5.2 7. 5A 12 for the exact configuration. :
This isolation prevents loss of reactor coolant ;
and release of radioactive material frorr. the A remote, mat.ually-operated gate valve on the [
reactor, prevents removal of liquid reactivity- return the to the feedwater lines in the steam - j control material by the cleanup system sho,ld the t~.act provides long term leakage control. j SLCS be in operation, and prevents exceeding the Ins.antaneoss reverse flow isolation is provided - i design temperature of the_ CUW and the .
by. check valves in the CUW piping.- l filter demineralizer resins. The RCPB isolation !
valves may be remote manually' operated to isolate .CUW system operation is controlled from ti.e !
the system equipment for maintecance or main control room. Filter demineralizing !
l servicing. Discussion of the RCPB is provided in operations, which include backwashing and Section 5.2. precoating, are controlled automatically from a :
process controller or manually _ from a local l i
Each filter-demineralizer vessel shall be panel. -!
' installed in an individual shielded compartment, i The compartments shall not require accessibility ;
i during operation of the fittar demineralizer _5A.8.3 System Evaluation unit. Shielding is required-due to the -!
concentration of radioactive products in the = The CUW system, in conju_nction with the l j
filter-demineralizer process system. . Service . condenuat.s .reatment system and the fuel pool space shall be provided the filter-demineralizer - cooling anJ ;leanup system, maintains reactor i for septa removal. All inlet, outlet, vent, water quality during all reactor operating modes j drain, and other process valves shall be located (normal, hot standby, startup, shutdown, and i outside the filter demineralizer compartment in a ' refueling), i separate shielded area _together with the- d necessary piping, strainers, holding pumps end :The CUW system has process interlaces with r
instrument elements. Process equipment and the RHR, . control rod drive, nuclear _ boiler,- 'I controls r. hall be arranged so that _all normal radwaste, fuel pool cooling and cleanup (FPC), l j operations are conducted at the panel from reactor building cooling water systems, RPV, and ,
L outside the vessel or valve and pump compartmeu suppression pool. The CUW suction is from the ;
shielding walls. Access to Ihe filtcs- RHR *B' shutdown suction line and the RPV bottom i head drain. The CUW system main process pump '[
i Amendment 2t - 5 4-26 ' !
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ABWR m6mn Standard Plant en c f ' '
motor cavities are purged by water from the the high presture block alves is designed to l control rod drive system. CUW system return flow Quality Group D.
is directed to either the nuclear boiler system (feedwater lines), directly to the RPV through A tabulation of CUV' system equipment data, l the R PV head spray, suppression pool or radwaste includir.g temperature gressure and flow capacity through the CUW dump line. CUW filter- is provided in Table 5.4-6.
demineralizer backwash is to the backwash j receiving tank (BWRT) located in thc FPC (1sWRT SA.9 Main Steamlines and Feedwater Piping accommodates backwash from the CUW the FPC, and the suppression pool cleanup system). The 5A.9.1 Safety Design Bases norm .;enerative heat exchanger is cooled by the reactor building cooling water system. Other la order to satisfy tl e safety design bases, utility or support interf aces exist with the the main steam and feedwater lines are designed instrument air system and the condensate and as follows:
plant air systems foi the filter demineralizer backwash. (1) The main stecm, feedwater, and associated drain lines are protected from potential The type of pressure precoas cleanup system damage uue to t'luid jets, missiles, reaction used ia this systen was first put into operation forces, pressures, and temperaturet resulting in 1971 and has been in use in all BWR plants from pipe breaks.
brought on-line since then. Oper sing plant
, experience has shown that the CUW system, de- (2) The main steam, feedwater, and drain lines signed in accordance wi,a these criteria, are designed to accommodate stresses from provides the required BWR water quality. The internal pressures and earthquake loads ABWR CUW systen capacity has been increased to a without a faihne that coul! lead to the nominal of 2% of rated feedwater from the release of radioactivity la excess of the 1
original 1% size. This added capacity provides guideline values in published regulations.
- additional marain against primary system intrusions and component availability. The (3) The malt steam and feedwater lines are accts-
, nonregenerative heat exchanger is sized to sible for inservice testing and inspection.
rc'in'ain the required process temperature for
. 100% syttem flow. During periods of water (4) The main steamlines are analyzed for dynamic rejection to the suppression pool or eadwaste, loadings due to fast closure 'f the turbine CUW syrtem flow may be reduced .. lightly to stop valves, cort.pensate for the loss of cooling flow through the RPV return side of the regenerative heat (5) The main steam and feedwater piping from the exchanger. reactor through the seismic interf ace restraint is designed as Seismic Category 1.
The CUW system is classified as a nonsafety system. The reactor isolation valves are (6) T' e main steam and feedwater piping and classified as important to safety. System piping s ualler connected lines are designed in and compcnents within the drywell, including the accordance with the requirements of Table d
suction piping up to and including the outboard 3.2 1.
4 suction isolation valve, and all containment isolation valve including interconnecting piping 5.4.9.2 Power Generation Design Bases assembly, are Seismic Category 1, Quality Group A. The three flow elements that are used for CUW (1) The main steamlir.es are designed to conduct system leak detection meet Seismic Category I and steam from the reactor vessel over the full Quality Group A requirements so as to maintain range of reactor power operation.
structural integrity during a faulted conditiot..
All other non-safety equipment is designed as Nonseismic, Quality Group C. Iow pressure piping in the t ackwash and precoat area downstream of Amendment 18 5 4-27 2
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e I ABWR 2x-n -1 Standr.cd Plant my g ,
(2) The feedwater lines are designed to conduct The materials used in the piping are in _.
water to the reactor vessel over the full accordance with the applicable design code and range of reactor power operation, supplementary requirernents described in Section 3.2. The valve between the outboard isolation 5.4.9.3 Description valve and the shutoff valve upstream of the RHR entry to the feedwater line is to effect a The main steam piping is described in Section closed loop outside containment (CLOC) for 10.3. The main steam and feedwater piping from containment bypass leakage cantrol (Subsections the reactor through the containment isolation 6.2.6 and 6.5.3),
interfaces is diagrammed in Figure 5.1-3.
The general requireraents of the feedwater
. As discussed in Table 3.21 and shown in system are described in Subsections 7.1.1.7 l'igure 5.13, the tr.ain steamlines are Quality 7.",.1.4, 7.7.2.4, a nd 10.4.7.
1 Group A from the reactor vessel out to and includ-ing th; outbcard MSIV and Quality Group B from 5.43.4 Safety Evaluation the outboard MSIVs to the turbine stop valve.
They are also Seisraic Category I only from the Differentiti pressure on reactor internals reactor pressure vessel out to the seismic inter- under the assumed accident condition of a rup-face restraint. tured steamline is limited by the use of flow restrictors and by the use of four main steam-The feedwater piping consists of two 550 A lines. All main steam and feedwater piping will diameter lines from the feedwater supply header be designed in accordance with the requirements
- to tne reactor. Isolation of each line is defined in Section 3.2. Design of the piping in accomplished by two containment isolation valves accordance with these requirements ensures consisting of one check valve inside the drywell meeting the safety design bases.
, and one positive closing check valve outside containment (Figure 5.1-3) Also included in 5.4.9.5 Inspection and Testing this portion of the line is a manual mdntenance l valve (F005) between the inboard isolation valve Testing is carried out in accordance with and the reactor nozzle. The design temperature Subsection 3.9.6 and Chapter 14. Inservice and pressure of the feedwater line is the same as inspection is considered in the design of the that of the reactor inlet nozzle (i.e., 87.9 mair steam and feedwater piping. This consider-kg/cm 2g and 3020C). ation assures adequate working space am. access for the inspection of selected components.
The feedwater piping upstream of the second
) isolation valve contains a remote, manual, 5.4.10 Pressurizer motor-operated gate valve and upstream of the s gate valve, a seismic interface restraint. The Not Applicable to BWR o
" outboard isolation valve and the seismic ii.ter-face restraint provide a quality group transi- 5.4.11 Pressurizer Relief Discharge System tional point in the feedwater lines.
Not Applicable to BWR l
As discussed in Table 3.2-1 and shown in l Figure 5.1-3 the feedwater piping is Quality 5.4.12 Valves Group A from the reactor pressure vessel out tu and including the outboard isolation valve, 5.4.12.1 Safety Design Bases n Quality Group B from the outboard isolation valve
$ to and including the seismic interface restraint, Line valves, such as gate, globe, and check
, and Quality Group D beyond the shutoff valve.
The feedwater piping and all connected piping of
{ 65A or larger nominal size is Seismic Category I only frort Me reactor pressure vessel oui to and 4
including the seismie inter face restraint.
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