ML20125E395
| ML20125E395 | |
| Person / Time | |
|---|---|
| Site: | 05200001 |
| Issue date: | 12/08/1992 |
| From: | Louison R GENERAL ELECTRIC CO. |
| To: | Poslusny C NRC |
| References | |
| NUDOCS 9212170035 | |
| Download: ML20125E395 (30) | |
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504-1I1 % Thispageplus AD page(s) From A LOWIS M usi\ cocs 76Y 175 Cunner Avenue San Jose, CA 95125 2-Phone (408) 925 /f FAX (408) 925-1193 or (408) 925-1687 Subject kBWA.IT&bc - Message 14003) y A PDR j 6
ABWR outen Document Mr. C. Poslusny 11-H-3 U.S. Nuclear RegulatoO' Commission 2.10 Power Cycle Office of Nuclear Reactor Regulathn 2,10.1 Turbino Main Steam System Washington, DC 20555 Design Description The Siain Steam (MS) System (Figure 2.10.1) supplies steam genented in the reactor to the twbine. Thb Tier 1 enuy addrenes that portion of the MS System that mnges between, but-dmoodndialei the cut:netemtainmen46olation. mlves-and4he-twbH tep =lves, but does not include, the seismic restmint dnwnstream or the outermost continment bolat on i vahes and the turbine stop_ vahes The hiS System is not required to effect or support safe shutdown of the reactor or to perfonn in the operation of rector safety features; however, the MS System is designed: (1) To r. amply-with-appik,% ~d- A %dania4n-orderao-accommodate operational stresses such as internal pressure and dynamic loads without risk +f failures, endumsequentia! -!=:: :f mdioanivit%n-c=:= cf th: ::d'Ahed-regulate:j hh. (2) To+ct+mmedet: nc =2' end-abnorma- "---~ ' limita, Provide a leakage path to the main condensers under schmic condidont
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= r= :!n 6--p hs, (3) With suitable access to permit in-service testing and inspections.
The MS System main steam piping consists of four lines from the sebmic gstraint oudmard-maineamur : ^%1ves to the main turbine stop vahrs. The header arrangement upstream of the turbine stop vahts allows them to be tested on4ine with minimum load reduction and also supplies steam to the power cycle auxiliaries, as required. The MS System is cuality croup D not ufety related. Inspections, Tests, Analyses and Acceptance Criterls Table 2.10.1 provides a definidon of the inspections, tests, and/or analyses, together with associated acceptance criteria which sill be undertaken fc. the MS System. 2.10 -1 11ms2
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1 ABWR oenlun coecent 1 2.10.2 Condensate Feedwater and Condensate Air Extraction System The Condensate Feedwater and Condensate Air Extraction System (C"*!M comists of two subsptems, the Condensate and Feedwater {CD. Sptem and the Main Condenser Evacuation System (MCES). Condensate and Feedwater System Design 00 sorption The function of the Cerd:= : :-d F=am:er (GF) (Firure 2.10.2a) System is to receive condensate from the condenser hotwells, supply condensate to the cleanup sptem, and deliver h!;;h pu-ig feedwater to the reactorot 6: : ;b:d S; = :, p:rr: =d ' rp :=::. Condensate i pumped from the main condenser hotwell by the condensate pumps, panes through the feedwater i heaters to the feedwater pumps, and then is pumped through the high pressure heaters to the nuclear Steam Supply System. ; he CF System boundaries ==!d=:d h= extend from the main condenser outlet to (but not including) the merd baden & net-le restrant outside the containment and downstream of the mtmnost Mstle valve The CF System conuts of the piping, valves, heat exchangers, controls and instrumentation, and th e associated equipment and subsptems which supply the reactor with heated feedwater in a closed steam cycle utilizing regenerative feedwater heating. The CF System does not serve or support any safety function and has no safety design basis. System analyses show that failure of this system cannot compromise any safety related systems or prevent safe shutdown. The CF Svitem is desismedJo qmHtv Groun D non. safety related. Fed = d i: 9:= e::=: r^d!:rSr d=E;; :p:= den = :"-!d:d it weee n:t:! fr inp=d:=. b&p S '-%!=d -ie =1dd === den 2:d d== p=det!:. Relief discharges and operating vents are channeled through closed systems. , Operational sptem redundancy is prtnided with respect to feedwater heaters, pumps, or control vahes by using multi-string arrangements and provisions for isolating and bypassing equipment and sections of the aptem. The majority of the condensate and feedwater piping :5=id=d b SE = is located within the turbine building which contains no safety related equipment or sptems. Se p :6: dkh ==nu :: S: =end 5aden .d: eutid: S: =1&==' k !:=:d in e: == :=ne! 5:== n ne =55: =d , 2,10.2 1 12/4,12 a- =.-. - . -- - ------- - -- --
48WR onion onumut icem: huildinge. Thb punkm ef ir pipingsanaly=d :er dy=mk-efrece r_2 r posalmed-wenend-safety /::!!e 9.whharges, Thedre *yuem-pipingsenalyzed for -terhammeAwbiw+mid-pmwab!!y --e f+onwuelpeed-lhumnWm Inspections, Tests, Analyses and Acceptance Criterls Table 2.10.2a provides a definition of the inspecdons, tests, and/or analyses, together with associated acceptance criteria which will be undertaken for the CF System. MsIn Condenser Evocustion System Design Description Nem,emdensab!: g=: a:+-twner-d from4he-pere: '.y:!: by4Ihe Main j Condenser Evacuation (MCE) System (Figure 2.10.2b).Th: MCE Sy:tm removes the hydrogen and oxygen produced by the radiolysh of water in the l reactor, and other power cycle noncondensable gases, and exhausts them to the offgas system during plant power operation, and to the turbine building compartment exhaust system at the beginning of each startup, l l The MCE System does not serve or suppon any safety function and has no safety design basis. The MCE System is designed to Quality Group D, Non-Safety Related The MCE System consists ok:e 10E apachy, -! cub % of redundant steamJet air ejectors (SJAE) units komp!ete "h L-t=end=:n) for power plant operation, and a mechanical vacuum pump for use during startup. He !=: stage ofi: Syl mit b nemc!!y in-epe: den =d 2: cier b = v=.dby. Steam supply to the mend :q: :jeuw SJAE is maintained at a minimum specified flow nte to ensure adequate dilution of the hydrogen and prevent the offgas from reaching the flammable limit of hydrogen. 5= p:=ure =d Per h :cnenueu:!y nh :ed =d :=telled in tb ej:::c - meam-eupply " ::. Redundant-p :== cent:cl!e:: ::=-v=n pre == :: ie-c.::ced :: ge in!:: =f madulate thuwam supply cenre!=1vec upstr:= cfie 9 eje::=. He ::v=' 90, T.m :nittere p::dde inpuu :: !cgi: device.Mne legk-device: pre dd: f : i:cledng i :Eg= Sev; f.m:- 6: cir ej:: tor = : en l wwmt44three !:g :, Should the steam flow drop below acceptable limits for l offgas-stream dilutionethe Ofrcas System will be isolated. l The vacuum pump exhaust stream is discharged to the turbine building compartment exhaust system which provides for radiation monitoring of the 2.10.2 2- 12/4/92
ABWh oneleaceoumect systern effluents prior to their release to the monitored vent stack and the , atmosphere. The vacuurn pump is tripped and its discharge valve is closed upon receMng a main steam high high radiation signal,
- Inspections, Tests, Analyses and Acceptance Criterls Table 2.10.2b provides a definition of the inspections, tests, and/or analyses, together with associated acceptance criteria which will be undertaken for the MCE System.
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ABWR outgaonuncat i 2.10.4 Condensate Purification System i Deelen Deeeription l l The Condensate PuriScation (CP) System purifles and treats the condensate as- l
++9uleed to maintain reactor feedwater pudty, using filtration to remove insoluble solids :=:9: p::d=4s, ion exchange to remove soluble solids from
, condenser leakage and other impudtles, and water treatment additions to ni:' : e reduce corrosion / erosion releases in the power cycle. The CP System does not serve or support any safety function and has no safety design bash. The CP System is designed to Quality Group D non safetv-related standards. The CP System consists of full flow high efficiency particulate fihers followed by full flow deep bed demineralhers. Due!dbg b prc-Ad:d fer i: C" Sp::- Vent gases and c'her wutes from the CP System are collected in rwH2 tion controlled areas and sent to the radwaste system for treatment and/or disposal. 4 The CP System is located in the ilurbine bBuildingu r ' p!;ing 2: :q.dp =t-
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Inspections, Tests, Anstyees and Acceptance Cetteels Table 2.10.4 provides a definition of the inspections, tests, and/or analyses,- together with asociated acceptance criteria which will be undertaken for the CP System. i I 1 11/2042 2.10.4
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- 2. CP Systeen WSSESS gris-4pe IS ColleC99d in L Vi* **8 ~ --^' ' d the as-built CP Sv$ tarn. L CQtRDliSGCS With Certifped dSeign
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ABWR onian naum:nt 2.10.7 Main Turbine Deelen Description The main Turbine Generator (TC) System convens the energy in steam from the nuclear steam supply system into electrical energy. The TG System does not serve not suppon any safety function and has no safe design bash. However, the TG System is a potential source of high energy missues that could damage safety related equipment or structures. The TG System is designed to prevent overspeed and thus nMme reducing _ the poulbuity of high energy missue generation from TG System moving paru. The following mmpenem instrumentatioLcontrols and vahing redundancies are employed to guard against overspeed: (1) Main stop valves GSn/ Control valves LCH IMSVs uip/CVs modulatch (2) Intermediate stop s-alves/ Intercept valves (CIVs) ICI% triot (3) Prbnary speed control / Backup speed control. (4) Fast acting solenoid vahts/ Emergency trip fluid system (ETS). (5) Speed control /Overspeed trip / Backup merspeed trip. Temperature. preuurc and soced indications. u well as oversneed alann are provided in the m2in control room s The TG System is enclosed within the Gurbine bDullding, which contains no safety related equipment or structures. The turbine generator is oticntated within the turbine building to be inline with the rReactor and eControl bIluudings to t-+ reduce the potential for any high energy TG System generated misalles from damaging any safety-related equipment or structures. Inspections, Teets, Anstyses and Acceptsnoe Criterls Table 2.10.7 proddes a defmition of the inspections, tests, and/or analyses, together with associated acceptance criteria which will be undertaken for the TG System. 2.10.7 1 iif23,92
ABWR Dnign Docum:nt l l 2.10.7 Main Turtelne Design Description The main Turbine Generator (TG) System converts the energy in steam from the nuclear steam supply system into electncal energy. The TG System does not serve nor support any safety function and has no safety design basis. However, the TG System is a potential source of high energy missiles that could damage safety related equipment or structures. The TG Sptem is designed to prevent overspeed and thus phhe reducing _ the possibility of high energy missile generation from TG System modng parts. The following compnem instrumentation controb and vahing redtmdancies are employed to guam against overspeed: (1) Main stop valves (MSV)/ Control valves .(CZ). IMSW trip /CW modubtel. (2) InterTnediate stop vahts/ Intercept valve n (CIW) ICI% triol. , (3) Primarf speed control / Backup speed control. (4) Fast acting solenoid vahts/ Emergency trip fluid system (ETS). (5) Speed control /Overspeed trip / Backup overspeed trip. Temperature. pressure and speed indications. as well as oversteed alarm are provided in the men control room. The TG System is enclosed within the tIurbine haullding, which contains no safety related equipment or structures. The turbine generator is orientated within the turbine building to be inline with the e]Leactor and eControl hiiulldings to mhanda, reduce the potential for any high energy TG System generated ndssiles from damaging any safety related equipment or structures, inspections, Tests, Analysee and Acceptance Cetterls Table 2.10.7 proddes a definition of the inspections, tests, and/or analyses, together with asociated acceptance criteria which will be undertaken for the TG System. 1 11/23.92 2.10.7
U Table 2.10.7: Main Tuttine Generator System P w Inspections, Tests, Analyses and Acceptance Critoria , CertfEed Design Commitrnorm ". g _d, w Tests, "_ ___", r - Acceptonce Cnteria
- 1. The TG System welNeeis desegned to la. ConductVytsual inspeccon and ransw_ 1. a. Following Design prtmssons to prevent proverx tPe turtsne generator rotor from Consing; Don recg[ds of the insta3ed overspeed are in placoq exceedingthe domign ov -c :1with equipmentmtogedierwishewnedstedtesting (IL MainJtoo valves / control valvas redundant instrumert.ation, controls and < .
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- S c8 :n; lb. Inst the controllogic of the as-built
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- b. Valvos_thst_succhr stysm to turbine GIQHt_uDQD_[WGR:D1 cf overinoted asonal
- 2. TWIN: 6.?d'r;; ni eentein no se&ay- 2. Conduct Vyisual inspecbon of the as-built 2. Turtaine generstor .n c== per-4
- eeleted :;:5- =wwweensee+mmThe tuttine building and plant arranDoments. ;;= d pl-* i:7.. is in hne wish the_
turbine generator wis be ja orientated to reactor and controlbudding. minanee* Enduce the potential for Fow trajectory high energy TG System anissiles frorn damaging safety-related equipment or structures. 1 Control room in*= tors-are orOyidh 3. Inapect nns will he nerformed to vnnfy the 3 Instrumentation is present in the Control IGSyste n carameters definerM;n section Dresence of control room ir*=tnrs for the room as defined in Sectige14191. 2.10.7. TG Systerre i IMLbine stoo valve will closa in 20.10_seG i EstfumLinst i TestInsultsin closure time 20.1(L3ec I
- 5. Ivrtine contmf vatve fastclose in.;t0J5_ 5. Entformlest 5. Issussutta inrivsure nme 2 0.15 mes l.
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ABWRouluommut i 2.10.9 Turbine Gland Steam System
- Deelen Desor> tion The Turbine Gland Sealing (TGS) System (Firure 2.10 91 prevents the escape of radioactive steam from the turbine shaft / casing penetntions and v.dve stems i and prevents air inleakage through subatmospheric turbine glands.
The TGS System consists of a sealing steam pressure regulator, sealing steam header, a gland steam condenser, with two full capacity exhaust blowers, and the associated piping, valves and instrumentation. The TGS System does not serve or support any safety function and has no safety design bads. The TGS System is designed to Quality Group D standards non-saferv-related. ne euter p;&r ef-1! gbet fi rd' =d :- ' :::= =!-::E = r rt:d te i: ;hJ -::= :: d=r, t.!9 S - '- ' rd et :";h: =: r. 'y Se e in.e:r W.::. N 'r; p! : p= den,6:;;hd :::= =rd rrn =d ene. ef 6: t= 2-"^":d 1^^% rp-9; :t= d. .: b!~.;= = L :p:-Ar Thz
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u _i .Ihe TGSS steam supply A*Wd win be switched to the auxiliary source,if the Alvhurne steam radiation level exceeds netnoint. : Relief valves on the seal steam header prevent excessive seal steam pressure. Inspections, Teets, Analyses and Acceptance Criterls Table 2.10.9 provides a definition of the inspections, tests, and/or analyses, together with associated acceptance criteria which will be undertaken for the ' TGS System. 2.10.9 1 11/23,92
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48WR onleDocumnt 2.10.13 Turbine Bypass System Deelen Deserktbn The Ttubine Bypan (TB) System provides capability to discharge main steam from the reactor directly to the condenser to minimis.e step load reduction transients effects on the reactor coolant system. The system is also tued to ; discharge main steam during reactor hot standby and cooldown operations. The TB System does not serve or support any safety function and has no safety . design basis. The TB System is desiped to OumHrv Group D non4afety related. Thee b -d:rj :6 :d :qd;=:n != 6: d&!r; cf i " S):::.v. M! hi;;h r:gj 'i e d tIhe TB System an hlocated in the turbine building - J --
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Inspections, Teets, Analyses and Acceptance Criterle Table 2,10.13 provides a definition of the inspections, tests, and/or analyses, together with asociated acceptance criteria which will be undenaken for the TB System. f 2.10,13 1 11/2192
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ABWRoule onumut 2,10.21 Main Condenser Deelen Descr>tfon The main condenser is designed to condense and deaerate the exhaust steam from the main turbine and provide a heat sink for the Turbine Bypass (TB) System. The main condenser does not serve or suppon any safety funcdon and has no
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The condenser la denhmed to Challev Group D non4mfety related. The mnin , condenser la denirned to be sunnmted under meismic concihsont
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Since the main condenser operates at a vacuum, any leakage is into the shell side of the main condenser. Tubeside or circulating water inleakage is detected by measudng the conduedvity of sample water extracted beneath the tube bundles. In addidon, conductivity is eennimueuely monitored at the discharge of the condensate pumps and alanns provided in the main control room. A sien21 in urovided to the remetor nrotectinn svntem on t<w of vacuum.
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The main condenser potendal for flooding is less than the Circuladng Water (CW) Sptem and, consequently flooding protecdon is the same as the CW Sptem (2.10.23). Condenser pressure indicators are located above A..hm w.t.
=y ;-r " ' Dood level. .
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__, ___.,_____ ..a___ __r----__..____ . _ _ t . 2 . 2 2. . 2_ _ .1. . .; _ _ _ Inspections, Teete, Analysee and Aeoeptanee Criterls Table 2.10.21 provides a de6nidon of the inspeedons, tesu, and/or analpes, together with =winted acceptance criteria which will be undertaken for the main condenser. 2- 11/23,92 2.10.21 au m n . u ., . .. . . ,. . , , _ ,. .. . , , . . . . .
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. 'AB$ Desip oocument 8 2.10.23 Circulating Water System Deelen Descr& tion The Circulating Water (CW) System Wirure 2.10.2R proddes a <4mbneem '
supply of cooling water to the main condenser to remove the heat rejected by the turbine cycle and auxiliary systemi. The CW System does not serve or support any safety function and has no safety design basis. To prevent flooding of the turbine building, the CW System is designed to automatically isolate in th e evem of grees system leakage. The circulating water pumps are tripped and the pump and condenser valves are closed in the event of a system isolation signal from the condenser area high high level switches. A condenser area high level alarm is provided in the main control room.
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r_ _ _7...,- _.. A ... E:Ehr :dp- ( g.,2 er: ef 3 ?:gk). The CW System is designed n =d ::r:"u:t-?. != ::::: 8 :: with Quality . Group D g ri9etr: nonwafety related. T': C" S;::- :=6e eri: fel!:i; :r=pr:re (E;r: 9.10.25):
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M "!:::- E= 5" =d d-i- ebb:::= Inspections, Teste, Analysos and Acceptance Cetteels i Table 2.10.25 provides a definition of the inspections, tests, and/or analyses, together with associated acceptance criteria which will be undertaken for the CW System.- 4 1 12/3,12 2.10.23
, _ - . . s s us s i c - - . - . , _ _ _== , =~ , ,
y Table 2.10.23: Circulating Water System 5 O be
" Inspections. Tests, Analyses and Acceptance Criteria
- Acceptance Criemria inspections.Tes% Analyses CertiEed Dessgn Comrnitment
- 1. C W 9, m m ' A u m .;;:!;- A +n.
- 1. Testing of the V: =!!vd: c'$e I:c'dh S;ne! Pumos trio ent _condena i
A Rooding d the4artine 5:5?d5g d!! M in d :'!: d : ; f r e nt - g ' M M S tt + prec;de'd 5/ M D,J:n 6'db . b *he- valves cfram, cr:d M W_ r,_ - .';;ir;; . UpgrL
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60 -MWh M :% as-built CW System Inceiet of an fac8 son sianalthe- will be performed using simulated signals cifGulatiDg water pumos will trio and thn_ to verify system iscistes on high level. "
; corx$entervalves close. L The as-bu3t configurWon of the CW 2,_ Constructica records w98 be reviewed and_ System is in scusrdancranth the_
t L A simetifioCconfiouration for the CW_ visuet insoections wM be conducted for the dWotion in Section 210.23, Sygam is dembed in Section 2.10.23. confiouration of the CW System. 3, insoections will be oorformed to verify the_ 3. InstrumentatnonJwurement in the Controf
- 3. Controlinom senscra are provided for CW_ toom as defmad in Seon 2_1n M-
- System oarameters defined in Section_ DInsence of control room indicators for thn_
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