ML20040F693
| ML20040F693 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Limerick |
| Issue date: | 06/04/1971 |
| From: | Case E US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20040F238 | List: |
| References | |
| FOIA-81-385 NUDOCS 8202100134 | |
| Download: ML20040F693 (8) | |
Text
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.: n c, c.. AND 2. DOCKETS NO.@AND 3531.IINAL SAFETT IVALUATIDE ',.M rif gr PHILADELPHIA EIECTRIC COMPANY,.IDO: -/ . mn. an, ., n e The safety evaluation related to the protection and emergeiicy powe;rfn.D,, ? : $ - w.
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_m ; .. v systems for the Limerick Generating Station, Units 1 and 24.isatt@$. j._ ty' The evaluation in two areas is incomplete.pa m v further.information'. Y,.
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' Q E.M.. Q.ci. ~.. , x.,X[W.e -;. M. from the applicant. The. areas.aret r..'.4 Design criteria ~for cable -installat' ion,'and ~:.4.h,..., .w" a..wwg....,?.ri.Q yW; f.M"9. s. /> .er t. --r . r :. 1. v_.,.: 2. Post accident monitoring instrumentation. t. .e In addition, the evaluation assumes documentation of oral conmituents ^3 m de concerning: '))- 1. Environmental testing, 3 ?. ..!"L. - f.~f.1,,,;... 2 Engineered safety feature periodic testing, and Jr.ly. %.,.., N,LC.;1.,.,,,. 2. + ',. ?. w >. w.. = 4 :~ g;;:, m .-. TJ7 j' l.'. 3. 'Onsite and offsite power design criteria.: ": 9 10dgWSip.d By +' y.' 4 L g.Q. ..-: -~ w
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-*;,*. r -j ESB-53 _ Edson G. case Director DRS:ESB: CPM Division of Reactor Standards 2 s .w a Enclosure i _4a safety Evaluation Distr: Mv cc: DR RF 4 S. Banauer DR DRS RF f ?. R. DeYoung, DEL ESB RF ( D. Skovholt, DEL 2 R. Boyd, DEL .s D. Knuth, DEL '~ C. Lear, DEL ^~ V. Moore, DRS 2 a C. Miller, DRS s ' D_'RS ;_E.SB 'DRS-RS ;f5R,.s ~ v i . omer y,, ~ ~ s. lW l. n. sud LLER:rc1' CA "~ 4 6/S/71 6../ /71 6 h_ /. 71... m om e. i C202100134 811019 ="a==a d -'a"=a*-=-" f Z b -_385 PDR
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..h^.l? i.. :_... 6. _ _ ],.'. .,...r..,,._ ...... m,. g. ;3,, ,. s, x _ NSTRMENTATION. CONTROL AND ELECTRIC POWER SYSTEMS Y,,,..,.. y '( m, 4, a. y-s I M$ '.I.'. - ..W .y.C, p. - u. DT..'.ys. W.~., W+,. W ACRS REPORT FOR LIMERICE CENERATING STATION ITNITS '1 'AMD~ ~2: L
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- he instrumentation and control systemsSave Dean evaluated'against'f.9..
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.2 1 dated Mi Criteria for Nuclear Power Plant.ProtectionLSystems -(IEEE-279)f.,.: u x:3 4,,,,c '.,. _ w -yi ....#. g ;,,,, ) . e.. m. y g.. : i f.V gy,. g... * - 4 >.j . 4. August 28;.1968.- A comparative review was made with the EditinW&O ;c'f. gi m S;a:t. :.yr c.. -b.; .->r-. ~.-:p... c.a:= *: . m ~.
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y .v.a 3-a features were'found to be functionally the same as those proposed for -J
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A i Hatch. The evaluation is limited to the BWR generic problem areas i -s and to those areas for which new information has been obtained. g f. Specifically, these areas are: . 2c.. ... '.,..<,,vG : f: d.3 y. ,..,;.,, W..Q. a -.,; f q .. p..% ::.... y ,; -. t- :,.. g. .;,.a g _ ~- ~..,.T::dd.a.Yff,?,.. <3; pfx;d, 'ENsNf.9. -l:a e. . J,y: ;. r. ).w ~ '?- BWR.G.enaric' ' Problem Are.as 4 [ a. f u .n g .c ~ b. Post Accident Monitoring Equipment ' ~' ~. j'J.H ' - y .wi. 7l..(-h]. ( -.. ; } . ] A,., j q. c. Environmental Testing, and. ;..,a - n ~. f, d. Engineered Safety 7eatures Testability.~. s.
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a ?..,. _n,J.. ..f ',. 1.1 EWR Generie Problems ( n e following EWR generic problems were evaluated:. u.,s ..g N-Auto-Relief System Interlock y a. ,e b. Rod Block Monitor, and [ 4,. c. Flow Reference Scram. . - ?ci. -7 ' .,,e-g The criteria for these systems were found to be identical to those j s.. _a. _____,.m__.. m..m 3: x
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.T' O _ operator. 'Es will report.3 rally at' the ERS meeting as; to tha?43. QJ -n ;% o, ;g:; *.. c. .,-.y.. f. u n. ~.clL...-,.. w. ,(:.m&., ' w.v. - g, 4.M . ~~..y -:+h , y adoquacy' f the. design 2 N D *~.,2 N,i N.M..m' [.$d 5.'.h.A,.: w w.k b = l o .....- A..: . r.m .,. p. -. +,... .-.ux. u. -.. .. y. w-4 ~ ~ ~ ~ '; n w-l ..y s. I 1.3 Environnental Testing. "c ~ J' 'the appliesnt has identified ciectrical equipment located in the .d primary containment which is required to operate during and subse. I g* ,4 I quent to an acNd*=t./The:.M. alific' ticut test procedures and tast ;,.' 4. M. ; '., - l a .y _,.. :.. p....., >~ v. -. ,.4., ~,.-.. q 3.;m u w. n. ,..y.. v.,c x .g_; _ '. -f; ecoditions't..o# assure that the 2 amp =mtij;will perform as required s.W-M.'y . l ~ ~- >
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~. were adequately identified.' D Type tastizyNE the air operators for- ^ 4 e J .,,7,, . valves and electrical cabling was not included.'.,ne -a'pplicant~has - ' 31 - e t ~ ..;. c agreed to provide this type testing. .~, r. . ~. - =. ' " ["." Instrumentation, controls,.and ;anergency power equipment which.are,. a.. required to be.functinnat during or after a design basis earthquake t will be analysed or vibration tested to assure that the design require-ments are met.. All General Electric supplied equipment which are required to be functional will be tested. De applicant has agreed to test all equipment supplied by Bechtel, where practicable. ..f*- a w 4.s. e s .sf
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..-w ,c,, We have discussed with the applicant the type te, sting' program .h..i k,n .e ... ~ - ....-..c. .. :. a >. - .. e.u. . -w:.m y. the air operators for walves and tho felectrical cabla,and.nbration 'f 3.- A .,. q. . g :gpMN,,. jv tascing of Bechtel equipment and find At satisfactory.'.When this,,-),g,g, JJ' ;l D ) ? -. 1. ~; gi f y '. _; 'f; gj.'.f '- g information is documented the criteria ~for envirocamental; testing'.will',k. M , p2. <, Wy; . ;...\\;:W:; c.. J %Cd:2. be acceptable.f = sj.. :... &.;:[ '.% C*i G, p;},,;':^.%f.v;q ', n '? M & M. :.. -Q 1 ..: -yg:. At .. a. m.. .s. n, *. e n. . ~.e.. ?;,n.. g, - r 5 &l< ~~ .s. .c
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m 1 3-features presented in the PSAR does not include all engineered safety Q, g feature systems nor is it presented in the same detail as the reactor ici o 7* protection system. The applicant has noe made clear to what extent g f engineered safety features will be testable with the reactor in'. . m. 4 v '.. operation.. 'We have informed. the app 14 cant that we. interpret IEEE-179M .~ : .". _.,.,. m.:, :: 2;m.: '. -.w -.:.c w:. g, to require the sa::ie degree of on-line testability for ~engineerod'.. < r. .. _s ^ n;. 1 s.., safety feature systems as is required.for the reactor trip system", r;, 41 ' u. s.u..~'. ' The applicant has agreed to meet our. interpretation of,IEEE-279 testa- //. ~ s i bility requirements. We conclude that when docmrw nted this will be a a w-. g satisfactory cousaitment for the construction permit stage of the,' 45 o c. e F. l review. e -p: 31 2.0 Electrical power Systems ~ 2.1 offsite Power Limerick Units 1 and 2 will be interconnected to the Pennsylvanim-q New Jersey-Maryland system through 220 kV and 500 kV transmission 4, --t n ~ :. .pg p "9
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-v ? f, ~, Power from 1htit.1 Jeeds -a -220 kV;aubstation'and towErdonD.e,.ce. '" 3 k systems.- s '. Unit 2 feeds.2 500 kV aubstation. ; 2he subs *=%, = - s. j.s.,t. .r.w. g_.,f a.,f',a .. y,~,.,... n o ; ms 4 . : c. w.- ~ g
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l .b. 1 .. 3000 feet. apart and. interconnected by da'l500-220 kTbei-tia trEndfordsid 1 l and transmission line..s.->the ' transmission 'line.ts on,its own *iridependent D " E; .., : y;. g p;.f'7 3;j. ;. : Q.^ ys,Q,'..hQ:g, yM:Sy(',.p*g, [ ~ %:L.:k _ . :-- c i: y. v.: '. =. ~. ;p.J..%:s %..;.%. :.,W.2::? ' %o ,z, . :., c.c.,.s +2~, :..
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. ~;?. ,3. ' 2; r,7-..l f, ' - configuration. = Five : transmission ' lines.=mante from the station #111.:M,#5'. 4 - q.,. n. -; ;;,; g g~ g. y >j .r~..... .. (,. t.;>. "....; q.~.
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q<ya . w, .. ~ s =.: A..gon individua!.sats.of towers. ~ Two ~1inas~ leave the 220'.ki.substatloa'n..e'R, ~ ,... :... e m. ~.:. y. - _7 ? ..... m_ ; +,.- ... s -:, <. - - .... ece., p on separate right.s-of-way and three lines ' leave the 500 kV ~ substation,* ~ p one on one right-of-way and two en another right-of-way. Sufficient i.: g. distance exists between any two rights-of-way that assures any one p event will not physically affect any other cac. Two startup =mr414=ry Q d -~ l power transformers areyrovided, one located at the.220"kV sub'ai:stion,yk .k. e ~- .~.% lii.. ..a..- r.Q. : C.. :rE :W.,n.h.%6 3..-., s.f 9*.? s, l ~. % :... :,.. supplies and -the *ther located at-the~500'.kV.. Each transformer".. tam. A. ~ 3, . ;.9 g;.. g ..-. m v..,.,. f..,. :. 0 capable of supplying power to eithar unit..... f m.,. 9. y... q f,- y.,9, 4.,,;.,_ _~j. - The applicant has completed transient 1 stability studies 'that have ~ 4 w Hj simlated the loss of each of the Limerick generators and the loss of,- y 4 J .)- the largest generator 1m the 500 kV grid. '!be resnits have shown that 2v loss of offsite power would not occur under these conditions. 2 l The applicant has orally stated and will document that the offsite j a 'k l' power systems will meet the requirements of General Design criterion 17 M e 3 .,,. 3 k ~ 2 .e _ 4 = . ;:i:, ;.n e g,...L. - -f y s,* .~..g..
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i ..e.y = c.. 4 .>s.w,.. s ne engineeredssafety. feature and. safe shutdown. loads.a.u, ;dividedg*M-.V_..- .v. w :.,. n.. ~~r, m.. s. s. re r c:.
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~s.k. Eh c,.:.c i ..,.%;.s..:,.<.n,..:.e :u.,. y <=q.,. , ~.. v. 9 between four 4 kV emargency buses,for, each..,it <such' that the operat. ion,* i,'/. r, -un ............c.,
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- unit:.will supply minimu,m safety isy.rirements:Jor2.M.r.
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w _a.. Each bus in both amits can be suppliad power from the'500 ', ,r-that unit. kV startup auxiliary transformer or the 220 kV startup auxiliary tians-j' 2 former. n ese supplies have independent and separate auxiliary
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( ~:.: %::d ;w .u.x.n *., g-Q:-Q.~,; Q from-a diesel _ generator. ;,. A total.ef'four diesel. generators arepro,M i.s g %. ;~,.,. - - s.,.. . -v - w.m:.... +.m .,, a. :.w : n .?. y s~ . g. za r.;.,, - ~ ~., vided for both intem'and nach is assigned to two amargency buses,.caa. s, .,.z. y bus for each unit. Ear h diesel generator.ts started automatically:.by - 4 a.r-...c.,s.w" g t u... .e.> 4 an emergency core cooling system initiating signal:from either unit or / loss of offsita power. ~ %e accident loads are aut<==rically sequenced,. y? a . y;. .. a on each diesel generator. ~.. :- ~ 1:'q,g, ~~. ob J 1 De diesal generators will have a conei-= rating greater.than the j electrical safety loads. Each diesel generator is housed individually e i _A 1 in a reinforced concrete Cimas I seismic structure above the'. design. ] T flood level. Each diesel. generator will miso' be a sel. f. sus +=ia4=C; '- ? so. g,, h*. * ' a_';..v;a.f ',.*C,,- J, 'i l.e,,, l '., j t i- ,s .o- ~ .e. [O y. ',. h "., *... D,, n ', *. '*1 r' .,4 g. y , '. m_.,a a " ='.. ;,,". _ * } g $. ^',,.. - ; Q.., *?Q.%** '., p.w.g..,,q 'Qs':'w' Q... . p.'...
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..*:c..,. .y .....~;~.- . m n . C. entity with its own independent. lube.cil,ifuel ett.Dacket isateFyE6V F. ,. :.c ;4, a.. :, y3....... c...;,J.
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4 lube oil cooling,.a. ir s' tarting and contro11systemsf Wour dissi1..M~p+ =....,.. ...,p. e~. 9 r A .4c.... n m. .^. ".9.m.. x, .,.Ay.. g.4 ..:...-r g .c . fuel-oil' storage tanks-are providedi.one for each yi===1 unit.(p.JEach s-J's - t n
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m.>.. . m.... s .v, .W..: ne,115 volt.a-cJystems;provided for= safety aretarranged with.ps,y. n.': 4 tuo E M W v ..~. ..,...w. - ~...:.......,..
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. physically sepamteireactor protection system. bases..for'each mit(-t.. _7.,, t,; ... -.,e .. v...,, r; f.,m.. p g y, y s... Q ne 125 and 250 yoit 4-c power supplies for each unit consists of _two !.g .a independent 125/250 volt, 3 vire systems. Each system has two 125 Fr.u volt batteries, each with its own charger and distribution panel.. D a (" .,d ~ d battery dargersfa,re.. capable ofleeping the batteries fu11y'chargedh.. :.... ..a n
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.y i:M a and exhaust ventilation systems with two fire dagers. D e batteries ~ willibe Asized to supply essential 1oads Ior a period of greater than p m r.; four hours cn loss;of its battery chargers during any plant.+didag T .M y or incident condition.,nis d-c power supply arrangement provides 4 for adequate separation and independence of redundant supplies-for 3 g -q s..., y both nita. +.z. g -~ E =
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f Jg ...e- .,y. v..n.:- . ~, l* , p,. n.. , p.. s m 'c ; ' 'P.nclosure. X Qld '?. ~~.. V ef. 7 ' M '.'. ~ ' I f.pt f.Wlf2 'O M. .,.w. s.. .:. x., - ~., e.c. ~. a n ,. -. 3.:,, ....-.c... . - Qm,>...,..r..v v..::. w: .4 n, w-g v. 3 :... . n., w.,v.. v,..,,n....,.+,... <.w. w -n..,.-p. +w .~ y 2 =e. ...,. u,. ,. x. ~, g. 2 .. r 2,,..,.n. n .. m.: ., p..... .s,.. ~..rn. 4.,,.,., y,., ,..u . ~.....,. s.. r,;.1.. '.' he applicant)has. orally _stataa and will d.ochene that.W..Mi,ta7.,,'.F.... 'li5 C'.m. w .. ~.., -.. .w v- ..a..,-.. power sys. t., ems will.be i.n. accord with Safety.Gu. ides 6 -and v. . e......... --. . s. ...R s~ -f ,.. m,d %,.., Y..;: <.. - t._, ., p.' f,[ f...*..., _ $. i. '. r.._.... ..,.,, W a*. n....). -; d'=C.,. ;, . y. f. a.,*:..... ..,.,.m-x go, x, .;. General Design Criteria 17.'1 Our review cf the pre W h y desisnt.X7. W - ,$9 =-*s A - .y A: G4.... s;. ...~..,,..,.....;..:.w.....-'._... k f,, .o. .,. y..a.-. s. .t., .......Q*.,.- .:g %.. y.. - ...b ~ ' s. . n... -y 7.. u.(.. /;
- ..also.ind.i. c,ateslt. hat safety Guidas 6 and.. 3 3-;..and
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..".v'-. & W : p..,.,,.,.u. 7 m.. .. r;Q,.- g 1 n.. R:y. .y p T @.'.} ;J ' conclude, that with this'information d~ mtad,i 5%l the onsite p % Q % k f^ fl l~ j%.? W,-- '@c ,9. R :c-M % : W.'*5'~.3. l'fW.'. ~ Q'*Wj.4. ".'v.,L.. systes'will.be.'.acceptabisUn ' ;M - ww;n-w,... ;~,..:..l.,MS.CWDM,,,I'6'd'... MMW '. . m,~. 2... m, a., ;. ~ ~ r~... m p m. g; .w y. t.
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m. .. s. n,;n.. .. ;..t. : . n j. m.....av.a.<. ... ;,... ;., e..,. m... <..g 4.: 3.0 ^Desirn Criteria'foi ca,.3 . ;.. tble'Insta11ation and7dentificationi'4. MIG.t-@9 6 .- a m w ... nn. m,. i.....,. .... 3. v... -, w .;i..... 3. .m. ... ~... s f.9 '.: .:.:v.l~gf.Yd. }: The applicant's criteria were found to be acceptable in'most areas & & b.Q ~~..~z..g.m. 3.o. n -;.g. :. ~ Vfi. y; 7.4 De applicant agreed to provide the following information:.. % rE, p. y. a. The nint=== horizontal distance separating redundant safety. ; Q.y m.f.y._ ^.
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a,- The.uinimum distance,between rerhaviant.penet' rat 1& areas.,m-"- y% -u-. s m .e.. " ' b. .-; - :. s . - ;, n .r ~.:Y s,u.v.,s pc.:.3:.. ~. - .. v>... .. m
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o,,..- e. e.- p ._= Confirmation that beat detectors will be 'io.4cated in the cablaWV"- is . +. ' ' f - 1. ?_ P '. ' ' c.
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N F,~ - spreading area and in penetration areas. y... - m. q..i~,.v.a. n.. _4;P u .~ _ a. 4 =g
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e -.s.. e.. c. courni,= ant. ..3 . -. <..<~.:.... ~...,..... .,.u...., a.. p.....~ Mini== distam - eeparating redundant wiring 'of subeystems A.,. ~. ',.W...., ,[ .n .-...A...- .n 4f s inside contro1 boards, panels, or relay racks.. ~ > ..my,;,. g ,..s. r. ~.a .e,.. ~ f. Criteria for min 1== physical separation and barriers.between.,.. .,.,...e..m. n. 1 v. .v .,s redundant' manual switches and relays 1ocated on boards, racks....~.. 2 ~ .., = - ,. - - -.r. 8.v. a. - - y %.X n. g, A
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_..,a., n,.. s.y> ~ > - We will revise the applicant's criteria and report orally"to the ACRE. -w,y :e[.,' k' f. (\\ A..p'. ".y .;..s;, s, ', [ ~ l s7 d 6 5. * - $ L.. O s -*r. ...?.... mw. 6a. a,m. >,gm $p.. ~
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