ML20024A934

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Discusses Proposed Positions Re High Point Vents,Primary Sys Water Level Measurements & Void Fraction Monitoring
ML20024A934
Person / Time
Site: Crane  
Issue date: 12/20/1979
From: Rambo G
BABCOCK & WILCOX CO.
To: Taylor J, Womack E
BABCOCK & WILCOX CO.
References
TASK-06, TASK-6, TASK-GB GPU-0033, GPU-33, NUDOCS 8307010202
Download: ML20024A934 (17)
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=L ...u { h / t THC BAECOCK & Wl*COX C0!PANY. dNs-dd p'C ! i PO'.!ER GENERATION GROUP JAR 151980 t s 6' i To l J. H. Taylor, Manager Licensing .W. F. JONES f[ D E. A. Uocack, Panager. Plant Design [lp p.,.,,, _ .C 7 From .j j-g g 4/G)* G. E. Rambo. PS&C ,.. :.y , p, r Cu st. [ 58 F " 8-3 File No. 177 FA and Cacklog 205 FA or Ref. e . Sunj. ce Proposed E1W Positions Regarding liigh Point Vents. Date Water Level Measurements, and Yoid Fraction P.onitoring ff December 20, 1079 ) i w.. -.. .- -..= - - -- ~ 4 .IN, 7 Attachments: (1) ' Proposed E&% Positions Regarding High Point Vents 8 W. = (f.p() '."j h For I -- ] g (2) Proposed E&W Positions Regarding Primary Sys'tems Water ki I ~$ 2Niedemia.Ey _ Level y.easurements p~ l P

harles Shapiro CSR gg)(3) Proposed EEW Pcsition Regardi 1 Yoid

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co. In order to properly respor.d to URC Lessons Learned requirements for high 3 point vents and pric:ary systcm water level measurements. I believe that ...;3 .d .B&W needs to take a strong position supporting those changes we feel are 6-( advantageous and.iustified by good engineering practice and just as strongly. M V.9, rejecting-those suggested changes which are not advantageous and justified. ,T.' a T y%

t l.-.pf by good.enginearing practice on the B&U plants.....k.

,. O(. i lt i i ..... /.. ? M3. ; . a. ~.- .;,.. ;^:: '. '. Jg.3 .~ .The attached positions were developed from input and c'onments from the followin_g

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.+ Q individuals: T G.. J. Brazill, H..A.. Baker. D. J. Firth and.D. B. Fairbrother...E. RJ r.an -;.,; kJ . 2. &; ~';Q r .. :t - N V.

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~ '. '. ]i h Several'of these positions are at variance with recent NRC positions and. E;.S N'ct 1 specific.custs::aer.%eb TYA requests. flowever, we feel that the B&W plants L -' are unique-in both the hot leg

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)t Abnormal Transients Operating Guidelines (ATOG) gn and in the on-going ~ -3 program. For exac:ple, hot .. f,, leg " candy cane". design prondes a ir.eans.of venting the primary system and a.G;g monitoring primary system inventory not.available on other PUR's. s m.. Core Cooling and ATDE programs have been ~on-toing long enough now The Inadequate. ' ". i R to provide p a good h:ndle on what should be the B&*d re'quirer.ents for pric:ary system venting and RCS inventory conitoring. Thus, soce recuirements which are generally f? 7 i app.licable to other PVR plants c.ay not be specifically necessary or desirable t i i ! N on ELU plants. 'l t Your review and coc=cnt'would be rest appreciated to assist in meeting a mid-7 L January cc:: sit:-ent to preparc Systc:a Design Criteria for additional instr tents. 7 E:t GER/rw Attachment . [. 'O g,u) u cc: G. J. Bra:111 J. A. Uelmer E. R. Kane C. W. Connell E. V. St:anson J. D. Carl ton R. J. Finnin T. G. l'olcott j H. A Eaker E. A. iarrasch G. D. Quale, T. A. Grand:; herg i D. J. Firth D. U. LaCelle K. E. Suhrke F. J LCVandO5ki i D. P.. Fairbrcther S. H. Dunn J. A. Castancs R. D. Davis i -... 7..,.g. .. +,.yn .f -'=~-~- ' ~~ " " ,J[(, ~ M g a:q.- 8307010202 791220 l-PDR ADOCK 05000289 ,.,.;;,/.,; ;,.: P " ~ ~

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~ -~~ - o;. ~... - . 3:3 4 : ?$ : ' _. ; ;hu:i:i.,g;-yl. ::....;;,..,.*:2 - e ~~ W. t ~ PROPOSED DT.M POSITIONS RECARDING HIGil POINT YENT: 2 / W a ? / / g.- s/ /pfco'i Purpose of the Vents .,.. k The purpose of high point vents is to provide a means for rcmoving non-l Q* condensi.ble gases which might otherwise impede natural circulation flow N~ or prevent regaining RCS pressure control in a post-accident condition. d., According to the NRC the two ieportant safety functions enhanced by this -n-g 1 1 venting capability are core cooling and containment integrity. /; 9s.. w w c-.- !!RC Reovire ents for Reactor Coolant System Ventind- -.'~ '.. ~. c-.. - ? Each PER licensee should provide the capability to vent the reactor vessel head. [p.. 3' ~ The reactor vessel head vent should be capable of venting non-condensible

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a .1 gas frtes the reactor vessel hot legs (to the elevation of the top of the outlet 3 t nozzle) and cold legs (thmugh head jets and other leakage paths.) .dditional A y*~*.T'.~ venting capability;is req...uired for those giortions of each hot leg which can. c. ~:2 .-7..' T.J. f m=: p. ...n[: u..;:i.f.t,...~..:.?:n..G:4 r.C&*, w.

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not'be-vented through ths 'rfactor' vessel head; vent.

Venting of the pressurizer W. m -. is required to assure its availability for system pressure and volune co. C.i. .a 3 m:. y ,p.. ..ia;. r 9.:.:. ntrol. p ~. .H These.are important considerations especially during natural circulation.... g..

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n . Single safety grade high; point vents should.be, installed at the top of'each 1.W ~ . ~. - $pe; .;:1 .i... ~ .. a %.:. a.%:.. v. : :-.. 2 ? ? .' s Im~... .t..Te..g.*ca.ndy c.ane$ *.The vent size should be :samil enou. gh that.a. stuc

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. 3..e.ne.:.: . y +. t8. : .w ~~ vent vahe'is (covered by the instrument 1tne break a alysis, i.e. i.ake

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>u. 3 ', ' ~ (-f can keep up with the stuck open vent valve. During an emergency the gases Id" ne should be vented directly to the contain ent through double valves as shown 7-schematically below. Separate vital busses should power the valves on the two. r-2 hot legs but all valves on a single hot leg should be powered from ti.e same a r= Y P. vital buss. t 2 i h-s I= . 1 g r i n s

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_m. .,.;,;g .,,.*w..,.. s.- ...~-- '.,.,., L.u:N w ! M. K ' -; -1 f,:: W % c.: p, .. j _._ ~ ~ c. .Ol W PPOPOSED BT.',l POSITIO::S REGUDI!:G HIGH P01:iT VE!!T / s A' R 4 b. / a / g. o t L Purpose of the Yents 4 ' c, ,,,,, -- o' Q

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The purpose of high point vents is to provide a means for removing non- [_ g. condensible gases which might otherwise icpede natural circulation flow b. 'g,, or prevent. regaining RCS pressure control in a post-accident condition. P' s. According to the NRC the two istportant safety functions enhanced by this N-e venting capability are. core cooling and containment integrity. t_N t.. % c. NRC Reovirements for Reactor Coolant Systen Yenting y, Z. Each PWR licensee should prcvide the capability to vent the reactor vessel head. ' z.- -.3 .[ The reactor vessel head vent should be capable of venting non-cendensible o;.. g. 9as from the reactor vessel hot legs (to the elevatten of the' top of the outlet . r

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Q ...+. 2:5 :..tik.%% quired for thos..e portions.of each hot leg. v.which.. . a,. .fsn :'- su R ' ~ ~ '~'$..Q; p can _

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not be vented through the reactor vess?.':,+&M :'MH-:-TM.%"t i ..m .W. - m 2.;. '- .17 - el; head vent. Yenting of the piessurizer -}' .p: a? * ? 'C:'.j -sp is required'to assure its availability for system pressure and volume control. g W.M W3 a. :,. i.. + E-5, .These are.important considerations especially during natural circulation..:. (N Y i.,~.N.h.5{Nk...;.k-: a"y. h. hk. fig d;'.?';h.. ;N ' E-h..'.h'.)??4.h+ ~ Iy' kl.i .4.r -p ....s. -. -ag. -. w;. u...... e.

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, ~. n r,.: -.. x. Proposed B&W Yent Position (1) M. , 's: f.y,~4.7 g/'"~.~t? '#~.'. ?..g.: ;.. ...a, 3

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- -- %..{.pe f- ~ Single safety grade. huh point vents should 'be installed at th'a top of each nz. .. s ,d 'a ' hot leg " candy <ane";w-lhe vent size should bet.small e k 9 . :~.:p :-.w e c ~ zc.. a. e.w .. : x. .,W4,w,d.' ne;.,..

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~, . -l ".. 35 ' ~ ~ ventlvalve is covered by the instrument liie b (p reak analysis i.e. hake-up' flow' I can keep up with the stuck open vent valve. During an emergency the gases r-- y, 4 should be vented directly to the containment through double valves as shown . :l P ~ schematically below. Separate vital busses should newer the. valves on the two. b,..- -2 hot legs but all valves on a single hot leg should oe pov : red from the same i r.. i r i f.

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3., 1 Non-condensible gases can accumulate in the hot legs and block natural GJ j .] r.L r-circulation ficw even when the system is sufficiently repressurized to collapse steam bubbles which night have also formed in the top of the hot legs. 'Thus e... q:. d.,.e 4 o :. 'a m.eans should be pro.vided to.. vent n.on-condensible gases which could accumslate fi ,:: :.7,-. .~. 2.r. :. ;. m y.c.g x.u.a. ;,.,..; 1.. ;. a,......,: ~ .... x.y.... ?:...., g.;, .g u in the' hot.le.gs..The. vents should'be". double valved and safety grade since F.'& nee A- ?. ~

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g.: they form a primary..n.systen. boundary...'y. :s.. 4-...' '; e.._.. s ,m W . f. .?.. ri M... A di . n. :n.e;.W. ?. :.:-:.-x.5 iy- ?.' E .: 2 . A:. /.._ z., -:.%.1M*W;gigV Proposed Sci Vent Pos1Nond2U.4,:.D.%?.4iGS.:iW: ~ WN :.:..~.: : ' '.'+,..7.,7.0 W b ~

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W 9.. '.~4.2.*;.".7..../.?. ,b.:. %.g .~w....=:-.. -c. .,. :.-..,.. ;; n - y !y The existing. pressurizer ' vent valve should be motorized and made safety gr'ade si ....:e.., c-.: w , with provi: ions for venting directly to the contain:aent under emergency conditions. g&~ .:Q2 ..: L::. ;.... 1 5 t ~.. c.. ' The vent size should beliai.te.d by the.instrament "line break analysis.'.The l. i ~. ', - f: . :c G j y- .~..,a..,............... pt Q~:q .._.,...v. .. -pressurizer.v.n......f..r ..e. vent valve will provide redundant venting capability in con,junctica ',., ;. g p) ,e. with the PORY on the pressurizer. The PORY and vent valves should be powered

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frun separate vital busses with all valves on the vent line powered from the W same busses. fi .s r i k Justifici: tion F,. If the pressurizer were to empty and become refilled with non-condensible gases. 1 ,.1 j 1

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Dk W. $ [, or possibly superbeated stcan. venting the pressurizer night be necessary i in order to cbtain a water level abovc the pressurizer heaters - a necessary 4 ElN;j 3 9 Use of the pressurizer step to re-establishing pressurizer contrcl of the RCS. O hJ'i spray in conjunction with the pressurizer heaters is one way to degas the v. -~ M' reactor. coolant; and venting of the pressurizer is necessary during this 1 + 9_ i -l MFrs-process. $

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1 .'4 a q.. Proposed Blu Vent Position (3)_ 4 At this time B&W does not reco::cend installation of high point vents on the (.- yc. ~ E.. 'p. 7 reactor vessel.

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4 :.h.. .i p. .I ^ 'x W 'I ~ Justification We recognize that this position is at variance wi'h the URC require:nent. ~~ s 4 liowever, we also recognize that the B&W NSS design wit. its " candy cane" hot 4.: I

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' J.;@^ flegs.is different fram the other PER designs.. We can find no compelling reason n L. S.. -ma... - - - W/ ^

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F. b M. to quickly. vent non-condensible gases which could accumulate'in the reactor.

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i'b M .:,g. u-. - 'r:n.. ~ :........ 4,.. y=g .f 9 vessel head.since there is no danger of. achieving a potentially explosive. pj p .s c yv-l head will ,3 ..'.... simixture:ofgases.in the.RCS and gases trapped.in the reactor vesse. Y gi y -@. :-d;P.gracM v:... : y %. - ?. y( Bubbles which expand-. 2 @q

  • kk.B.n,:pither forced cr. natural circulation flow.

7.s 'not -irepede ? l .?.:...> - - ii .,y ., out'of the top of the reacyr vessel will buh into the hot legs and/or.; pressurizer ~ s. j .. A 'Ewler's they can be vented and will not. endanger the core with potential' ,f : .M ..:yM.Ri '-. :6.c;p?.r." - - - f~ - ?. %

  • f.%:encoverings.'2f the RCS.could be rapidly,depressurized, it might be. des E'

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. : s.... QQ -. 9 -. ;;p y : --. - . c;,.. to be able to first vent the KV head but there presently exists no means for. i ~ rapidly depressurizing the RCS. There are a ncber of technical reasons including I ' their small size and the increased potential of an ejected rod accident which i make utilizing the existing CRC 1. vent valves for c::argency venting at pressure -ii' highly undesirable. In any case, the seal gaskets on the control rod drive mechanisms, in all itkelihood, will leak any trapped gases to the contair=ent !l.) eventually. 1 _i ^* ^ * * ' ' " " " *

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~ ' D,::t ? CT- ,i .-Q PROPCSED BM! PCSITIC::S REGARD!!:G PRI:'ARY SYSTEM CTER tEVEL I EASURE:*E!:T5 p::-(: .i Q\\ / '? Tcoj w. P_urpose of Prirary Srstem Mater t.evel 13.easurements ' .,-) N, ~ Q ?- m* * ;(

l The purpose of RCS water level ir.casurement.s is to provide:

p-4 The reactor aperat'cr informatien to follow,the course of an accident, c.. 1.

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so that he will know whether he is losing pricary syste:s inventory [. * ' ,a ~

f. An indication to "the operators on when to' operate and secure the primary

[.,;. =,: system vents, and E'.. An indication to the reactor operators of RCS inventory during refueling (,,, 3.

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.2j cperations to pnvent &n undetected leak fross draining the water level p, e.. h

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beloE the suction of' the decay heat'purps. w. .e 3* g.- c. ~ HRC Reovire ents for Detection of Ir.adecuate Core Cooling u,. c-y ~ Ths WRC requires an ur.a=biguous indication of inadequate core cooling which e '&} }' .. :.? - =. v.~ .. must cover the full rance from normal operati,on to. complete' core uncovering... r -

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1.._ :..3...;. p.- =.p.- ...,NRC does not specifically require a water level indication.' although they., i:c. .i The t - h.* ..'., a ..c.;

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.~- 6 -s do say it should be.. evaluated.- - @.3.!i -i ?- 5.. 7.:'.'s:. g .f. I. f'.Q[..... w".:......,/. ' " *L.v.-~.... : >*r..-.*,.. --'..,. v.:, - .. :e (, _... _,. [}g@ + [' ~ Proposed BSW l' eve 1 Measurement'Pestion ll)._ ",.,Q.' ~ $7, '.<;..,., S k .,;;;J Safety grade water level indication on each of' the hot legs with co5 trol room ' C [- ~ -e . fd read out.:is.necessary, to satisfy the. purposes stated above. At.this time i..,*- [y .p.a.. - -: ':. -"~ 2 (; q-.m . the preferred e:ethod is 4,. single channel per hot leg, safety grade, temperature ;. - p, co=pensat61 water level :easure=ents utilizing cne or more differential pressure ' [' sensors. The fo11 ewing goals appear desirable: The ' ange should cover the full range from solid water. conditions with the hot leg full to the hot leg t completely e:;;ty. The instru entation should give an on-scale reading with ,1 four reactor coolant pu p forced singic phase flow. The indication should be accurate within + G inches during nor=al filling anii draining and accurate 4 to + 1B inches during accident conditions. The level ceasurements on cach hot i m > 1 t '. ",C j .y ;-. wM M.*i W-L* ,9 * *O, k. . ' ' ~ ~ ~ ~ -~Q g%. g .*.}.'.- . 34 r I 'a ' '.

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.3 }R A 1 leg should be powered frc:a the scr e vital buss as the vents on that hot leg. h 2t {W(Q[ N17 A separate canually isolatable, uncompensated dP reasurement covering a L narrow range near the botto:s of one ho't leg cay be desirable for use during j h-~t-refueling operations to provide ccatrol room indication that the water level L

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in the vessel is re::aining above the decay heat' drop line suction.

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3.. - ~, =- e dustification m,...:. - o Hot leg water level ccesure:sents in conjunction with proper operator instructions 1 3 w- [ satisfy the purposes stated above. Differential pressure sensors appear to {. be the only co::cercially.available method of water level measurer.ent which can nm" '.7.:. p. n -- 0 ..s ~ satisfy the need for a reliable, proven, safety grade method with a long life, y=(.e 4 [rr. 2 expectancy. Temperature co=pensation is necessary because of the very wide Ec ter perature range over which these ceasurements need to 'be fairly accurate.- a . - $5'~bhk&.Y$:. ' ': l ~ ..C: ssM. ; ' v T'- :':Q". W.. p--

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SP 7.'E 5-Propesed BW tevel F.easurement (2)Wy.: 'W. >3. f....:-:?-@.L. W..~r- .G 9 n.... ,.~ E.4 .~ .BW does not rects: rend installation of a water level measurement between the '". r -T p .ggg .;..s:,.f ...g ~. ,;,g * ~,',. M .3 ., bottom of the hot les and top of the reactor. vessel head.- '5 hY; ".'tY.'--W'yr2&f'ki'er=:&y&. 3-n$p%.n W f, f'.iti. c.l.c-:;~ 3 ~-<*y.. q)&;:...).... -: d'6 6.c-Z: .q. ...J Q--=,j

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.1:: '; ~.. -a-7L. '.'h s ~:....... c p .gz . Such a measurement would allow conitoring gas or void accumulation in the top - ^ W x-sd,- ~ of the reactorYessel head and provide an indicad.on as to when to vent the...' k M;h 2n

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. +.:. -~ y_ g:: :.. D e.; ; :. J [.. _. _ ~ '.' :.. - $pp .y, reactor vessel head.;(Howe.ver, since bubble formation in the top of the. reactor... : vessel he.d per se does not endanger ade:;uate core cooling or natural circulation, [ e.. high point' vents on the reactor vessel head are not' rococnended and water level-k,. L measurement in the RV head is not necessary. Such instru:sentation, if it were m 1 installed, increases the potential for small break LOCA's. The small break L' t, LOCA potential is a:plified by the fact that the nV hea ! is a highly congested E. q c area and the pressure sensing line from the FN head would have to'be disconnected 1 and later reconnected and vented at cach refueling. h. - w... ; -- -v...,' m- ^' 7.r,.,q w..w 3 s,g. -,m ;. - m p \\,. F

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-Nk 'i.- f y-l p j Proposed B'.H tevel Measurement Position (3) 4

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A water icvel measurcment should not be installed across the core region of g 3 h the reactor between the botto:a of the reactor vessel and either the bottom g of the hot leg or the top of the RV head. it;- E.- .:n i e.... - L Justification 0" 1 The hot leg level r.easurement provides the reactor operator the neans to.- W-r m.- c-.- follow loss of inventory down to approximately 18 inches above the core. - p., ~ Once the water level drops to the core region, the incore thennocouples .i {1,. provide a core reliable and accurate measurecent oi inadequate core cooling m ,g p:- b.y E. 4 and core uncovery than a water level measure:nent can., water level measurement c. cannot be made an accurate and unachiguous indication of core cooling

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.4 because if the the water level were to fall to the core region, frothing l r.. will provide heat transfer over a region not accurately defined by the C. ;. D . collapsed water. level measured. Also, since the core is a nonunifons heat.. ~ :: 'iy; 4v.

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=. 4 - Q ? 1, w ~'- " ' source ~ proper temperature cc::pensation::of-the' indicated water level.~is ?..g."...~ ';.-- D .. ~. g. ,v,._... .5 impossible. This probina appears' to negate any value of this measurement' : ~. GL ~ r ..~b y ,, : ~ : as a trending conitor for the reactor operator during an accident. '. The In. '..'. :...... N.;. ..- :... n.;.%..? a.- .'.. :- "- i: n. -:-w.. W . adequate Core Cooling Guidelines specify additional action based upon incore '. ~ - '"- Y m ~ M '.... -.+ w -thennoccuple readings a'nd we do rot anticipate that these criteria would ?.--

.7 change even if a water level.

m-e.,. .,a reasurerent were available across the reactor core. ' ' rad - ;f.w . ~. d- . _ Thus..BW feels strbngly that a water level r.easurc:nent across the core should:;'. '.~,%. t,;;. h,..]- t., r g-

.- ;*';, *,;f *'&K.'.'h".K. *. %'$.

L.=:' -;~. ~l WPA. ~. ~~ =4 ~ pot be installed'because n;ot only will.it not provide interpretable andh;" - -

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' unambiguous infor:::ation to the reactor operator during the course of an p l 1 accident, but it may increase the potential for a small break t.0CA, and a 4. 1 l r small break at the botto:a of the reactor vessel is very undesirable. 6 i

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~ _. ~ ~.. >... -- ~ c-~.. l u. WI { 4 [4::Q l -i, l t PP.CPOSED B&t! POSIT 10'l REGARDII:G VOID FRACT10;i }C'!ITOP.I!:G t ~.c l ) Rl l

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y 5 CQ1; l f 1 kTc0 i 1 Purpose of Monitoring Yotd Fraction !O-..{* ? r Monitoring void fraction during forced flow conditions would provide an U).-. indication to the reactor operator or input to an auto:natic system of T-- O,s.. j changes in reactor coolant inventory in the loops and a basis for tripping '... e c reactor coolant pu=ps before voiding becomes so significant as' to inhibit M+.. u-establishnent of natural circulation flow. 4 Ei: b S .l ,s 1:. I n.4. a ..- ~ :: r N'~': MRC Requirenent for Yoid Fraction Monitoring st- ' ~ j There is no explicit tiRC ' equirement for monitaring void fraction except' - j r as it impacts the indication of inadequate core cooling which clust be h..5 1 unachiguous for all conditions including high void fraction pumped flow. l t... \\ .a ~. - s v.c. . 1:..,: i ... :..... a..- v..

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.r c p_2 .One or more methods-for determining if a large void fraction exists during %)i~ h;. ...g..... z. .,, <y . for.ced. flo.w..... conditions s,h ul.d be developed and -implemented..The methods under.. 'py-- ...z... '. -Q EE y .n~ ~ M. *MS%M:.).::5&-k.kEbb!.h.'.N.Ff.c,_.. 3 P-+..... '. I...$,.[ . h consideration Nehd h

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^ of void fraction can help the reactor operator distinguish between an overcooling

f..

u. [ transient and a,s=all break LOCA. Low RCS pressure concurrent with significant y. l 1 2 E voiding as dete:sined by reactor coolant pu=p current ceasurecent is the present a criteria for tripping the reactor coolant pucps in an ' accident situation. While f c. the best acthod'of =enitoring void fraction has not,yet been determined. this y ,s should not delay the plans for impicmenting a hot leg water level indication. ......,~...,w....m. a.,.w

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o ~_ - L-- 3 g r.- - - f-Q f ./.. pr-e,:~rm ? d ;'. b...g: !,0". -~ n r. W:... o. " -- O THE BABC0CK & WILCOX COMPANY c.i r-:.4 r 'r - g ; % M 'ij.., L,j POWEP. GE!:ERATI0ll GROUP ! p,-H To I E. J. Bateman - R&D Manacer NSS Systerts & Components O J. R. Hamilton - R&C Manacer,, Advanced I;SS Systerr.s 1 '- ' E. F' rom F. Boulina - Manacer. plant Protection Ecuter ent j i P.. E. Braurailler - New Idea Coordinator, f;PGD (2337) j 1' Cust. sos us.s, I p;y,go,413'130i7-l W or Ref. Subj. t;ew Idea - Subcooling Margin Indicator; R. H. Ball and Date 1 ~ i E. A. Womack Octob<.:r ll,1979 lm....,.........,. o s c.. Attached is a copy ~ of the Invention Disclosure Record which was prepared by the inventors for our Pafent Department. This information is forwarded ' /( k for your use in your R&D ProgranV;;SS design activities. This new idea is being processed for possible U.S.,,atent filing. There fore, please do not disclose this information to the public d:,..ain ortor to the date on which we intend to file, i.e., esticated at 6 - 12 months frca this' i, date. L !' o A 2 ~ .COMRDEMTlM. 4. FAJ. l ,..z----- R.- E. BraumiI. er ~i - M: ~ l REB:efe .,,j2 1,-

.g.

'.N [ i. '~ Attachcent ..,..+.:i. . }* cc: w/o~ attachment ..~,1 i R. M. Ball E. A. Wocack ..;J

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... ~ .9dk Exh. For ID . - = -~-cs.- . Charles Shapiro CSR } g.7)f l ] ,.Dcyte Reporting Inc.. g l ,,, ~ ~ - .' ?,- a .-). O i ~ ;in... 8 F' t ~ .,.. g. 2 :: :c N.... ~~ _ 1 r.

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r 3 --- ,s ~.w _-? -~t, & [35 {;l US.i. HC BABCOCK & WILCOX COMPANY l ",[;y-g.l' INVENT 10N 01SCLOSURE RECORD O oAft 10/4/79

  • tyj i["7' eAs ni - 13017
  • ElU'i o" 79-5-4
  • f

.i J fois eecare.: sa. :.,i en sessi' sec.e.t. re.. ines ' eke core la its ca sinie ereseration.., sees rev ti=e nas 6 asea- - ~0 i eeaieace leier. Insitucalens en t.cn es inis snesi sne le ne eens corenell, teiere lisilas la sets. I g (Ae lhttNTG4a f uLL Mh4 $i 423 YGuA I I TLt On PM4 T IOh 433 C@eFA hY D4 W 4 5 4 GN A7t3 4E A T 4 G4 Edgar Allen Womack, Jr. ager, Plant Design Nuclear Power Generation i [l1 Russell Martin Ball Manager, Product Develo Babcock & Wilcox Company 6 "*"* ~ Lynchburg, Virginia {' s5l DESCRIPTivt TITLE OF i pestssti tPs Subcooling Margin Indicator - A device to detect the loss of subcooling in a hydraulic loop [ ) c i L ] ic s etScnaPt sos or swvtsfions. he te caseisisy metee tal suggesses ser enciussen.an.ines sescrisuaa. As.ser.ies en se sect 6es f; (c) eiers,(e) inreusa (en en nac. es inis sneet. See attached sheets 2-5 b

DB DATE A%D PLACE OF. ihytte s iCoos Lynchburg, Virginia

{ e s t c %ct Pf s os av invCwton April 14 i, 79 AT

riasi sutica ca enAes=G April 14 to 79 At Lynchburg, Virginia rinst aniTTta otsca Pfion m y 15 is 79 AT Lynchburg, Virginia
  • Osi oiscLesto To iAs maw. Nelson S. Embrey April 23 i, 79 AT Lynchburg,, Virginia

+ ~ sei u w Richard E. Brausiller my 31 s o 7b ' At-Lynchburg, Virginia E b'.. i sai uootL on rutL Sitt otv ect. consatttto by 25 'e s 79 - AT Lynchburi. Virginia a esi rinst etST on o*caAfion oP inyti:Ti en my 25 t e 79 AT Lynchburg, Virginia iEl At5vtTS cr TCET5 AND ERTENT OF USE OF INvtN T B 04 .f-1 Invention has been reduced to practice and performed indicated function; demonstrated by h Babcock 6 Wilcox May 31, 1979. ( L. - L? ^ iF3 NAuCS OF THE.OTHER Ptm5sps5 MAvipeG specutEoGE OF FACTS STAf to UNDER Sectio 885 sol Afe, i El 1 ~ Paul E. Perrone, James P. Jones, Nelson E. Embrey, Richard E. Brausailler - 9 :', ~ I g. g.. l sr h' t. f, )<! iGl Pi t f i %C hi A LP OR T S. P A T EN T S Aho consP Apsf PATENT APPLICATIONS l Parallel Hybrid Safety System Patent Application by R. Bail and R. Roberts (Case 4281)

  • l 7

l h .r-Ps0 JECT C4 PRCPCSAL OCsiipsAfices. [ e 'TMtt CLOSCLY RELAf ro PUBLicAT,00NS. 3 r, i 1 9 n. (*) Added by R. E. ' Brausiller, 10/10/79 p-k- I L 1 --m .,,.. ;., r.T. w -..NJ 4 b. b ' ,.i

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" Sv i, 1970 NPGD NEW IDEA AND SUGGESTION FORM Q %=~; DATd j 15, 1979 TO: NPGD NEW IDEA COORDINATOR. DEVELOPMENT ENGINEERING THE FOLLOWING NEW IDEA OR SUGGESTION IS SUBMITTED FOR CONSIDERATION i DESCRIPTIVE TITI.' OF NEW IDEA OR SUGGESTION: E Device to detect and n'easure the loss of subcooling in a 7 ~' hydraulic loop. L 1 BRIEF DESCRIPTION: __ 'A device, as' described in the attached sketch to compare

f. -

acasured hydraulic loop temperature and pressure to stored,, g.- values for saturated condit. ions of steam and water, and to provide.the devige user with pressure margin to saturatioh, [g teqperature margin to saturation, and with an alarm indicating

@b that, a preset margin to saturation has been exceeded.

i l I j ADVANTAGES OF NEW IDEA OR SUCGESTION: L 1 I l The device, as sketched', ut il i::e s the parallel hybrid concept h of imp 1' mentation and c,an,therefore, precisely contain the I j-e steam saturation correlation between pressure and temperature f as well as any other corrections (including nonlinear behavior) er ..._.__ h.ich_may be seeded for_tecutacy in the particular systen__1n_ y~ w _# _E 1 - - wh'i ch it i s u s e d.. ' T t' 1 s Ta pi d Iri tr5po tr(F E-' w i'l I yTUvi de..

  • the use'r with direct indication of margins to saturation on I

continu.ous reading,b, asis. i j DETAILEDINFORMATIONAND/ORDRAWINGSATTACHED o q k_ 5, SUBMITTED BY h__ M w. p. THIS IDEA WAS CONCEIVED AS PART OF: [, y-B&W CONTRACT. R&D. OR DISCLOSED TO AND UNDERSTOOD BY ME [ PROPOSAL NO. THIS DATE, %v.h. . 19 ; 9 C GOVERNMENT OR OTHER ~,,g,. l b sign.ture (/ L CONTRACT NO. i. DISCLOSED TO MD UNDERSTOOD BY ME F

l THIS DATE.

%t+1 3 / . 19 3 $OTHER e 4 O b*e/w/ k u&n, l s1 = r-3 [ - l t .m.,. . c. = l.;,. '.u... ' Y. P ,. ~ r

Y ?=' ~* l -w pgl 0 ThE BABCOCK & WILCOX COMPA O Pb 1[ N I POWER GENERATION GROUP bh hfihM h,[M

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'.~ a.. _... q ~ ' w 4 m i Froe %\\5 C R. M. Ball, Manager. Product Development (2810) m es Cu st. File No. j or Ref g]* [3 d Su bj. Date Patent Disclosure ~~ October 5,1979 um g w.. i I,= r-I am forwarding this through you to Brauniller. I have not sent anything directly to the New Orleans Patent group. F Under C.a. The only prior art which would apply to this system that I know r. of would be the use of a book of. tables (Keenan and Keyes) or the use of a

y..

computer which has a look up table or computes the right answer with some special algorithm. J Under C.c. The distinctive aspect of our invention '.s the use of a memory with pre-determined or pre-calculated outputs for each st ce of the input. These inputs are determined and are directly addressed by the analogue-to-digital converter. i \\ 7_ r -.-u---------- h a ~~ - ans % -t.;- R. H. Ball ~~ ir . RMB/ow w ' I Attachment b (. ' .s 1 7 r Disclosed 20 th: jtacgby r ,a, azz p Direbteg. 3 ce ty.1, W unbre ec:g 3 7 1 /47- ' ~ r O C s ) F i a l m o ,n g= . ~ 'r >~,_fM -lw " [.*e

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1 o e d) ' ici j-THE BABC0CK & WILCOX COMPANY I 4- - - POWER GENERATION GROUP

(4l Oo

~ s Wl.' i T l M j RE. BRAUMILLER - RGD From .[ {._, ; sos eas.s E.A. WOMACK - MANAGER, PLANT DESIGN ( F.XT. 231S) Cust. File llo. j N orRef/JZ bety i Subj. Date OCTOBER 9, 1979 $3.. PATENT DISCLOSURE ~ ~ g n.. a.r In response to your note to Russ Ball and myself, dated K October 4, 1979, I am responding herewith and returning the R L; '. package of material related to our invention disclosure record. The material attached to this memorandum is the (e(*.- original. I have not.sent anything directly to the New Orleans I' patent group,except to respond to a specific list of, questions related to this item received about three weeks ago. f, 1 ] Under Item C.a., I.would agree with Russ Ball's thoughts,with j the addition of the possible alternate us.e of an analog device. e which attempts to simulate the saturation curve in a piece rise [' manner using one of the function generation formats which can be P O-had*with analog equipment. P b. = 'Under Item C.c. I concur.with the infor=a ' ion provided in Russ's I I . ~'. s e [o' o f ' ct ab e^r',5. " - : -mm.~.x=[5 0 m[- Please let ne know if you need additional information. J I :.v ~ g Th an k s,. s.- ~ C. O..uoomaac IcLAn,. ~ <: a EAW/ dab [ cc: R.M. Ball s. L. DiectosN to a.4 c U cre sed i37 1 t Eo'tt.Lt Q C g p g ?[ i ~ ~? ] !s/ [ Uittlosed t.> nd un!ereter.d h*, [- ~ se thi-94 <er p o ?- 1 Et

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    • '~

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_ J ? - u.,.,,. i M ' rE b 1~, 78dF#Gl' E . Inv m 29 Date:U M Fit If;t4 " # 41 A#.Ges'f, . f N - u A /[l.1cDate: Ai t isp+, rg x ) i r i ')isclosed and understood by me this 2 M day of M , 1979. f e-s. s Si9ned: M/4/h / 4+64:47 I x,n e..A sn .,s .,a. w-a. N A V 3 7~ ~~,9 L gg. [ re ti1 N igj &bd kUMEIAk. _J .,;, r. --...g., _. -- +,.z p.- s- - r - --- - - .= ~ . p* Lt.w -:. <.%- -: I ') b l l.

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