ML20126D068
| ML20126D068 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/09/1980 |
| From: | Thorpe J GENERAL PUBLIC UTILITIES CORP. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| IEB-79-05C, IEB-79-5C, NUDOCS 8004150621 | |
| Download: ML20126D068 (135) | |
Text
GPU Service Corporation s.,
f.
WWe 100 lnterp ce Parkway Parsippany. New Jersey 07054 201 263-6500 TELEX 136-482 Wnter s Direct Dial Nurnber April 9, 1980 E6L-2274 Mr. Harold R. Denton Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Denton:
SUBJECT:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Docket Number 50-289 Operating License Number DPR-50 IE Bulletin 79-05C Attached are copies of two B&W letters which form part of our response to the subject IE Bulletin.
These documents have been submitted by other B&W plant owners, but were never formally submitted by Met-Ed for TMI-1.
These documents are applicable to TMI-1; however, the operator guidelines have since been superceded by B&W Document 69-1106001 included as part of the TMI-l Restart Report.
Very truly yours, R
J. R. Thorpe Director Environment, Health & Safety i
l JRT:CWS:bjo Attachment ec:
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3.6.
~he core cutle: pressure and 50 and pressuri:e levels versus ti=e are given fer be:h cases in Figures 2.5, 3.9.
~h's analysis shows tha: the syste= t ehaves very s _ssa. s... v.s.u.. a.. ya.
t.
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- z..'
5w-a..d 'e. e s s".. ' - *.-
e levels versus :i=e are given fe; be-h cases in Tigures 3.c.
3.9.
'his analysis shews :ha: :he sys:e behaves very s' a.Sv, v.'.5. a > v '.'.... e... r, a.... u g a.....'...a.'.. -.. '..
B.C e"., ' 1. ". do=.s see:. o h e.' r ~.'.. ' a. e v '.'..' - ~. a. ' o.
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ex'..' b '.. *.> k. v. a..~ c '. 5.
cases analy:cd abeve. ?:evieus an:. lysis expe.rienee (ref.
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s.. '. c ~.... v A general assessmen: ef Chap:e: 15 nen-LOCA events iden:1f ie.
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1:. reased due to :he eddi:1:n c, 2... pun? : rip :n "
^2 a
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ev...s
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i o.,.
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A.al sis 5:0:e *aith.G! Available 1
i Centi:uces ?.0 3:eak leca-i.
=== eeera-1.
7.0 p=p rip G 900 veid
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t
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c e _ s. n.. ;
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able 2 *,. ~=pse: Assess =e.: ef 3:eak Spe:::.=
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n Break si e (f-4?,
Cere *.meeve-- 01.e (see) 0.10 550 0.075 625 0.05 575 r
s c.,. s n. a n., e L...a
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a
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No.es.
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Co.e ".~ov=...r ~.'.e's~..~.=.~.'.'*.
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Table 2-3.
Ce:parisen of Sys:e= 'v'eid 7::::icns a: IS7AS Sic.11 Sys:e= veid frae:ica
.._A_>
a:
- . 0 :
3:ea.x si:e, (f:^)
?=es en
?u=:s : iceed
)
0.02463 0.0 0.04 4.47 0.05 0.04 0.055 6.74 0.07 S.06 0.075 0.c0 0.085 S.45 7. e..
- 0. 0
...i o
0.15 10.70 0.20 6.78 9
4 0
6 5
1 i
a.
- e
4 t
i
- v. A,....,, a
- u... n r s. e. ce.... i..,..
Nc3I ct3IR p ? a m...3.....,
.v 1,33 Rese:c: Vessel, Leve: ?len=
2,34 Rea::=r Vessel, Cere 3,35 Rea::c: Vessel, l';per ?le==
4,10 Ec: Les ?i71:3 5-7,11-13
?:1:ary, S:ea= Cener::::
8,14 Cold Les Piping 9,32 Rese::: Vessel 3:s=== e:
13 Pressuriz e:
16,24 Stea= Genera::: Ocv. ::e; 17,25 S:ea: Genera::: Lever ?ien=
15-20,26-25 Secondarf, S:ea: Oeners:::
21,29 S:ca: Risers s.,
j Q
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.)
4 w.
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m.
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Core 45,46 Core 3y;zzs a,.c,, 5, ", ' ', 4.'
"me. L c-S. ' c.a...
d 6,7,12,14
?:i=try, s:ca: Genera:::
S,15 RC ?=ps c,,.' '.
C.' ' ' a t S'
..r 10,43 Devn:::er, Rese::: Vessel 17
? essuri:er Sc:se line 12,19,26,27 S:sa: G enera::: D:wnecce:
20,~1,25,29 Se:::dz y, S:ez: Gene:::::
22,30 Asp:. ::::
22,31 S:ea: ?.is er 24,32 S:ea: ?ipi:s i
2.5..*.*,
- .-u..e.S'.r d
34,25 3:e:h (e: Lesk) ? :h
)
36,37 E7I 3 :,.s e,,4,,,*.-
k a-40,41 F.ain Feed ?=ps i
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=
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Tir 2-1.
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Introdu:tien Guidan:e fer eperater a::icn, during 5 th LO*A and non-LO A events, ::
a:: un #:r the impa:: Of the R" pu:p trip recuirement of IE bulletin No.79-050, have been developed and are presented belcw.
The general intent of these addi-i:nal instru::icns is as fo11cws:
1.
Tc establish the basis and :-i eria fer a RC pump trip and e.....wj.5 a ra.s*.$.. c '...'. =. r. ". : "...., s, '. '.
p.,,.... s. e.
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1 Se::icn VI pr:vides the " Operating Guidelines for 5:a11 Srsaks" updated ::
i.".a. s a. -". i da.' i r.a s, i n i n-l ud a.
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4......=-. c '. *. ".. a.'r.". r "....p
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3 y
general, apply t: any abner =al event where a RCF trip is required and will be used as the 'casis f:r revisi:ns :: emergen:y cperating precedures and cperater training.
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f fra::icns during the initial stsges of the transient when the systa: pressure is still relatively high. The c:nsecuen:es of these p:stulated events with
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9 Te preclude the p::entiai ::nsecuen:e Of an un:imely R P trip, the RCP's will be pr:=ptly shu ::wn when R 3 ::nditiens indi: ate a small break in this si:e range =ay be in pr:gress.
This a:tien ensures safe plant con-diti ns as de enstrated by pas small break enalyses, under Appendix r.
assu=ptiens, wherein the R: pumps were assumed in: perative early during the transient.
In the interim, until design changes can be made t: aute: ate the RCP trip,
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a feilewing ES?!J a:::a-icn due :: 1:w RC pressure (< 1~C0 psig).
Table 1 cutlines :ne :eneral dia:n:sti: and ::nfirmat:r.v a:-iens w.ich wili be
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1 ult.s. 4.n
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These i:=ediate a::icns apply to any abner:11 even: which results in aut::atic ESFAS a:tuation :n icw RC pressure and will be me:Ori:ed by rea :Or Operating pers:nnei during training pr: grams.
.he -
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- riteria (iew pressure E3F;.5 actuatien) was chesen ever c ner p;ssible candidates be:ause it is a : lear, simple, and early indicati:n thr.: a small LOCA r.sy The visual indica-icn and ale'.r:s in the c:n:r:1 r::: fell: wing l
be in pr:gress.
ES?!.5 a:tuati:n aise alert the cperat:r :: the status of the plant, and ne d a. - d..e i.,... - =. s -..
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tha: an RC pt : : rip is ne:essary.. With pr::edure :hanges ::nsister wi-h
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1.
Criteria for RCF Trio Upon autcrati: a:tuati:n of the ESFAS due t: Icw rea ::r ceciant syste pressure, RC pump cperatien shall be prc=ptly teminated.
I...e. f a *.. A.. e..n s
2.
Upon receipt of an E5FAS a: uati:n (indicated via audiable and visual A.
- w.,.,. e..
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that RC pressure is less : nan the 1:w pressure E5FA5 set::in: via examination of wide rance RC pressure instrumentatien er E5FA5 Trip St.atus Indica: den, if available.
B.
If RC pressure is less than the 1:w pressure ESFAS setp: int, R* pump operatien shall be i=ediately terminated by =anual depressing the in-di"idual RC pump trip swit:hes in the c:ntr:1 rect.
NOTE:
If the ESFAS has been a uated due to hich P.5 pressure, the operat:r shall meni::r RC pressure and trip the R: pumps if pressure de:reases belew the E5FA5 se:peint.
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III.
Criteria for F.C? Restart plant ::ntrol f:11cwing abnormai ever.:s, in:1udin: small breaks, is 4
gres:Ty improved if the R: pumps are Operative.
a'ith for:ed circu-lation cf rea: or :::1' ant, the steam genera::rs and asse:iated auxiliary 1
systems are Ore effe: ive in re :ving the primary system stored energy and de:ay heat. The piant is also placed in a ::re "n real" ::de Of operation where : re faciliar pressure / temperature :entrei pro ecures can be empicyed by cperating personnel. Theref:re, to :: pliment the RC pump trip criteria provided in Secti:n II, ::nditiens under which an R; pump restart is ailewed have also been identified. These : ndi:icns cover b th LOCA and non-LOCA events and have been carefully chesen to pre iude the devel:; tent of excessive v:id fra::icns for s= ail breaks where an RC pg=p restart is allowed.
Table 2 lists the ::ndit'Ons under which a RC pump restart is all:wed.
For each tenditien, ty;i:11 even s fer whi:h they apply and a brief dis:ssioncfthebasisfertheNCpumprestartisprevided.
It sheuld be noted that a RC pump restart is n:t allowed unless feedwater is available to at least one steam generat:r. A cr ss-reference to the appr:priate se::icns of the scall break guidelines where s;e:ific inf rmati:n can be fcund is als: given.
Furthermore,'the criteria given in Table 2 are not new as each was previ:usly issued in past smail break guideline submit:als.
B&W has reviewed the guidelines in light of the break si:e and syste ::nditi:n for whi:n a R pu ; trip is repuired and has ::nfirmed that the RC pump restart guidan:e is still appr:priate.
i l
.a....s.,w
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l i n.e.. s...s.
- 4. n.., w. >
, sy,,... r.... s s.a. 4.,..,.4...
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ea f
. n.n.. z........... s...a... >.. s.....s.
n...n....n.....,../.......
s
.a....<,
s,.,u.. 3,. 3 r..
fer wni:n a R~ :::: estar: is all wed,
?:r these abn:r~a'. eve-:3.'resta":
ef :ne R: ::::: is e:: ren:e by ORW sn:n tr.e "ur: Resta-.:riteria is 5::is-7-
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e e
e 8
e e
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LCCA events, eer whi:3 e g; PU:: trip emay be initiated, wil; thus be revised :: in:1ade the pe : restart criteria $
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I IAnt[ 2: RC Pt#1P Rf 51Alti filllEnl A
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Ill50tK510ll EtHttillf ute IOR tutifil IfrICAL IViril5 full 113510t10110lt 10CAI10!!
2*I A ric1r lef 51 Alt! 15 All0MID tall (il A PCP fatSI Aftf lll SilAt t Ilftf AK GUIDit tli[$
(51Clluft) 15 AlIintin folleulng any reactor trip event during Fegain Coolant Sul(ouling
- 1. Small teak 4.3.4.3.2 whicli the RC pu.nps becemie f ouperative
- 2. Small Oscak within (loss of lu>uer doe to status al causes/
1.
P-1 (omit tlons indicate capacity of Ifri sys.
c< rale==rnt f alluees or due to a irct it ciate (onlant is > 50f subcooled.
- 3. IsolatcJ 5 mall fir eak trip inillated by ttic operator). the ITC
- 4. tion 10fA Overcooling /
punips case be e cstarted if HC (on.Iltions
- 5. loss-of-Of f site Power ase stahllised and at least 50f of sub-depressurtzing event twent (noling is indicated for the esisting P-I state. If sul<ented teniditions aec luulltated, the pe laae y and secesolan y sys-tems as e illecctly (nuple'l (ie, deoy heat rc==ivat via natui al cle culat tunh and if a becash of tiie primary peessure boun.lary is in esent also, the sesulting leak will tic ullhin the capacity of ttie ILC5 systems. the opera N r should restart the itC insaps (1 la. each Inne) ectuen to low % level (unte ol. and protect with a plant soutilown er stalntain the plant at hot sleutdown lf the initiating event is coirectable an.1 a retuin to power operation possible.
It0l[: the subcooling criterla will tie lle principle Indicator for a htr nestant for non-t0CA events.
&cpressurlastion Cestain small treeaks will result in a I.
Statile or increasing
- 1. Small Break witiIn capacity
- 4. 3. 4. 4.1 system repressuetration due tu som.cntary peessuse with PRC5
- of IlPI5 Inss of the % as a condensor for primory
- 2. Overcooling /Depressortration sysica steam (le. the llPl$ 15 seilllinp Ifdpi psig.
event the systrs= and a steam buhl.le is trapped
- 3. Isolated 5snell ttreak within the het Ir.gs alweve the % tid.es (unilesising sue f ar e). Small ta cals s.htc h produc e this primary syste.n 1,chsvlor ase sufficiently small such that high vold fractions will not evolve if the DC pomps aie restar teil. A htP sestart is thus allowed; this action will e.nual-lee primary and secon.lasy poessures and temperatures and touple the palmary anil secondary systems such that an orderly (noldown and depressurlaation of the 905 can Lee at(twplished. Settlen 4.3.4.4.1 of the saiall becak guidelines would
pt i 2_ Cl
)
til5t:U5510ra (tWIDillful Illit Will(.li
- Iffl[Al. IVittl5 T0tt insinttCil0tt 10tAllOil A l'imir Itl 51 Ant 15 tit uutt) h'lll(ll A Ittr It[51 Alti Ill 5ftM L ftttf AK OllD[LINf 5 15 tillmII)
(51 C110f!)
apply to a very small becak where a sys-ttm e eptessuritallnen innsld u(tur early (le. ps lor to initlatlun of the se(umt.
as y systeis depe cssurisation). A Itte rest ar t asul s esulting alrop in the primary system pressnic to tliat of the secon.l.
an y st le may allow tlic III'15 to establists a sut coole.1 pr imary systria.
Systrae s epuessurliation al ove tlie low psessin e lil AS setpnint f or non-ItK A event s is also an acceptable (enullt lun for an itC punge restast. In n.ost cases, liio.aslun 1:C pressue e will also tenit to e e-establista the reactor (uolaut sub<nuted ese gin uht(h. as Imitrated above, is the prin(Iple lmiltator for a Htt nestar t for nue.-t ait A event. A pump ecstant,t. hen systeia pe essum e is ahnvc the 15t AS settailut
- s. hen tiie 501 sute(noted mean gin is not yet establist.c l. Is pcomissable sin (e small 1.ieats f or i,hicle a ItC rwip trip is re-spolic.l ullt not prostute the system t.chawlor.
- 2. Increasing system piessure Small Break 4.3.4.4.2 4.3.4.4.2 of time small be cak guidelines applies ilue Ing the (anidoint ps aten i.here sJiere rit05 > + 600 (psig) ti.e secon.las y pe essur e has i.een eamially due ing (nel3oun ps ocess, o rduced loclow nois.a t conte nt (l.ot strat-down) setpoint5. A poa.p I,w.p t.:nt eJ.n e is stipulated, lhe Intent of 111s a(tlon is to min the system 50 that stram (an be condensed to allow a system seftll, if a refill and subrooled (omittlons aie s et estatillshed, the 600 pst decrease in primar y system pe essure will ps event higli HC5 vold is ottlons with an Rtr restas t per the guidance prowlded.
IInal Iransition to LPI taallas.
5tal.llied pressure with 5 mall Break 4.3.4.4.3 for (crtain small Incats, a prieury system refill stay not he possthle until Inw r$5< ItW) psig and pnC5 pa lmary system pressin es are achieved.
IADIE 2 00!!!*D Ififtulilliff f 0it 1:111011 1YplCAl_ EVEll!5 IOR lil51RUC110rl 10 Call 0tl pl50115510ft I
A 1luu* lil 51 Alli 15 AltinflD Util[Il A ItCp RESIAfti Ill 5tlAll. IIRf AK Ctllbil.Irli s 15 All 0MID (SEClluti)
Continued operation of an RCP is also 1
allowed since tfie LPI systein ulll climl-nate tlie potential for furtlier increase in flie system vold f raction.
In.ideiriate Core Cooling Small Dreek II/A Current considesations of tlie ludications 1
of aint mitigating actions f or inadeeps-ate tore cooling noy result in the potential use of the RC pumps under certain condi-tions. Criterla for use of the itC Inimes.
If e enpelred. will 1.e developed consisteit ultti the scheilule requirement of item 5
~
(sliort term) of 19 05C.
IClif :
1.
An RC Pump restart is allowed only If feedwater 15 avallaisle to at least one stearn generator.
2.
Staenind precautions to lie oliserved prior to puny restart.
A. ftW has been maintained or will lac reinstated prior to starting the flC pumps.
R. Seal injections flow lies licen maintained to all RC pumps.
C. Seal retuin is in.ilntained or is seinstated prior to starting tum.p s.
D. Pets y 250 psig.
3.
Inien geni.y operating limits for continucJ pump operation.
A. Sliaf t runout (vtl. ration) shall not enreed 30 mills.
II. Is ame vihs.stion as nicasured on the lower auster mounting flange shall not excee.1 5 mils.
O
- m. m
IV.
Ocoratine Guidelines for 5: all Dreak Part i and Par: I of the " Operating Guideiines for Smali Break:" have been revised :: include the F,0 pu=p trip re:uirement of :I Bulletin 79-05c and are a*tached. This information will serve as the basis for revisions to e=erger.:y pro:edures and addi:T:nal cperater training.
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part II:
Small Break : hen =ena. Des:riction of :lznt Bed.avice
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1.
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A less.of.ccolant a::ident is a ::ndi:icn in which licuid inven:Ory is 1 cst fr:: the reacter ecolant system.
Due to the icss of rass frc the rea:ter c:elant system, the ::st significant short-term sy o::: ef a less-Of-coolant a::ident is an une:ntrelied reduction in the reactor c clant system pressure.
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is the principal lenger-term indicati:n of a LC A and requires s;e ial censideration in the deveic; en of ope-ating pre:edures.
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. a Y a.. e. d..
w...*i.
C..
L.. s..J. e. J.
- 4. a...
i.
s 1 e.., 4 n. w. a.=:
e i
.... rn.
w.
.,] g, s 4,,........... p w a g 'i.s J...s3
..p*.J.)
a.
., 9 4.
- 4. 3... e. s s., I i a.../. wy
- 4.w
. y.. s..a,.
..... 3 4.
- k..,s.a g. :..e s.s 6 4....
e,
. e.
., L...
- 4..,
aa a....
.o.
y
- ws ;..
a.2...
e...Ja.
- L. a. o.4 e.a..,. o i.a a.. n..
3..... s. w. ',.., s 4,. i 3 s.
- 4...
a.
...a..s.o
.e
. ia; l
I l
J...w.
i
.s.
- 4...
- k. e. s..s... s..
- w.. e.,......
....s..
s s.
e.
l a...
'U'"
$ 'J O OE *e
- Ci p ". O f a l 0W 0" essure 53 AI siO.r.E*. i f.
r e..".1' - o. d J..e.. = =.=. s.
- ensure tha.
.e:cate ::re :::iin; is pr:vi:em Fellowing the RC pum: trip, the sta 1 break transient vd11 ev:ive as des:ribed in the subse:uent se:ti:ns.
3.
5:211 Ereaks with Auxiliarv Feedwater There are feur basi: classes of break respense f:r s:til breaks with auxiliary fee: water.
These are:
1.
LCCA large encu;h te depressuri:e the remet:r ::: Tant syste 2.
LOCA which stabili:es at appr:ximately secondary side pressure 3.
LOCA whi:n may repressuri:e in a saturated condition 4.
5:a11 LOCA which stabili:es at a primary syste: greater than se::ndary syste pressure j
The system transients for these breaks are de;i:ted in Figure 2.
3.1 LCti. Larce Encuch :: De ressuri:e.Resetor Ocelant Syste :
Curves i and 2 ef Figure 2 sh w the resp:nse Of RC3 p.ressure :: breaks that are large encu;h in :::binatien with the EC;5 te depressuri:e the systa t a stable 1:w pressure.
I; 2 inje:ti:n easily ex:eeds :$re beil-eff and ensures
- re ::: ling.
Curves 1 and 2 Of Figure 2 show the pressuri:er levei transient.
Rapidly f ailing pressure :auses the het ie;s :: saturate qui:kiy.
C:id leg temperature reaches saturati:n somewhat later as RC pumps ::ast d:wn er the R 3 depressuri:es belew the se::ndary side satura:icn pressure.
Sin:e these breal:s are capable Of cepressuri:in; the RC3 with:ut aid Of the stea: genera::rs, they are essentially unaffe:ted by the availability :f auxiliary feedwater. Upon re:eipt Of a 1:w pressure 3FA3 signal, the :: erat:r must trip all RC put;s and
- verify that all ESTAS a:t' ens have been ::::leted.
The Operat:r must als: balan:e Sp! fi:ws se:h
'.. - '. *. a 'i t' "n -
- i. 3.. '...a.
..- - ' + s a. / e. ', ', n ',v - - a.
.... < 3 w 4.
a va #. ' a.i a.
. i Mp: isavakiable..Tne :: erat:r should ais: balance Lp: fi:ws, sh:cid l
the sys ta: he a:tuated, :: er.sure flew :nr: ugh b:th lines.
The 0; erat:r
- n. ;........ e........
s.
4.
a'.s.
.......w.
.... s....................
i m
i i
- a. a.. e r.$...--s w~..' P. o nly
=ai.d d.=.
. a.a-L' '...=.'.....'.
".' a.
s. a. a...
n
.s.n j u. 4. c,..
w a.
- r.. -
a. *. ~ a... a l a. ". '.. =. 7.. ".. d a..a. r a.e. a- ". '.. = *.d.....
- t. '. is, hawa.va., r~a
- na..a.s a.y.
a Restarting of the RC pu :s is net cesiracle f:r this class of break.
shift the L?! pump t.cng-ter : colin; will require the operater ::
.n.
r,.
..,,. buildin. sL.
su.:,
0..
....n Curve 2 LC-* k'hi:5 Stabili:es at Aceroxicatelv Secendarv side Pressure _.
3.2 0 small in cf Figure 2 shows the pressure transient for a break which is t:
The steam
- bination with the cperating H?I to depressuri:e the RC5.
4
~o *...r.
' '-..a
- e..,. o. r... e.s a. a., '..".a..a.#.^.=,
n a.. a..e s.=.v *.., r e....a v a
~
I c-.
. ' '. #.1 '. - a.
-a$.
d a...=..v h a. >. '..
m" *.1 ~. ". '.'.. e s 3 ".. =.,,,. a.s s ".. a. wi '.1
'. n i. '. a '. '..v n..
the se:endary side pressure, RC5 pressure may eventually be;in falling as Curve 3 cf Figure 3 shows pressuri:er the de:ay heat level de:reases.
-'h a. he. la.
- a....c a.. = '.".. a.~ u i.ki;" a y". al. '. - a s *.*. '...a s * *."w. = *.*. '.
b.y e.'i k a.h..a vi.r.
w L
w a n. r a..*. r. a. l e p -i....=...v s.y s '. a... -. a. s s " r a.
d y
.....,. e. a '.'.*. a. c '. '.'.. =. s a... r.d...v s d. d a s 1.,.....e
...J......y r... :. s 1 1.n.1.v s n w....,).s..
... n a. s a...... e...,
7w.....i.
i
. w I '.
'.h. a. F.. '. r a #. i l l s
.$.1'
. a.,a. ".. s ". d.. a. s
'..'.a. R ".., *. *. a. Sc *. '> e as c a r. k a..-...a.
4.:C 1s....:.
.w. ar.....
L..,C.
r.
r.... a n
s,w.3 3.,1 o.s..
-'n. 1..... s. t.. v..
e... i...
r.er**
e...
4.. s.
an. *en.n ve,4.e.
a *
... c.2 1..., n. e. b.. r. e r a 5 s 4.,;. n., i i
.. r.
i
.w r..
1i.
.e.
... e.
r...a
..... v ensure flew thr ugh en:h The cperat:r must then balance 'r:?! in order t:
i hj.w p. c. $,
- 4. p. 4... j.o.. 14...
n..
jn
- b..V *5*.***."..'*.*.".
- s '. O..S i.' a.
- 5 a. e..a r *...y'
- . a. a. dW a *. *.
i r O'i 1 Cwy
.y cn d n'-*. CP. #. w* r as '..'.bl #. S *.a d n..' *.".. 5. i n
.......;. anc, a.
e- *, e.
- A..
).y.)
.r......
n...
p.i. e., 4. 3 f.3. w.)
,,g yg j aI,V d e"e. *s a-'J.1 - d. n* *". e s *. a..S..:.
s g.....$ 3.
4 3.,.
4..
i 3
..n.
- t. e. *w e. e..s.
e.se..s, 1......J.........
5L..
- n. 0, a no. L.
s.w.... s.
e ae
.. g y...
a 3
e y.
....es.La. s.n aa. C.
- 4. s a.,.a 1
- a., i e.. w.
- 4...J 3. s. C.,.,
e.,...
- t.... :. 3 C.
w*
a..
...n 5.
w..we.......
1
- 4... 1.,. 4... 9..,....,.. 4 4...,. s.
a..
3.........
w.
g...,...i.,
.,,., c. s.4. s.. C,,. r e s s,.,,. 2.
- 4.,.
.. $ g..
- 4.,. 4.,.. e.....;. e -
in.
.r..
.,,.,3..%.. i j
.................,q.e.... r...t,
.,....s.
g... w. 4. *i. n..,
u a
n..
4.... s
- 4...,., i.,v a s *..* ' I '. s.'. I * *. *. a. ".... -., i, a. ;,
~
. e. 4..,
1
.o.
3.3 LC*A 'Ahich '?av P.e--essuri e in a Saturated Conditi n.
Curve 4 of Figure 2 shows the behavier of a small break that is too small, in
- bination with the HF:, to depressuri:e the primary system.
Alth:ugn steam generat:r feedwater is avafiable, the 1 css of primary system cociant and the resultant R 3 veiding will eventually lead to interruption of natural ci rculation.
This is followed by gradual repressuri:ation cf the primary system.
It is p:ssible that the primary syste: eculd repressuri:e as high as the pressuri:er safety valve se:: in: before the pressure stabili:es.
This is sh:wn by the dashed line in Curve 4.
Once encugh invent:ry has been icst frc the primary system :: all:w dire:: steam cencensation in the regions Of the steam genera :rs c:nta::ing se::ndary side :::lant, the primary system is for:ed :: depre: Uri:e t: the saturatien pressure of the se::ndary side.
Since the c:oling ca: abilities of the secondary side are needed to con *inue t remove de:ay heat, RCS pressure will net fall beicw that en the se::ndtry side.
h?I flew is' sufficient to replace the inventory lest s
to beiling in :ne c:re, and ::ndensation in the steam generat:rs re::ves d ecaJ" heat ener:v.
The R S is in a stable thermai condi:icn and it will rezzin there until the eperat:r takes further actien.
The pressuri:er level res:ense is chara::eri:ed by Curve 3 ef Figure 3 durir.; the de:ressuri:ati n, and Curve a of Figure 3 during the tem:crary repressuri:::i:n phase. ETne i'
dashed line indi:ltes the level behavier if pressure is fer:ed up te the pressuri:er safety valve set:cint.
During this transient, het le; tamperature will rapidly apprea:h saturatien with thel initial system cepressuri: i:n. and it will rezzin saturated durin; the wh le transient.
' a.,.a......*.".-=.
w '. '. 'i
.$ -.....5 s a *.u. * *. i -. a s. ' -.". ' a. '... i s *i. -., '. ". *.
C a '..'
i may remain slign:1y sub::: led durin; :he repressuri:::icr. : nase :f the
........e.....4..4..........o.is...o.s......s......i..,
........a....$.4....
5.. s.'. J a... - =. '. i l l '..., -
... a. --4......>
...........3 s
I
-=
_m
~--,,
w
., -, 9
's.: '...'.,5 '..=. u s a '..=....-..=..,/ '..*. =... ". r. d. e n c '. s.a. a m....a.d a. n s.=..i c.a.
s,v a *.*.. h e4 *.i. a.
in the steam generat:r as the primary side level rises above the se::ndary A
side level.
If the de;ressuri:stien ca;abili y of the break and the HP:
is insuffi:ien-t: offset de:ay heat, the primary system will once mere repressuri:e. This de:reases H?! flew and increases 1:ss thr: ugh the break until enough ?. 5 ::clant is ics: to once mere ailew direct steam
- ndensati:n in the stea generat:r.
This cy:lic behavier will stop o r... a * ". a.W D. ?. and '.. a. a k..=... '. a l a n o.
- d. e...=..v h a. = *. c.,'.h. a. a.n a. r.= *..* r *..= k a s s o.r.a.
a y
action.
g.*J..ig.
jg
.3, 7..
- h e.
p.r. e g...m. g
- g......... e i. a
- 4 y
ip,e goe. g*...t g J
- e. s e. g a. n.
r.
c n....
y C '.
'....c. 'I C'.'.'
g. *. s a u '. *. *..* *. n.s i ;.. * 'i a"... V *. '. '. '. f' '. ". *. C *.... ' i *. *. '..' n v* *..' I 'e
".*. ? ^'."
y fun:tions.
The 0; erat:r sh:uld then balan:e HPI flow.
Foliewin;. hat,
.h e. 5 "..C"l.#
ra #. a* a. '.h a. a..'.~..
C. a. "..a. ". 2 *.*. r l *. V e.,'1+n. c. & o.
- .h. e.
e
. s... e.
c a m. s. p.a,
....y y....
h *. s.'..* u 'i. #.a
."
- s s u ". #....a g a s. ch. e.k
- e. a
- Da'.".. a l
".I *..u l a *.# C...
If i'. is y s'.*.iVa.,
a
. y v.
' 'p. e.
$ *. e s....
m e g e. w. s * =.=. g. ga.g t s.q. s. d e. m p o.e g. e w!.. e.
6 6. e.
m., J....../ s,Y s '....,
.$.a. d a *. * *....* *.
y.
'.' a.
s.v s*.a.... #. c '. i s.., o 1'. *.
~ '.
' c.,. *. a..... - o '. '. n 3
. a. '. i 'i l '. '. a n'.
e s '..* k.i d. <. h.
n 1
i
.s naturai :ir:ula:icnf he should ::en the ? CRY icnc en: ugh t: bring and
'.' a. ca....'.a.;"
s1.a. p. a. s e ".. a..
O n. e.
na."..> '. c'...-'t'i.$ *1 c, i.s Y
h-Id
'".a.
D.. '. '. a...
n
.. c
' t:..y.d, h a. wi l l M..
.a.k.,'1 a ' o w-n *. '. r,". a.
e s '..'.' ' 'i a h a.d. o. a o-a "...e
.*.o- '. a.
D.
a p
gn. e.g 3.siigw ), n........
s wsa
,.3.7,*........a e..
g. g
- .w.e...es.
fo.
e..e,g.,.
.i.
- We. p.
n o :
a.
e 3
r.
C,*,, 0 '. # '.'. ':'.
- t. ' ws '.". a
~4
.>. a
.t.
11.C a* 'r.**. i. '.
C. ".. b. #. I '.. ".. s '. E > E s a. "..
- ". *.i a.
o #.
n r. C, ". =.
.ne... pressure t: & Draak.:P wnlen high pressure in,,,e:ti:n behavier C,.
w.)
e p.e..e.o
- 4. er u...s..
...4. m. o. s. s
- .o e J o..s k
- . *l cw
- e. e.... *n, w
w m.
a.
1s be.ine g n. ai.i
- s..s e..s.
Te..a4. s c.w,.
1.e.
a.,. s a..... *6
. 4.
... t.
4.
.e
.s n.
w
. 1. 3 ;, 5 ;,,, *. e....
e.
- 1a.s.
6.. a.
- e. =*Je..e
$ *. a. s....
c, o. a,s.. s. a. =.
- e....a y e.e.a. -
- e. A e...s v h e.s. *..
"s"a s.a.-e..e g g J.. o. r m
s e
... s. o. y e..
... y.
.*.4.*.*
....d.'
......t.
- 4...,./ s V *a *..a.
".'a.'.a**.**.'a..
". h. * * - a '.".$..- '
as..
- 4... e y.
. r w...?.J.
J,. '. '.. '
sm.
- m. a.e... a s.
- b. s =.
T.
.7
- C s..
- J. a. n.. e. n s u. e.......e..s..
b s
i.....
- ge R '..,, o.....
.o n.
.... a
- k. o., o.,. ' e. s.,. 1 s.., pu..,
.. e.
{.
s s.......'.,.;
.n.. n e..,...=. sn...
'.s.. t.
sg s.
.... i.;
l a r...........
. e. t, t. *. *. s. s.,
.s.m.. s... s. 'i.
t.=...
- 4. a..'?.s.4.. aa w r. o..
...,...4..s..
a; l
F verifi ed.
A re. 4-: cf the ?.
pu=;s under these dditier.s is desirable for plant ::n:rol.
3.5 Smal! Breaks in Pressuri:er. The system pressure transient f:r a stali break in the pressuri:er will behave in a manner similar :: that ;reviously discussed.
The initial depressurizatien, h: wever, will be m:re rapid as the initial inventory less is entirely steam.
The pressuri:er level res;:nse for these a::idents will initially benave The initial rise in like a very small break with:ut auxiliary feedwater.
pressuri:er level sh:wn in Figure a will cc:ur due :: the pressure 1.su..,e.
...ia..
i...,..
...egn..<
s
.. a. E.
o..
.o.....
T,. >.,. 1 C n... u..... s a.... ;..
2..
.n
,o
- e.......w. ;..-. c...
..:,3,.e.y e...,.........i..
...2 2.., s
- r..., e. i e..
..u.....
. l.a s 'n..., w i l l ". '. '. d.
.=. a i.v -.. u. '.. '.".. a. F. *. 1a.,
d 1yi i n
'.h.a
-. a..e
" r #. - a...
w r
piping and :ause an insurge int: the pressuri:er.
This ultimately fills
- " a.
. es e u. '..' a... :..
'.h a.
- a....$ i n.' a... '. '.'.a. '..$. s t a..*., ^ e < ra. s e ".. '. '. a..
s will ra... 'i r. '. ".11.
i cw =. d.
'.".a. '..a*=..
s..$ e.s o '.
- .b. a.... =..- i e. *., '. '.. a -. =..e s ".. 4.. =. -
r
' may centain a two-phase =ixture and the indicated level will shew that the pressuri:er is eniy partially full.
~xcept fer closing the PCF'l 51::k valve, C...a... a..t...s a 2 s.....
.. pense,.
.u.,
sa,..,.
..s.., u.., l. s a s..
r..
..a similar breaks in the iceps.
4.
Sea 11 Breaks 'a'i:5eu: Auxiliar/ Feedwater
......e.,...e.-.i u. e..,,..s
.: u..., :s.
r,. a-,..u......,s<...lae..a.
.2g...
.a.
in without auxiliary feedwater.
These are:
1.
Th:se breaks ca;able of relieving all de:2y heat via the break.
J a
L.'.O. { j n e..J. e g. gn.
3.e..s ha 6 6..., 6 p } J. a. y a.
d.e...av he.,*. W.'..h b.g*.h
- .L.a.
J s...
c.
Via the braak.
- =
'd.. ?. a.d
-a. e. ' 1 '.
1'.
e... = k a-w
- d. ".. d. : r.. *. a '.......' '. '...= 1 'I,v a '.. a..a as
. n.. e. e. o.
- t.. s. <..
c T y~ s. s e...
r...a I
- 3., j.. $...... e......... r..e J. a.. 3
- e.... u. g.
L.... g.
g o. e.
s.
4.....
- 4... r. e.......
... a aw......
1 p.
O
.c 4.1 LO*A's Larce ir.cu:n :: De:ressurize Rea:: r.: clan: S vs tem.
For Class 1 (curve 1 of Figure 5), RC sys:e= pressure de:reases s=ce:hly througneut the transient.
For the larger breaks in this class, ~.~
actuation and LP! inje:,ien will probably c::ur.
For the smaller breaks of this class only, CFT actuatien will o::ur.
Auxiliary feedwater injection is not ne:essary for the shcr -tem stabili:sticn of these b re aks.
The pressuri:er level for this transient rapidly falls off scale.
Operat:r a:tien and plant response are similar t these described for this class of breaks with a feedwater supply.
.. 41as. v (.L,.y,.
p
- n. :.
e,..i.S
,u.zI;..,s e..,..
n.
a
. c.
i.e.a., s
,t.y. ;i
-3 2..,.,.
.. i Figure 5) breaks, the RC cressure will rapidly reach the 1:w pressure E5FAS trip signal (ab:ut two :: threeminutes). With the H.:!'s on, a slow l
system depressuri:ati:n will be established coincident with the de:rease in : re de:ay heat.
No CFT actuation is expe::ed.
Auxiliary feedwa:er is n:t ne:essary for the sh rt-ter: stabilization of these breaks.
The pressuri:eh level for this transient rapidly falls off s: ale.
The cperat:r r.eeds to trip the RC pum:s upon the 1:w pressure E5FAS signal, verify :: ple-icr. cf all E5FAS functions, and try :: establish se:endary side :::iinc.
Galan:ing of the R?I must also be performed.
' s '. n. a. = s i..,,
I e. 3.... 3.,...
. e. %..,g..
-o.r...* *. b e.
- a. k..= #... a. d.a. r.'. :.#..<
a. =. e s "w. a.
c the Operat:r sh uld ::en the FORY and provide all the Mp! and makeup capabili:y 1
possible.
The goal is :: depressuri:e and c:01 the ::re with the ECOS, the FORV, and the break.
If se::ndary side :: cling is again established, l
u,./a l,i a,s l,.,
. s
.e
- 5.........r s... s....
.y a.... !. e.....;-., e.n,
1,.
wy....
....i.,...............
6.h. j e A d. 96.,
O 4
.. '.M.'s9. g
- 4. g 3.p g.p n'g p.) e.a y.e l.N A.
f..#
a
- 6. m.
A 4.m. m.
g*g A64 84
. s.
4A
..a p.
.....a.
n.
m
. y A Q M, yO. Q. M..
O. O O.,
. n M,
-}@
.% Q.-
b..*. g. f.l.f..&*
W O...t
.O.
g.vns....
e e.s *..,.W. 9 J..g *m..s. d..
n
l
.y.
4.3 Smail '.0 A's 'dhich de no: A :va e the ESFAS.
Aut:ma-i: ESFA3 actuation will nct e :ur f:r Class 3 (Curve 3 of.:igure 5) breaks.
On:e the SG secondary side invent:ry is beiled off, system re:ressuri:ation will o::ur as the break is not capable of re ving all the decay heat being generated in the Ore.
System repressuri:ation to the PORY cr the pres.
suri:er safety valves will e::ur for smaller breaks in this class.
For the ":ero" break case, repressuri:atien :: the FORY will c::ur in
(
the first five minutes. Operat:r action is recuired within the first 20 minutas t: ensure ::re ::verage -hrougheut the transier.t.
Fer the 177-FA
'.'.4.<
.a '.'. c.....
- k. a. a. '. *. 5 a.....a..va'. a..u.a.'... c'.
5a.
l ew a. -a.d.- l e., s
~'t.a.
y auxiliary feedwater syste er the HFI system.
The establishment of auxiiiary feedwater will ratidly depressuri:e the RCS to the E5FAS a::uation pressure, and system pressure will stabili:e at either the se::ndary side 53 pressure or at a pressure where theNPIetuaistheleakrate, bponreceiptoftheicwpressureISFAS signal, the Operat:r must trip the RC pumps.
For the raised 10:p Davis-Besse plant (whi:h has a safety-grade auxiliary feedwater system) cperat:r action is ne:essary at sema time greater than 20 minutes (appr:ximately 40 minutes) as there is in:reased inven ry in the 1::ps that is available :: drain into the rea ::r vessei.
H: wever, be:ause the plant is equipped with 1:w shut-eff head HFI pumps, the operator cus: establish auxiliary feedwater in Order :: depressLti:e
._Se n....:.
For the Class 2 breaks, pressuri:er level respons.e will be as shewn in
' a r..'. *. r - a. e s u. '. - a.. i s "- 4.=. #.- -..' a.
lu-a.
... '. n '..."..... a. '. d. '1 '1' d... a.
a r 3...1..... e..
iv
. i n
.. n g. 3( o,n;. 4i 3 c.
..q3.
- j. -4......
N...
J. j u. J.
- i.,y s. 39...
- 4.. u.
....y
- e.
e..
sci
.. i..y a.ess
.J..m..
4**
J...........e.
.. e.e g... J.. n.,. g o.
$.y e....a
. e...o. g. n..d.
e. 4..
g...
i.
. s,.
- s.
...a g..
2.
r..
- e. n. *. *I.. s. e.. n. J.
- 3.. } s. y s. t.
Q.. e.
.g e.
..s......
j,. Y 3 9.
- 4.... e..s t e.,
...$.b.ju 4
aw
..a g..
- x.. s. n.. s k e..r.....
..,...s.
3,. 1...,.,.. $.......
- 4. *i. 3.v e. s. o... q s...
2,
...4..,
a....~
-- =
.,.,w-7
--,,y
-so-the cressuri:er.
cepressuri:sti:r. will result and cause an cutsurge fr:
Fer the smaller breaks C:=plete less of pressuri:er level may result.
in Class 3 whi:h result in a system repressuri:ation following the actuation of the h?' system, pressuri:er level will increase and then stabili:e.
Without auxiliary feedwater, b th the hot and cold leg temperatures will satura:e early in the transient and, for the Class 1 and 2 breaks, will remain saturated.
For the ~1 ass 3 breaks, once auxiliary feedwater
/
......s w1;1...idl.y s... ~.., 3...,
- i. es.,w11she.,.w. cols., i.,
s
.r i
l
.G q
i
,.,..,. e. s.. S s j e,.
- 0
- L. e.
a.p.,,4.
...]y
- on. s3....
4.,.sn. _.e.r....
w..
r..
ny
)
y.*......
,.. m n 3 r _.., i n ' =. ~..
- .5.. " ",., - " '. '.". a.. =. ~.... '... ' a. r c '.
'.5 a.
a-
.s s e... s.,.y...
r...,..
.e, a *.....a d. h.. ". : '. a. u '. '..". a.
- a. v =. a. *..
- ,. a n.., i a. n '..
V.',,*.
i a., * =..c. a...a.'.' - a s w'.1 "i r e....= d..,
6.
The operat:r needs te manually initiate all ESFAS actions, balarce HFI flew, and attempt to rest:re se:Onda-y' side ::oling.
In the meantime, he should actuate the makeup pump and cpen the PCRV in order t: ecol the : re and limit the F.05'repressuri:stien.
Once feedwater is available, he can
- 1cce the PCRV and centinue the F.CS ecold:wn and depressuri:stien with the If natural cir:ulation has not been established, he stez: generat:rs.
.n a.
", c =.1 i t.
- d. a *. a. s - ". *. '.. =.
e.. u l c-.' o r..
d P. '. g.....
.a
'.$.u s a.
- . :. ~.. d b
=
, a n.t....
te wnere the EC'S can refill the RCS and guarantee long-ter: ecoling.
4.4 Small Sreaks in Pressuri:er.
See the writeup for s.all breaks in n.,.. s...
- 4.......... \\.n *. =n.,.,. s..
z Scali breaks in the pressuri:er will differ fhm these in the 1:':;s in the same manner as these previcusly described in the section addressing s
s.a "i i ' ~...$ k.+
- d. r. *.".. a.
.a s s " *. d. - a. - w'. "... a "."'. l i s..v#. *..
r.
a
.C.~..a *.1 *,
- a_ m. 'r W.*..*.
I. *. #. *.# a l D.. a s *
- a. t a.
T. d. *.*. #. *i ".
S i
i
- .**..s'.a...*.*
i
..s.. a b = e..s 'T.a*.
". h.. a. c. s g *I..=.=..a
.e 4..=.. J. 'i.s =.
- a.
I. q. 6 4.s *1 J
.C o. Y h. a.s ] *
- s p,3 j o. e. *.a*
.a j y a.
3..
3 s.
s 4 n a '. i *.**. a. d.'. Y
.S M. M E. *. #. C.S g. 3 '6. *. '...J 2 8'..A 4..*. *. 4..* * *. E.*. *a A
Iw
..a.$.2".*.t.
W *. e i
- h. a. d E. g *. d 4
iy s..b. t s. a. n. a a *~..../*.*.ai.a.=.m e. s a..a.s a..
m.
w.
e
- s a. ' '4. a..a
- h. F a..s '/.*,
J. a. a =.e..s a s. a.. o. m. e. W.s
- e.
S.
I 9'
Qy m. e. *.*.*. } i a.. y *
- s a. *a
- o. a.. *. a*
a....
4 a
a
flew, and stea. generat:r everfill can cause RC5 Oressure de:reases witn l ew a r a..' '.'.* r *.. a. $....-..d.e
>nd :..:n".:. a -.>.l a.u. n.
2.=..>... ".. n = ', a..s 'r.s a:tuate 1:w steam pressure ala-s for the affected steam generat:r, and steam generat:r overfills result in high steara genera :r level ir.di:stiens.
The overe:oling transients will repressuri:e the primary system because of HPI a::uatien, and will return :: a sub:cclet
- ndition during re:res-suri:ation.
The immediate a:tions for both ever:: ling and snail break transients are the same, in:1uding tripping of the RC pumps.
The cperat:r will re::gni:e ever:: iin; events during re:ressurization, i s.
..e... ". =. '..: + 5.. ".. '. a.
'.4 0. *. a n d..a.e.'..=..
'w"..aF.*.
a'.."..'e..
r d.
i f n.s*.
s *... =.., a.. d r =. =. s..= b ".. ".. a. d., '.v. ". a. s. ~* 1 '. '. a..$ '.. - =...*. '. 9 3 i ', s u'..^ i a. d... n ^...d....-
a
$ ns...... e. o.e..
A less-Of-feedwater trar.sient will* result in a high rea:: r system pressure alam but does net give an ESTAS a::caticn ala:-..
a 1 e.e,,a c.
4.
..,. *'..a'. c.r.*..,I sys *... r v.=.... >. n s i a. r.*.
s '..'
'..e w'.'5 a
'.'.3-F e
. a.p,..
a...,s an ov,....e 1..
.n1s o......
~... s2
,.. :.,.. A c..
cv r..
trar.sient and will give 1:w rea:t:r system pressure and pessible ESTAS a c '. " =.. # -..
S '. = >... - a. v..*.... l a. v e l s r a....' i r. F. '. - h.=..'.
'.5 a e " s '. a.... ' a.....a s
.s y
3 1
e, u b.. I e..a.. 1.
- a..a.e,.,.,,.:.. t...
A r..
a.,....
su.
e
- 4...
.).
- b.. e.
g 3 j,3..
- e. s.... 3. : *w. : c*i n" i.e.c g..y
,s 3.......,.*...
c......io..
a.
- Y i d 'i.. ; a d a.. "..,. *.a.
- ...e e.".. I,V
- a *. *. *.
- e....$. '. l b r o. 5 k '. ". a..' '. a..a. * *,'.b. a. =. ' /'
r.
a e
c,. 5,'11 k..a.aks.. ue. 1' J. a.. t :. :. a. p aa a n. r. r 1,...,., s.1 e,. s..,Kan.:
. e. e..
r-
.s s
^ p a..' '. *. a.* *. #..*.. *. *& #.. a d i. s '..". '.*. # '
- ha a,v a '.a.
"s~.a.eeni,v p r....-'.
ma.'.u.2. 's o
a ir a -
y o n.... ui..es......
3Cw
.s.....
- n.g s4.y..,,i l a.
.,a,3 s..
a...
a.
nr
... e t. e.
. e
.w,6
... i. e... i.. e. s.. a '. a a i.'*s* A c.
.e..
ic..n*
- w,*
. 4.. w. j
- 4. 4.3..
e.
en..
.. g.
J.
- 4. 3.. s.....
- 4. n...
.....a
...a 4*
.*....e.
- 4. '.
- 4...
g.9
.J 3..a
- b. e. e... e. 3 g.
=..=3
.h 4.. W o.... o. g a.. o.
an.
- h.. e.
- 0. ".
a..a. gg. e.. e. J.
4.
J. o a.d. n-s
- t,
.o. = b. s..=. e.* w l..,,
g.o.. j i.., g
- 3. J..... a. 4. e....,.n..
I j. $.g
.A.
. O. $. O..
4 w,
l t
i 1
.);.
. h. e.....s..
a u
t s:
2*
..a.
How.v., i :... ~r :v,o.. s ocu ~i
=i. :. a n.. a. i.. r.a..,
.n.
.u... s.. Ens i.n
- r.k......... a n.1' n. t.. a.. a c.
..r s
4 t.n 1'..;0 s v 1.n'.sa....r.n a..
- n.....s. F,, s.
u.
hese in. ce:
tu i
transients 1:er.t lec acove.
o...a a:tuat1cn
- .s. n o Quench tank pressure / temperature alan s o Satura ed primary system o Rising pressuri:er level These additional signals will identify to the operator that in additien
.o. h. a.
- 4.,. i.... s.... n.,,,.n., a i.n,.n+ h o.
..a.r.A..
In.h. u.il1k.1y s
r..
event that s.all breaks other than a malfun:tiening DORY cc:ur after a
.. a..- i =... *., *.". a..v..*.. b e '. d. a. r.. '. #, i a. d. "..v i. n '. *. i a *i 1.v d a. -. a..s s '... - :... - -a.s..". *.
r.
a an. d.
.. a..v a.. ; *.... a.. s a '.". ' '. '....-... ' '.... s i n ' h a.
. =.. =....
C....= *i 1 i
break repressuri:ation, if it c::urs, will follew saturation c:nditiens.
.., o l a..*.. a.....=.'. ns s "".o. l a. u' c-w '.. a. "... a..
'.5 a.
r e.=... s.
B,v. a....> '. n i.c.
av..=. a. * #.
w r a ". *. :.. #.. *.
g... *.. E.".s # a.." '.s, ".". e C *r *.. a '. 0 *. i s
.8 ". l a e...
w..
..es
-3*.o.,
.. A.
i a
k.n.n a
.e....s.I s w
.,k h,,s C..../.
- u..p I i n.... *.... : i n s.
/
- 4 i..e r. A,1.. a x.... m
- o *on e.
s j. *... 1 s n..s. e. d.
. e.,
2 ma s : 9 l 1.S.,*.m* i s,
.k.. h* D. 'A u
C. n,.
a..
e.
l a n.,...s. r e...., i.. m e. r. s i. L,, l. s.
e.,
- 4. e. 4.,
1'..
J.
- c.. s a *.l a. :i s..
s....
.i or R a r,
...a r..
5.,. s...w.s..
1.. 4.a a.. d s. 1w..s. b.1ew.
in. v e..
For certain scali breaks, system depressuri:atien will resuit in 5.DI
'.s.es'.;.ad.
'..,...".'."a. '.n,',a..'.'....
a '. a ;. =. = *. =..
d i..p e..., a '. '..-..
S i r.. a.
'.". a.
t W:
%... a. ". a..,
.. 1 i s e-1 1 e~s a.'.
"D. '., * *.... i..=. *. i.a.. eT *5a
...a
,. a a '. '..,> '.'..a n *.".. a n
. g c.).v.......
je..a.e.),w r...s..., -:n.a n 1in.
4.,, a. 1.,,.
w e
a.: n s....*s w
.x..
h a.
0... '. r. ". *. *.
- y.., v...- a.d
..'1=.a-'.'...>*.d..-.
- 5..= s k a. a..a.
s *..*. '. I a. #. -.
?. O... ' ". *. a. s.
6 3
. '. a.. L.. 2.ys..... Wi))'...
p..
. 2g.i e.
. a.. c.. a.y 4.. 1 n,..s.. s...
e.m.s...e...
a a r..d. ". ' *. s '.' '. *. *. *. a e. s s " #. ". ". *. ' O. '. #.'."'..'..
T. *...b. a.
- 8. v a. n *. * #.
a C *. - *. #. *s.* ^. d d. r. -
...... a. f.. p.
- a. - =.e. #. *i * *. d '. o ;* l '. q. y'i i.
- e.*.
a i.1 0.
L. *. c. s. k,
- .h.. ' 7 '.
- . *l *.* '. d. P.*.s. J...;a k.
i..
- W.
..a.......
- e.... e. s.4. 3.... e.
... 1.y
.w...,. o..,.. ;.
- 4. 3........
..s,
'I * *
- 4 *.
- .= a. y '..d 4. *..
- I'.*,
- ..,..I *.. *. * *. *. '.
8
- k. n. 4...
4.
4 A. *. *.. M.*.
- .,.b
" '. * # d.* *..i. i ** - S..S i.
A I
- 3.... f. o. a *i........ # "...d J.
.... 4 m...
.a=
e.,,.. *..%..
'.%.. w.
a 1
P ' - '
ew a
e-
- l a. -
- .qn...: 9.....e, g g e... a.g.gy a.a. s. g...e o n. a n...t.. a. t.
5 m
- b a.
y.p t.
n. n..., g,
u
.y g.
d o. *l. y o. - a s.. a.
.We D.. "..
4 4.3 a.ina a. e. a.J.s,. a. :)
.g k
s y
iew is atso a.lewe:... a..
inre:tlin; er terminatien c. the Hn..
r..
i it ti the fo11cwing :riteria are met:
A A.
Het and cold le; tem:eratures are at least 5C".: belew the saturation temperatures for the existing RCS pressure, 0
...e.
s m.. a q s. a o
- w
- s....e..... r. s 2,... n.
..c r o.
.aan.3.;
o*.*e.-
. h. 2..
- w c,.
u.C. j a.r n
a....
.,7 a i d e a g *.....s
- 4. -.g
- m... o. r....J.. ('ihj$
e.q$...o.$
6.5.3 h e.s. *. j $ bo.i r.e a
=
- v. o....n v a.? vs
- k. a.
.e.
a.i a. n '. s m.a.
- a. e - a..,v
.... a v a...
'..".a. i. ^...* *. a. '. -. a. e s ".. #..- a.. i= val C.
4h.. a.
.a.
g
- e.. a., c :. :.. s, *i,
.,1..
.. 3..
s..,.. a. s s ol i c.
C,n.1 n,J a.s.
- u...p I L6 n s,.
- u.,. s,... a a.. i...,
- n,.,,r1 a.
flow at full ca;a:ity may result in a sciid pressuri:er and w:uid result in a lifting o# the POP.V and/:r the pressuri:er : de safety valves.
This s...Jid be *h...*l s.
0 a
F,y.n *.,.. lea... a t_e.n.
6.. u s, u..c. A :l $W e
s a
w a
w w
e
..,j 34.n g $. s b *1 *. i r ". =.. *....v i n +.. a.
P. wa.va. i.*
'..h.a "Og:
s"'...'.#
i-i3
..w "n ?.. s h.2.1 '. b o.
i.~....a #. #. 8 * = 1.v r =. 8.. '. #. V.' '..* d..
C S. n..0 *. ' e "..i.' #. r. *..S 4. D a ',
- h a.
"n? ;.
- e. I.w s
- e..x.... 6 wa 3 Ia. h e.
- k... *
- i. e. s. *.. m r. \\........ \\.1. *I a
- 4. O n 0:,.h ni *i
. y w
d u - '. #. '. i '.,v, '.a..*a...**."..a.
( a"~.i~s ')#. 0 F
- .a" a."a.'.-'.**
V E.e s.= 1.
-' 4
.. n e s,...-, n
.m.m. I a ;e,a.:.
.%a. **1,1s
- e.e,.,...,.a.
t an
.u A
a e *w h.J e.w. s.
- w,....... v.s.e. a. o. i is a. le.3s*..C.: s u L..
0 *6 a.s..
n C...v.
C.
...e i
allowabie d:wn:::er tem:erature for a given RCS pressure is previded
- '. = d..w..-....=.-.=...-a-'.".".*.
' 4'
' =. a.. '.. i e '.
e...
... a '. i n - y ". 'i.- a 'i..a. a s.
d w..
4.
l..
=..
.y..
3
.a g. 6... p.
,m y
ng w.
. 6 3,.
- e..
.., a a..n..
. a s.
q z.....,.:y,..
3.
- l
- c..s.a... y o.g a n. 5 4 ~,q..= ~ ~...s.
- h. 4. *6 We a.g.a...s.... g.,y
- . s.
e.s..e
.s e *. a.
b a
3...
3.
e.... e..
- 0..* r.' -.. a,.-.. a.t. i.. ;. * - s. a....*
1 e.*g
- 7.. *. ' 4' a..s v...= *.. - a. ". # - =.
.4......
m.
.o
..a i.
n..........
tempercture readings indi:stive Of the actual P.Y d:wn:::er temperature, as a stagnan p :1 of water may exist at these lo:ati:ns.
Tne in: re then. ::uples will pr: vide the best a n. s..e..,l s. L.
.s. 1ll'
.s s
w inw....
c<..w.
d,w,,...
.r
....p.....J s4 w.
if n ?.C pumps are available.
In order :: a:::unt for heat 0
added te the fluid frem the : re,150 F must be subtracted frem the in: re therme::Uple readings :: reflect the d:wn:::er temperature.
This method will result in temperatures whi:h will be icwer than the
~'n " s, t' ' 8 * #.
'. ".1' ",."..$
- b. ^.d. " 1 ^ "u' "
.$.'.~ '."."..a. s e y*
- a. ". '. a. d. #. ^e'"'s'"...*.".
'.8....**.'."a'.'J'.'*..
i 6.g. Pa-.w. yj]i 6a. g e =. a. L *i.
)
r.....
e e
l I
1 1
4 y
... l r.'
... - l L e t e v. 4 i k a.
Ib Thevi
..., E. J f; L i tt re a t
- fia G
- J Dan:n.
. n.' : *
- '.. J L.,. :- : a l '1 '1 a en Z ':..: l
....n-l l l d. r. e..
e.w. >v>.>.. : L n
a.i l
w i
i 100
?e-a..->.->--n
- _na, l,/
,/*
+/'
p',-
30 p
u
~ / +s.
k t
- &*/
\\q//
r=
c'e,g./
g/
S /
. n.
o f
g/
5_
o I
i
/
)
/
/
64 e
/
/
\\
/
~
s0
/
/
4 g.0.
/
-u e.
/ /
/.
i
~ +/
=
90
-/
./
/
g 0
400 800 1200 1G00 2000 2'00 2500 Time, se:
Figu e 1 4
6 e
l i
i I
~~
" " n' v. "
"I,' l '1 'M' a' 'J' X l l '. n'.' T
~r ~; ~; ~'.;"c'.'. ~I : r.
P *. ~; ~ ~G "w '. ';
"i?"
- ... )
ii.
J f &
i
~~00
,~
a
/
/
/
\\
/
\\
.\\
. e n. n.
,/
1 J
/
1
'. '\\
/
w l
i 1500 I\\ N
\\
i 5
.i e
2
\\f 1000
/
500
<D 0
0 500 1000 1500 2000 2500 3000 0500 4000 Tine, : :
Figure 2 G
e a
r e
=
i 1
- 9. t *.
g ; ;.i y. e...
.a n i i :..a.s.ty 9.l. [ e a v.
.:r:. i s i l.ee...
o..e n g L
.s.?.;. a..t* *
=
ee p.
....ou :..
l.....n.l..e r.
e.: s.
100 j. __
I l
50 L 1
/
/
I
_o>
/
\\
a a
/
i eu
/
I u
~
C
/
5
/
1 0
4 0 -
/
l d
l a
20 l.
ds I
I w
h,
.i n
0 500 1000 1500 2000 2500 2000 3500 T i..2, se:
Figure 3 0
e
i
..,,... -....,,,. ;..... i, e n.. e e.. n.. i. n.
c:...;...
c...,
..: i-s....
e 1
l l
(
l-l t
100 -
W 1
a e.
I 3v I.
_=.
=
.=_-
a o
N 0
m.
.a c_
l e:
Aw I
O f
I 0
200 400 600 E00 1000
- l.".. O, S.B C 6
Figure 4 e
.... n 1.:.
- 2. i. i. :::
e.e.
2 : : e. 3. n.. :. i, e. i
- e. v. e : : i.,.
a..
h/0 AUIllIAP.Y FIE0":ATEP.
2rna- - :-
i,4 : r. v,
i
--ei i
f LE Af-3 SMALL
(?,
1
, C e. n.
fi 7
i
/~_
t.,,/
/
-~
1500 "\\\\
- , /
/
u A
{_
S 1000 N LARGE (5) 500 c
O 0
500 1000 1500 2000 2500 2000 2500 4000 T I,?.s. s e e o
Figure 5 e
e 4
6 I
e
s..
a
..... - s. r5 J J J
...; L J.'.". I i ; *..; r '. '.
8J.
Ii
- sa c..:,,a n e 0 3 L,a I,. l a m.y e ::.. : r.
y
,.g.,..
c.
t 100 w l
n, e..n n }
l
/
6.
J
,.... n k-I 0I 3
\\
=
c
\\
3*
f' a
a l
-u~
so I
ONLY F0F, 3'.'ALL CLASS 3 5
I
- c. :. :.. r.s
_o c
h.
l 40 I
r I
l 20 I
1 I
0 O
500 1000 1500 2000 2500 3000 3500 4000 Time, se:
Fi ure E e
\\
D
1 i
i V.
Guidelines fer Nen-LC'A Svents Because of the bread spectrum of system ::ndi: ions ::vered by the small break guidelines, the : era :r actiens and pre:autions' identified to bring
- cling cede apply, in general, to any abnormal the plant to a long ter :
event which results in a decrease in RCS pressure.
The small break guidelines will thus be u:ilized t: update the emergen:y procedures for non-LOCA events; at a minimum, the f:liowing pertinent sections of the small break r
guidelines wili be in:orporated:
1.
RC Pump Tri; Criteria and SG Level Centrol a:tiens to pr: mete natural 1
circulation.
4 2.
RC pump Restart Criteria 3.
H?I Cen:r:1 Criteria 4.
The need t: :: niter system sub:: ling limits.
The items will be sup;iemented by the additional instru:tions/ precautions
.o
.w. e.t....
e
- 1. Fcr non-LCCA events, a restart of the RC pumps (1 per loop) and termina:icn
.of SG fill is prudent : minimi:e system ever::: ling due to addition of co id n. -, to the G.Sa, s.
rn i
Note: The establishment of a sub:: led ::nditien (>50F) is a clean indica:icn ths; a non-LC;A event er a LC;A f:r wht:h a R ? ri; is not required is n t in progress.
- 2. HP1 should be thr:: tied, when 50F sube ling is established, to avoid a pressuri:er overfili.
- ient.... water may s.e acce
- , prier-
.. During severe over::: ling even s, su...
n.- ;
a:hievine a sub::: led ::nditi:n (_> 50?) and a i essuri:er. level (en-r s: tie), such that the system may evolve t: wa er se',id state wr.en
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1 steam pressure :entr:1 using the turbine bypass valves and/cr at :spheri:
dum:s) may be recuired :: maintain pressuri:er level on scale.
NOTE: The C;erating Guidelines For Small Breaks have been ::dified
- include :. tem 3 ab ve.
With operator training in the : st-LOCA re::very methods in conjuncti:n with : difi:stien of existing emergency procedures based en the small break guidelines, piant re::very and centr:1 can be a:hieved for any abnereal event fer. whi:h an F.C? trip is re:;uired.
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Rea::er Cecian pump orque can be dire::1y related to pumo oewer which is in turn dire::1y presortional t0 vol age, :urrent and the power fa: or.
The cumo speed, pcwer factor, anc voltage are assumed to remain :enstant, the pump ::rque can be related dire :1y to current as follows:
T (Torque) = KI Where X is a precortionality factor (1) and I is a current.
The pump tercue is also directly proportional to the' density of the pumo fluid, e, at a given speed and flowrate; That is,T=
'R for 100% pump speed.
(2)
-- o C
'R Where s = dimension'ress :enstant R = rated For small breaks in the RC5, the flowrate through the RC pum:s (at normal s:eed) increases very little early in -he transien.
Even i the flew changed oy 10%, no sienifican chance in :Orcuo would o::Ur if the cens;;y of the fluid remains constan.
- Hewever, if voiding c::urs in the ROS, the pump mc:cr :urren; w:uid drop as the density decreases (Ecua-ions 1 and 2).
Table 1.0 shows how the ac:cr current would change at snecift:
void fra:tions and pressures.
This table assumes that s in Ecua ti on 2 i s 1.0.
Preliminary data from the CE/EPRI tests (Reference 1) cf a 1/5 scale ByFon-Jackson pu=; show that I changes as v:id fra:: ion increases u: t: a void fra::fon cf N 50%.
Ficure 1 (Figure 1 cf Reference 1) shews the change in 5 as a function of void fraction.
The lines cf :p = 0.2 an: 5/=2 have been ad:ed ::
show tha i is N C.9 at a veid fraction of 20%.
Therefore, if this degrada-fon in Tercue (current) is considered, the : current shown in Tabie i.0 at 20t void fraction should be reduced by multiplying by 0.9.
That is, at a pressure of 1000 psia and 20t v:id fra:: ion, One curren would be expected to be 0.9 x 53.3% or 75%.
Additi:nal dsta was re:uested frc= EPRI and on S/17/79, this addi icnal ca:a from 0-E tas:s were eb:ained (Le: er:
Charles W.
Sullivan (EPRI) to Charles E. Parks (5&W), 8/1a/79).
One curve is essen: tally the same as that shown on Figure 1.
The other curve received comes from a letter from King House (ITI) to Chuck Sullivan (E?RI), S/13/79.
A copy of this curve, as re:eived from EPRI, is shewn en Figure 3.
Fr:m Figure 3, assuming tha: -he cr:ue at a
- ero veid fra :icn is 250 f:-lb, shows a dr:o in : rque between 20 and 40% at a veid fra:-ion of 20% wnich is consisten wi:n Figure i.
I i
O
2 Only :he rated soeed data, indi:ated a: X's en Figure 3 should be c:nsicere: fer this a;:li:ation since the 1/2 s:eed data shown on this Figure are at #iewra es which would cause a flu::uation around I
I the :ero torque line even at void fra:: ions of :ere.
Tests cer#crmed f or ELW by the Singham Wiliamette Co. i n 1973-1974 on a 1/3 s: ale pumo snow the same trend.
These tes s were performed using air / water mix:gres rather than steam / water, and data ob ained from these ests are reported in Reference 2.
In this test, a limited a=0unt of data was ebtained at full speed u: te void fractions of 20%; bu: no cata was obtained near rated flow cue to tes loop limitations.
However, :ensiderable data was taken at 1/2 the rated test pump speed with flows near ra ed condi icns at that soeed.
While the density of the air / water mixture at a void fraction of 20% differs censicerably in torcue is experien:sd as the void fra::icn increases.
Figure 2 displays the rati: of creue at a given void fra::icn Oc ne t:rcue with a :er: void fra::icn as a fun: tion of :ne inle v:id.# a:-icn :: :ne pump.
As can be seen f-:m ths fi;ure, :ne ::rque is shown :: ce:rease by 20 a
an inie: vei: fra::ien
- o n. e.
4 These three sets of data from two different :um: tests su::ce:
the cesition that a: leas; a 20 drop i n curren or erque will resui:
when the :um: suc-ion void fraction reaches 20%.
It is anti:feated that a core heatup in excess of the present licensing basis wcuid no: c :ur if the RC pumps are tripped -a: void fractions as high as 400.
This void fraction estimate to limit LOCA consecuences is based on engineering judgemen and mus: be confirmed by computer analysis.
Tnerefore, a tri: cf the RC ;um:s en icw RC5 pressure ::inciden; wi'th a 20 cre: in current should Orevice a pum: trip when re uired f0r small breaks.
In addi-ion, no cther events su:h as overce 1in: have been identified where ne veid #raction would even a;:roa:n 205.
iris means tha: -he R: cum:s would be available for -hese even s wnich pr: vices for be-ter centrol of the plan:.
It is therafere re:cmmended that the RC pumps be tri:?ed au :-
matically :n a
- in icence signal of the low cressure ESFAS signal en a me:or current signai ef 50% of the 100% power, a-pump cperation met:r current reading.
1 1
1 i
e I
e O
4 e
e e se
P. e. r r r. r..Le r. :.
1.
Kreos, D. A. and Kennedy, W.
G., "C-E/EPRI Two-Phase Primary Pump Performan:e Program", Cembustion Encineerin,
In:. Report, American Nu: lear Se:iety, Thermal Rea::Or Safety Meeting, Sun Valley, :daho, July 31-Augus: 5, 1977.
i 2.
R. W. Winks, "1/3 S 31e Air-Water Pump Procram, Pump f
l Performance Data, EPRI NP-150", 00:ober 1977.
1
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Babcoc!:&Wi'co.x roJer cenmisn cran P.o. Box 1200. Lynchburg. va. 24505 Telephone: (804) 384 51]1 File:
595-7102-5 September 25, 1979 To:
BaW 177 Owners Group Technical Subcommittee on TMI-2 Incident Related Tasks
Subject:
Impact Assessment of a RC Pump Trip on Non-LOCA Events
Reference:
To B&W Owners Group Technical Subcommittee'on TMI-2 Incident Related Tasks,
Subject:
Responses to IE Bulletin 79-05C Action Items, Atigust 21,'1979, 595-7102-5 Gentlemen:
In the Owners Group meeting on Wednesday, September 13, 1979, the Dabcock and Wilcox Company presented a revised response to Item 2 of IE Bulletin 79-05C.
This revised response was
. required based on discussions with the NRC on September 7th ahd lith in which the NRC requested a study of the effect of steam bubble formation on natural circulation for non-LOCA cooling events.
The purpose of this letter is to officially transmit this revised IE Bulletin 79-05C response to you.
The attached document replaces Part III, " Impact Assessment of a RC Pump Trip on Non-LOCA Events", in the reference letter.
Sincerely, THF BABC0CK AND WILC0X COMPAt!Y R. B. Davis Product Manager RBD/ryc i
Inc Cabcnek t, witcox company / Est.,tdit.hed 1067
/
s
/.
I!OM-1.OCA PVENTS 3)fPACT ASSESSMC!!T OT A RC PUMP TRIP 07 III.
A.
Jntroduction Some Chapter 15 cvents are characterized by a ' primary system The Section 15.1 response similar to the one following a LOCA.
cvents that result in an increase in best removal by the secondary system cauce a primary system cooldown and depressurization, muc Therefore, an assccsment of the conse-like a small breah LOCA.
quences of an $;tposed RC pump, trip, upon initiation of the RC prescurc ESTAS, was cado for these events.
lov Gencyc1 Arsensnent of Pur.p Trio in Non-T.0CA Events B.
that Several concerns have been raiced with regard to the effcet exhibit LOCA an carly p' ump trip uould have en non-LOCA cvents that Plant recovery would be more difficult, dependence.
characteristics.
on natural circulation mode while achieving cold shutdown vo*uld bc highl$ghted, manual fill of the stcan generators would be required,
)
11oucver, all of theco drawbaclis can be acco:::modated since cnd so on.
- Also, none of them vill on its own 1 cad to unacceptabic consequences.
restart of the pumps is recommended for plant control and cooldern Out of this scarch,
/oncecontrolled'operatoractionisassumed.
thfee major concerne have surfaced which have appeared to be sub-
\\
stantial enough as to require analysis:
A pump trip could reduce the time to system fill /repressurication i
1.
If or safety valve opening followin; an overcooling transient.
L-the time availabic to the operator for controlling HPI flow and the margin of rubecoling were substantially reduced by the pump
"~
O trip to where timely and effective operator action couhl be quectionabic, the pump trip would become less desirable.
line break (maximum overcooling), the (2. In the event of a larne nteca.:
- 1) blowdown may induen a stcan bubbic in th,c RCS which could impair natural circulation, with severe conncquences on the core, es-pecially if any degree of return'to power is expertenecd.
A more general concern exists with a large steam line brenh at EOL 3.
cond$tions and whether or not a return to power is experienced folloi,*ing the.RC pump trip.
If 'n'rcturn to critical is experfenced, to remove heat and natura3 circulation flow may not be sufficient to avoid core damage.
..spem w geg gumeuED 000 " 8859 9.
Ovstheating events ucre not considered in the inpact of the initiate the low'RC precourc ESTAS, RC pump trip since they do not In addi-and tiicrefore, there would be no coincident pump trip.
tion, these events typically do not' result in an empty preccurizer Reactivity or the formation of a steam bubbic in the primary system.
In addf-trancients ucre also not concf dered for the come reasonc.
tion, for overpressurication, previous analyses have chown that for
~
the worst cace cond$tions, an RC pump trip will mitic9tc the precourc This results from the greater than 100, psi reduction in rice.
preccureattheRCp}umpexityhichoccursaftertrip.
C.
Anniv63c of Concernn nnd nenuits t
1.
_Syntem tenrennuri: ntion in order to recolve this concern, an analycis was perf ormed for a 177 FA plant ucing a !!I!;ITRAP model based on the case oct up f or TMI :2, Figurc 3.1 shows the noding/ flow path, l
schenc used and Tabic 3.1 provides s description of the nodes' and flow, paths.
This case accumed that, as the result of a small steam line breah (0.6 f,t.
split) or of some combination of secondhry side valve f ailure, secondary cide heat demand uns increased' from 100% to 138% at tine scrol This increase l1 in accondary side heat demand is the smallect' which results s
in a (high flux) reactor trip and is very cinilar to the k
l vorst moderate frequency overcooling event, a failure of.the 3
In the analysis, it was assumed u
steam press'ure regulator.
that following HPI actuation on low RC pressure ESTAS, main feedwater is ramped down,11SIV's shut, and the auxiliary f eedwater initiated with a 40-second delay.
This _ action uns taken to stop the cooldoun and the depressurication of the system as soon ac possibic af ter IIPI actuation, in order to minimice the time of refill and ieprescuri:ntion of the I
110th 11P1 pumps ucre assumed to function.
system.
The calculation una performed twice, once assuming two of the four RC pumps running (onc loop), and once accuming RC pump trip right af ter llPI initiation. ' The analysis shows that the In system behaves very similarly with and without pumps.
both casco, the pr.cnsnriner' refills in about' 34 to 16 minutes from in$tiation of the transients, with the natural circula-
.m een ** en amp-
. amas -
emusemeses esse W **
' tion case rc11111ng aucut one minute vem o u.c
-..a
... a two of four pumpc' running (Sec Figurec 3.2,3.3). In both eaccc, the cyctcm is highly cubcooled, from a minimum of 30*F to 120*F and increasing at the end of 14 minutes (ref er to Figure 3.4).
It ic concluded that an RC pump trip follobing HPI actuation vill not incroacc the probability of causing a LOCA through the prescurizer code cafetics, and that the operator vill have the came lead time, ac well as a large margin of subcoo]ing, to control HPI prior to safety valve opening.
Although no case with all RC' pumps was made, it can be inf erred from the onc loop case (uith pumps running) that the subcooled margin vill be slightly larger f or the all pun;p'c running casc.
The pressurfacr vill take longer to fill but should do co by 16 minutes into the trancient.
Figurc 3.t shows the coolant tc:nperatures (hot icg, cold icg, and corc) as a function of time for the no_ RC pumps case.
2.
T,ffect of Stem P.ubb3c on Naturni Circu3ntion Cooling For this concern, an analysic.was perfomed for the same generic 177 FA plant as outlined in Part 1, but assuming that 2
as a result of an unmitigated large SLB (12.2 f t.
DER), the excessive cooldoun uould produce void formation in the pricary s
system. The intent of the analysis was to also shou the extent of the void formation and where it occurred.
As in the case analyacd in Part 1, the brech was symmetric to both generatorc nuch that both would blou dot.n equally, maximining 2
the cooldoun (in this case there was a 6.1 ft.
break on cach loop). There uns no 11SIV closure during the trancient on cither steam generator to maximinc cooldown.
Also, the tur-bine bypass system'was accumed to operate, upon rupture,.
until isolation on ESFAS.
ESFAS was initiated on lou RC 4
pressure and alco actuated HPI (both pumps), tripped RC pumps (when applicabic) and isolated the MFRIV's.
The AFW was initiated to both gencrators on the low SG prescurc cinnal, with minimum delay time (both pumps operating).
This analysin was performed twice, once assuming all RC pumps running, once with all pump: being tripped on the HPI actuation (after ESPAS), with a short (sS second) delay.
In both cance, voids were fomed in the hot lege, but the dura-
f tion and cize verc cualler for the cace'ulth no RC pump trip (ref er to Figure 3.7).Although the RC pump operating case had a higher cooldoen rate, there was Icon void forma-The tion, reculting irom the additional cystem mir.ing.
coolant temperatures in the prcccuri:ct loop hot and cold lecc, and the core, are choun f or both cases in Figures 3.5, 3.6.
The core outlet precoure and SG and pressurizer icv'cle versun tinc are given f or both casen in Figures 3.S, 3.9.
This analycic shows that the system behaves similarly with and without pumpc, although maintaining The RC pump flow doce cecm to help eitigate void f ormation.
pump flow case shouc a shorter time to the start of pres-curizer refill than the natural circulation cace (Figurc 3.9),
glthough the time dif f erence does not cecm to be very large.
Since the volume of the hot leg loep above the louest point in the candy cane portion is about 63 cubic feet, thoce steam formations have the potential for blocking natural circulation in the hot Icg As a result of these findings and since TRAP had not been loops.
programmed to closely follow this specific condition, an additional It is based on the unmitigated 12.2 ft steam TRAP case was run.
line breah with RC pump trip, since thic case represented the bound-ing event f'or steam f ormation. This case included a more detailed noding scheme and conservative bubble risc velocitics (5.0 f t/ccc) to the upper regions of the hot legs such that the effect of steam formation on natural circulation in the loops could be observed.
The noding and flou path scheme.used in this model is shotm in Figurc 3.10.
Table 3.2 provides a description of these nedcs and flow paths.
Figurc 3.11 details thc. hot Icg - candy canc -
upper steam generator shroud noding and flow path model superimposed over a scaled figure of those regions.
The flow path positions and sicos u,cre carefully chosen to al]ou for countercurrent secam and This model is concistent liquid flow at the top of the candy canc.
with that used for the small break LOCA analyscs described in Sec-tion 6.2.4.2 of Ref. 5.
The results of this analycin shoucd atcam formation only in the prennuriner loop (refer to Figure 3.12). These steam volumes arc conservative cince they include all of the nteam that was calculate?
as being entrained an bubbles in the liquid. The additional utcam J
volumen calculated for thin loop, compared with those shown in Figure 3.7,. arc due to the additional boiling and nteam neparation I
that occurs in the candy cano as the liquid flow rates are reduced by etcom formation and aided by me.a1 heating., The lack of steam forma-tion in the non-precourizer loop 'B' is a'ttr'ibuted to a correction in the metal heat transfer and metal heat capacitica calculated for the hot lecc. The previous analycis'crroncously includcci half of the cteam generator tubes, haced on the calculations from the ECCS CRAFT model.
Since the TRAP code aircady accounts for the tube metal in its cteam generator model, this represented an unnecessary concer-vatism and it uns dolcted from the model for this casc.
This case chowcck that the natural circulation flow was temporari.1 reduced. This flow reduced in the prcccuriner loop to 45 to 100 lb/sce frca 250 to 360 ccconds (ref er to Figure 3.13), with flow steadily increasing after thic time period. The flou in the
' non-pressurizer loop remained relatively unchanged at about 10C01b/cc (ref er to Figure 3.14).
Core flow was maintained from 1000 to 2000 lb/sec and no void formation occurr'ed (ref er to Figurca 3.15 and 3.16).
The steam bubbic was collapsed, natural circulation fully restored, and a grc'ater than 50*F subcooled margin achieved in the prescurizer loop (refer to Figure 3.16).
Both secam generators and the pressurizer estchlished level and the system pressure was
\\
turned around from the HPI flow by 14 minutes into the transient (refc to Figures 3.17 and 3.18).
3.
Effcet of Return to Power There was no return to power exhibited by any of the BOL caccc analyzed above. Previous analysis experience (ref. Midland FSA%
Section 15D) has shoun that a RC pump trip will mitigate the f
consequences of an EOL return to power condition by reducing the cooldown of the primary system. The reduced cooldown cubstan-tially increases the nuberitical margin which, in turn, reduccc or climinatcc return to power.
D.
Conc 3 unions and Summnry A general ascesement of Chapter 15 non-LOCA cvents identified three areas that varranted furthe'r investigation for impact of a RC pump t. rip on ESFAS low RC presourc signal.
1.
It van found that a pump ti-ip does not significantly chorten the time to filling of the preccuriner and approximately the came time f uterval for operator action exista.
~
e--r, s
.r-.
F 2.
For the maximum overcoo1Jng cacc analy::cd, the RC pump trip increased the amount of void f'ormation in the hot leg ' candy canc' of t.he prescurizer loop; however, natural circulat' ion' uns not completely block'ed. The steam bubble was collapsed and full natural circulation was restored.
Core cooling uns maintained throughout the t'ransient and no void formation occurred in the core.
3.
The suberitica'l return-to-power condition is alleviated by the RC pump trip caso due to the reduced overcooling effect.
Based upon the above assessdent and analysis, it is concluded that the consequences of Chapter 15 non-LOCA events are not increased due to the addition of a RC pump trip on ESFAS low RC pressure si nal, for all D
177 FA loucred loop plants.. Althou;;h there werc.no specific analyses perfofmed'for TECO, the conclusions drawn from the analyses for the loucred loop p3 ants are applicabic.
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Pressurizer 15 Steam Generator Deencomer 16,24 Steam Generator Lower Picnum 17,2.5 Secondary, Steam Generator Tube Region 18-20,26-28 Steam Ricers 21,29 Main Steam Piping j
22,30 Turbine 23 Contadreacnt
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Core Dypass 2
i Upper Picnum, Reactor Vessel 3
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~ Cold Log Piping 9,16 Downcomer, Reactor Vescel 10 Pressurizer Surge Line-17 Steam Generator Dounconer 18,19,26,27 Secondary, Steam Generator 20,21,28,29 Acpirator 22,30 Steam Riser, Steam Cencrator 23,31 Main Steam Piping 24,32 Turbine Piping 25,33 Break (or Leak) Path 34,35 HPI 36,37 AFU 38,39,43,44 Main Tecd Pumpo 40,41 LPI 42 Tabic 3.1 e
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(
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. Secondary Heat Transfer Region, S. C.
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