ML20204E986
| ML20204E986 | |
| Person / Time | |
|---|---|
| Issue date: | 08/30/1982 |
| From: | Mattson R Office of Nuclear Reactor Regulation |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20204E909 | List: |
| References | |
| FOIA-88-99 NUDOCS 8209290302 | |
| Download: ML20204E986 (3) | |
Text
___
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UNITED STATES I ,*# paisgy NUCLEAR REGULATORY COMMtsslON h QV h!al WASmNGTON, D. C. 20SSS y,
- AUG 3 01982 nf MEMORANDUM FOR:
Darrell Eisenhut, Director, Division of Licensing FROM: Roger J. Mattson, Director, Division of Systems Integration
SUBJECT:
BOARD NOTIFICATION CONCERNING RECENT .SEHISCALE TEST, RESULTS SUK".ARY ,
The purpose of this memorandum is to request that you notify all PWR licensing boards of the results of a recent Semiscale "feed and bleed" test.
During a recent test in the Semiscale facility
- in which the "feed and bleed" mode of core cooling ** was being tested, uncovery of the core simulator occurred, causing the test to be prematurely terminated to
' prevent core simulator overheating. The relevancy of this result is that core simulator uncovery was not expected to occur.
BACKGROUND _
Recer.t licensing proceedings (in particular TMI-1 restart hearing) have focused on the ability of PWRs to remove decay heat using "feed and bleed" cooling in the event of loss of all feedwater.
Altnough neither the staff nor the licensees or applicants have ever relied upon feed and bleed in order t' meet the Comission's regulations, and although the staff ha> never concluded that all plants ,
with installed HPI and safety-relief systems can successfully "feed and bleed," we believe that there is an inherent margin of safety attributable to a feed and bleed capability.
CONTACT: H. Keane X28957
- 5emiscale is a test facility approximately 1/1500th volume-scaled to a typical Westinghouse 4-loop PWR. ,,
- "Feed and Bleed" refers to a mode of core cooling in which all feedwater (main and auxiliary) is not available, and decay heat removal is accomplished by adding coolant inventory with the HPI system, and removing decay heat energy through the safety or relief valv s-
/ . -
e
g , ,'DarrellEisenhuy}c SEMISCALE RESULTS AND REL_IANCE, .90 1982 The Semiscale test simulated a loss of all feedwater with a complete dryout of the steam generator secondary side. The scaled FORV was C opened as the recommended action to depressarize the system to below the HPI pump shutoff head to allow the HPI flow to restore primary coolant
'- inventory. Prior to achieving an equilibrium thermal hydraulic M condition f or core cooling, the core simulator rods began to heat up excessively. This caused the test to be prematurely terminated to
- d. f
,. protect the core simulator rods, w,
The reic.ance of this result is that core simulator uncovery was not c,j expected to occur. Pretest predictions were not performed for this 2 - particular test, and it is not known if any new phenomena occurred that G were not capablo of being predicted by current analysis computer codes.
.i4j (The expectation that no core simulator uncovery would occur was based
'L'-; on engineering judgment and not on detailed calculations.) Thus, the applicability nf these results to the feed and bleed capability of large PWRs is unknown. Further information is presented in the RES memorandum
! from Bassett to Speis covering this topic which is attached. ,
A related test has been run in LOFT, which is approximately 1/60th in volume compared to a typical Westinghouse 4-loop plant. In this test.
- the PORY was latched o,oen and the system depressurized to below the HPI shutoff head (the HPI was not allowed to inject for other testing purposes). There was no indication of core uncovery. ,
Westinghouse has also performed an analysis that indicates that with
~ low-bead HPI, core uncovery would occur it feed and bleed is not
- , .; initiated before the steam generators have dried out. An analysis of a PWR at the Semiscale test conditions is part of the resolution plan.
y RESOLUTION PLAN 7.i. To fully understand the relevance of the test, the following resolution
? plan will be pursued by the Office of Nuclear Regulatory Research:
.jj ,
Analysis of the Semiscale test, including study of the data and j) q 1.
RELAP 5 computer code calculation of the experiment.
l j
A , 2. Analysis of the atypicality of Semiscale as compared to the PWR for l
.yg this type of operation. ,
1
- 3. ' Analysis of a PWR for the same conditions that existed during the '
g Semiscale test with the RELAP5, code. ,
. .g
. CONCLUSIONS Nn Based on our assessment of the results to date and or, the criteria of Office Letter Number 19, we do not believe that a board notification is -
- f warranted. However, due to the interest in feed and bleed cooling in
, A. recent licensing proceedings, we believe it is in the best interest of the regulatory process to infonn the licensing boards of this recent I 4
. .p, g " ,
, Darrell Eisenhut h @' -
2 AUG 3 01982 4
.y.1 d test result. We do net believe that sufficient infonnation is available 7 yet to draw any conclusion from the results. We also do not believe M that these results adversely impact our present staft position regarding reliance on feed and bleed cooling. We intend to pursue resolution of
- the issue with RES. We expect this resolution by approximately 4 September 30, 1982 and we will inform the boards of our conclusions at 49 that time.
,f ,o 4 C.
^ ' p/ L c)C \, -
Rogef J. ttson, irector
.g- .
Division of Systems Integration "A) '
Enclosure:
As Stated
. cc: H. Denton E. Case
' G. Knighton
. S. Hanauer R. Minogue, RES D. Ross, RES ,
- O. Bassett, RES H. Sullivan, RES R. Landry, RES G. D. McPherson N. Lauben T. Marsh y~. .
W. Hodges G. Mazetis y
. W. Lyon R. Barrett M. Keane T. Novck G. Laines W. Jensen D
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fiUCLEAR REGULATORY COMMisslON wAswiNoTow o. c. mosss
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- s. m***** AUG 2 31982 2'
MEMORANDUM FOR: Themis P. Speis. Assistant Director d- for Reactor Safety Division of Systems Integration la 0. E. Bassett, Director FROM:
3.i.4 Division of Accident Evaluation
- .(
' ' * ~ Office of Nuclear Regulatory Research
.:r SUBJECT : FEED' AND BLEED EXPERIMENTS IN SEMISCALE NJ l As you are aware, RES has performed a Semiscale feed and bleed experiment (S-SR-2) at the request of NRR. Results of this test indicate that
~6 difficulty was experienced in maintaining a steady-state feed and bleed 1 condition without uncovering the heater rod bundles. Several members of
'g your staff have had questions as to how this relates to the PWR feed and bleed operations being purposed for several plants. These questions are w now being addressed by EG&G Idaho, Inc., while taking into account the atypicalities of Semiscale, as they might affect the feed and bleed m behavior.
- :, m
"' As a start, EG&G have provided a letter report of several steady-state calculations tfiey have performed in an effort to help understand the Semiscale data (see enclosure). These calculations included a ciudy of
- .]i "Y the sensitivity of the results to core power, break flow quality, surge ~
j '
line and pressurizer geometry, and availability of equipment, and were
-' extended to parametric values typical of a cormercial PWR. The report concludes that there are large uncertainties in predicting the satisfactory i performance of feed and bleed in the steady-state, but that the Semiscale l experiment does not point to the existence of a definite problem regarding the satisfactory performance of feed and bleed in a,PWR. The Semiscale results still must be analyzed to deterraine the extent that the atypicalitit i effect the results and to put them in proper perspective. This analysis work is currently in progress and shound be completed in September 1982. ,
The Division of Accident Evaluation has concluded that. the Semiscale results have not produced new and unique results that indicate a PWR '
would have a definite problem regarding feed and bleed. Therefore, we
-- do not recormend a board notification. We have concluded that the M Se:aiscair: results should be carefully analyzed to determine that relevance
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to PWR feed and bleed transients and this work is now in progress. We .
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cam should be able to provide you with a more complete answer to the relevance qt, of the Semiscale experiment and our investigation into the feed and ~
1,1,bi . bleed transient in a PWR by late Septamber 1982.
.:44 o ; /d h -
sirq O'. e.. Bassett, Director 3*hM Division of Accident Evaluation Office of Nuclear Regulatory Research
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. '. 3.' j Tiller dtd 08/06/82
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L. H. Sullivan, EPB ,
. . ..&,'f R. R. Landry, EPB *
- B. Sheron, NRR
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'4,9 Mr. R. E. Tiller. Director '
acw Reactor Operations and Programs O(vtsfon .
- Idaho operations Office - DOE . .
_.:;.; Idaho Falls, ID 83415
. W.;c+)r w PRI,MRY C00 TANT SYS1EM FEED AND 5LEED - PM-137-ts2
.; ais ~
~'E Dear Mr. Tiller
- At the request of the Nuclear Regulatory Cornission the Semiscale
..' Program recently conducted experirrents designed t.o investigate the
'.~
feasibility of primary coolant system (PCS) feed and bleed as a means of rejecting decay heat in the absence of steam generator heti removal. ;
g The results and preliminary analysis of the emperiments soggisted that a reasonable uncertainty may exist in the ability to effect stable PCS feed and bleed. Since current pressurized water reactor emergency
- operating guidelines call for primary feed and bleed unoer certain abnonaal conditions. it was coraidered of scot importance that the
. +~Q- general subject of feed and bleed be studied in some depth aaf th6t the femiscale results be carefully analyzed so that they might be inter- l prated in the proper perspective. To this end, the *emiscale Program
@j%,-
is currently engaged in an extensive analysis effort invohirs troth
'=6 full-scale plants and experimental results (i.e., Semiscale and LOFT).
- eg ' The purpose of this letter is to provide a brier overview of our analy-sir of feed and bleed to date, including the recent Seati cale results.
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Prtuary coolant system feed and bleed in a pressurized water reactor 4+i. beccees a necessary decay heat recoval ecchanism in the unlitely event that all secondary heat renoval capability is lost. While there ea.ist
'M i t . nmerous secnarios t. hat could lead to this situation the focus of
. thrt present analyses .is the.Jetsthility of achieving,a favorable cool *.
- v. 2 ant tioniand energ,,bal,ance w ,h,in,,the,,pri,m ry_ cool,6n_t,,,sys.tjej ,under .pond
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- 1.' the reacht h'as 'sNW -
.- . , . . . . . . . . . . . . _ - . . . - . . . . . 1
.. . 2. the steam generator seconderles are completely depleted af c .,o o .l .-ant,- . e. . :.
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. August 6, 1982 ,, .
Pete 2
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.. a n undegaded r, pts s s ure .f adecti on_tys t em (ECC S) conditLen
- . 4. the pres'surtrer hea, tert are inactive 1 - r. .
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6'.'"'"th~e Fressure~o~peWted'Irelief valves (s) (PORys) are e;
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WQ' '.f ,,' 4. prfeary recirculation pumps are off . .
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Feed and bleed would commence when the PORYN) were opened (bit
- ' .P y! - - " . - - W P. .
and high the PORV(pressure injection began (feed).-tion s)
The passage of stea-j
. .g .
d.. p.
coolant provides makeup for the resultant coolant
.i Yht reastnder of this letter examines the general as>ects of pr 1
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feed and bleed opera.tfon and the thermal-hydraulic pienomeda tt goverd it. The p'r edicted tysten Hsponse 1s out1Ged ff rat hu V
t ' i- '
effects of uncertainties are illustrated with an exaryle fras a plant parameters. Next the key thermal-h 1 -
fluence the uncertainties are itscussed. ydraulfs phenwnene Finally, the data fre the
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Seelscale experleents is briefly presented to demonstrate syste j ... tures and resporme during an a.ctual experiment.
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_ THEORETICAL FEED AND M.EED OPERAT)#G PRESSURE KJUCC
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4 -
A sisiple examinatta of the sus and emerny. transfer pathways a
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- f. .
sted wtth feed thd Clee'd pesultFin tMWnclui%h that feed W i
- 4 ..
.is theorettcally possible within e certain band of press,uce (se l ,mp W&JdN'r.tec.l.J,he
~_
U ' y taatgo'verning
'Hi/tTP94 pa'Pit rage f1 etermine ,t.h,j s .ressueg bar,
- (an'd enthi
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. ' fl6W Mte). fuept f6r"L e. my e'at lev (e1Ylomi 'y recatata;
.f 2-
,g;. 1. * , peter,s. are function's"of prthiry. 'dysted fdstirre.,.' hit Tower heiq. .
- 3. , the','t$arating band yp're' rents AAe afniswa $cesstree 6'i which tt
..q.;.'4, .: . con pass enough stema (with the coolant replaced b
. c.9.bif-e~ , -
.',G ig,. h d' ..
.... operados .wster)lto .resqva tietow surf.fetentieneek.ft:gs tblf prkis6tf'wi tdditional enfrgf f6 the Steady-ste swatsys i ,.a
....i 'L.
. .14.aot:pos:ible.L operatIo6Wti ords:ure above the toner be.e4 1 .. , lbe accc.911shed by cycling the PokV open and closed within a de 5: - .
pressure band. .
. - 3 i e$ - "
An upper pressure bound to the steady state operating band is e
'q'5: V-i .
W'A pes %"' n. - -
. b a balance between the PORY average coolant r:emoval rate and NIS coolant injection rate.
3 The average PORV coolant removal it simply defined as the core power div"ded by the difference t ;
4
- Q'n=4 waseme g'
. inlet and outlet enthalpless
=-
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- a. Base case conditions asswee that 100g quality steen is else ,
..b.m g lp- through the PURY. The affect of yarted qual 4ty is examined j j
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August 6.1982 P494 .3 .
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" . ... . (This esstries that the coolant iw;4 through the FORV is replaced
.. with tebtent tennerature water. Actually a coolant deficit exists
.4 et pressures hig ser than the upper bound and o steady state conditten ,
a cannot exist due to a'centinvat loss of system toolant inventory.1 b;l Selow the upper bound the system mass inventory can theoretically be I maintained within a desired operating range by either throttling ths c,
0 HP15 or cycling it on and off. .
l UNCERTAINilts ASSOCIATED WITM STEADY-5 TATE OPERATING PREssoat SAND i
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4eloot.wp1)
, 'N" .M,. e), pfs tf#'t., the .cdryei)]31sMsedAeve krt5$estertiintyenrs
.unc... deft'ned.due
.PMV. ss. . .gcerLathti'eR. Sub.1ecki59.thecr h .v- theg . HH
- 4 the PORV 1s degndent on the fluid conditions at the top of the pres-i* .
' surizer. If t se pressurizer is near liquid full the flow through the l
d*' *' PORY will be e alsture of 11guid and ' vapo 7. At a given sytten pressure this results in great'er mass flow than for saturated steam f1W through l 7 the PORY. The result of having two-phtse flow through the FORY is j- therefore to lower the upper bound pressure.
[ Uncertainty also arises in the PORY energy renoval curve due to two-phase flow. With decreasing qualit 3
~ -
decreases while the mass discharge rate y theincreases.
energy removal E(pendi per unitupon mass "q the quality the energy removal rate at a given pressure may 1 .,
than or greater than that for saturated state. The 1wer boyndless of i
e", , , ,
, the ope' rating. bend wl.11.Mr,y~.' ado,rdingly..
ev Another signiffeant variable that affects the width of the operating
.e band concerns the actual heat lead that most be rejected through the FORY. Core decay heat decreasts continually with time af ter shutdown.
- -s
- i Also, if some additional heat sink exists, such as environental heat loss or residual water in the steam generator secondaries, the heat load required to be re.jected through the Por.Y will decrease.
i . to F1 ure 1 this results in lowerf the core pwer line **d tSes,- Referrind
- i. . , lower ng the bottom end of the opera ing band, and also lowertag the .
- 4. FORY ins band, average mass f1w curve. thus raising the upper end of the operat-
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, . . ' . ih'e finsi Uncertainty addressed here is the smcertainty associated g .
6 tith the HP15 injection curve. The tFf'ects here are rather clear; I
.a a lower inject. ion rate wil) lower the upper end of the operating b
'l" the quantitative effects of the uncertainties andt'or variances dis i@ s "
sed above are illustrated in rigures 2 through 6. For these examp
. Li s : -
. the curves tvern q9ngteo using data obtaines from'the lio9 ! nuci
- f"@ F i#'t . generating plant. '. a 3411 MW(t) pressurized water reactor, Ff
.- 2 shews a primary feed and bleed map for si h eecay heat p=tr lev i
P.N'**b.
MfM "
A steady state operating bar.d is seen to exist between 7.5 amr 14 A tiecay heat level of 2t of full power is typical of the tine. geri
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free about 10 min to 20 min after shutdcwn. Figure 3 is a sistler curve, but here' no makeup purrp injection is assumed; only the HPIs 4 ip ," ' . pues were assu:ued to be operating. 1he HPl3 pumps are showr. to d
. *. . - head at ahnut 10.3 Ws. For this t.asa no aperating band palsts, 3
- D _. .. at the aitnimum prosaure whers the PORY can rt:nove the energy there
,- ;, - - o is a mass deficit between the PORY coolant. removal and the HP!$ tr.
tion capacity.
m . ' ) .... '. . ' ' .
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rigure 4 shows the primar.y feed nd bleed map for 1 1)2$ rutt powe a decay heat level typical of the period from 1/2 to 1 hr af ter st dow, and for only HPl.% injection. Cceparison to rigure 3 shows t
~/ . - the reduction in core penver and corresponding PORY average mass f) l
' '? ., . ; ~
both act to establish a steady state operating band. ,
f ,1, *1
,7 3..'
The above curves are bas.ed upo'n the assumption that 1001 quality s exists at the PORY. Figure 5 shows the sensitivit of the MtY er.
'. reeoval curve to lower qualities as determined witf the HTM flow a
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Since the energy reinovel per Unit mass decresses while the mass f1 rett increases the energy removal rate inillally decreases with de !
. ing quality. However since the mass f'10w rate increases sutrstant J
' Y.i' l' -V.1l. irl'.h decreasing quell ly the energy removal rate eventus11y. tnereat '
) t ',' O ' . i . . /. . The effect on the lower operating bound pressure is not larget htm
'~
the large increase in PORY mass flow rapidly lowers the uger end
, ' 4E..e.. ./,. 7 ',' '
I
~ c .'. ' . . the band. At an example, for the conditions used in rigure 4 the ;
j -+ 'l.i.' -
operating band does not exist at qualities below approximately 75) l tsee rigure s>. .
4 l T *
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. The foregoing snalysis is usefui. In that it pE.videt a bails for '
i
- 1. ..$g
. exantning the feasibility of feca and bleed and for quantit.ative): 1 i P. e '. .
- assessing the effects Of unce.rtainties or variations in the Leound. '
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' However, it does nol ' address transient behavior that at M
an important bearing on the ultimate viability :( primary feed l and bleed. In particular, it' should be evident that there ex1sts at ,
a k:.'i.] . - uncertainty regarding the ability to safely bring the primary conlar i
.. . a... System to within the "feasible
- operating pressure band withcut sust '
- \.
ing unacceptable coolant loss in the process. Tactors which bear or i
.. ..>-. )42. ;. ? . th< s transient process include the primary coolant system state at f ' . .
- f, ,
. . the initiation of en atte:spt to f eed and bleed, and the nature of tl '
tuulant disr.harged through the >0RV(s) in cepressurising the systen
. .M- r. .r . ". .
to trithin the operating band. These questions can only be addresse( ;
.y . . .. f c . * '
threugh capernmentation and the use of cunputer code, analyses. * '
' 0.%; ./: *
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, e ACTORS Arr(C,T,1,N,q ,PORY D15 CHARGE . ,
's,.< : . . . . . .
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Of the betoi s previously discussed sni isegest uncertainty affectin ,
the feed and bleed operating band arises from the influence of two- '
. phase PORY flow. The mass flow through the PORY is de '
st~ ream fluid contlitions at the top of the pressurizer. pendent on fact up
- ":
- M,. Several contribute to' establishing pressurizer fluid conditions. The ones
>' discussed here are. transient vs steady-stats behavior, pefmary coe l 4 4 W.$.. c.
ant system conditions, pressurizer / surge line geometry, and surge 11
- .. A . '. - orlentation.
Y9 , .
jravs tent,,vs hteady-State conditione and primary In ren,t,ory or 7 '-4 e;k,'.. . ,if-feed and bleed 14 not initiated soon after loostreg the se<codary 1 ;.: -
., heat s)nk the primary liquid steell will fill the pressurlaer and col-
- p
- . - ' lasse the steam bubble. Several conditions may form or sustain a va; '
'" rf . . bu>ble at the top of the pressurfrer. A vapor bubble can be r.roduce: <
. . #.S. . , ;
- by loss of pressurizer liquid inventory, heating of the fluid to satt ;
& y. :- tion, and/or depressurization.
i V;,' . . - heaters are assumed to be non-o. perhtionalIn the present and studyheating direct the pressurirer is ther I 9 fore precluded. In a transient depressur{ ration. liquid flashtr.g in b'g.j #m. f, . the pressurizer will tend to crr ete a high quality region near the l .' .' top as long as the fluid in the pressurfrer is the hottest in the l..' syst ers. However the liquid swell that accompanies bulk fleshing wi'
. 4. 1,' tend to decrease,the quality at '..% top of the pressuciter. . f"oc eitt j fa ;
~ e quest-steady state situation or in a transient once the original pressurt2er inventory has been, replaced with coolant frere the hot let 4
~
i . ' ... the PORY fluid conditions are dependent uoon the conditions in the 2 ,*
hot leg. If the coolant lost through the PORY is replaced by low 1
f . '.
? ty fluid the mass discharge out the PORY will reecin fairly high 'qu'
! . T- -
This will occur until the primary system inventory is. reduced enough l
I
._t .1.,'. .
to cause significant voiding in the hot leg. O nce significant het
. ammame. leg voiding occurs pressuriter/ sur come into play as described below. ge line ge oeetry and orientation
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.' fresidriter/ Surge,,_Line te,gnetry :
i .- for d gived vapor volume a bressur' iter with e large tength-to-diar ,
Sk#
M l.1' , i. ..l.
0 -
retto would have e "tal)" void height relative to e pressurizer w 4 a sr. aller ratio. in addition to also having a sas11er cross-sect 0 l r
0 @'..'m '**,*-
A steam bubble of greater height would tend to enhance seoerstion ,
i the vapor of liquid droplets created b bubbles bresting through i wi dc ,
o.4 g .
liquid surf ace, due to the greater walk surface tres and reduced rJ'-4 : ' l - potentlat for droplets laelng thrgwn upward linwever. into the vapor since high vapte av,t b ve' '
l 21 ' ':.
area near the P0M line entrance . ne '
9.P ' - -
necessity pass through the pressuri2er liquid from the surp !!y the PORY a large L/D would ' Lend to promote liquid swell and dropf entrainmert due to the smaller cross sectional area.
%y. .'.
- 4 in any esse. the influence of the pressurirer geometry may be min j J-by the preclusion of counter-current flow in the surge line. Eve '
a ifquid/ vapor separation mechanism did exist in the pressuriger. l typical Surga: line valocities are well above flooding limits.
- 9444 l .
fore, the liquid could not drain ~ back to the loop and would conti i T.t i /.i - -
to be stored in the pressuriter until the PORY dischar e quality el. s*. s! l j **" p"M' e :
adjusted to acco:tyr,odate removal of the mass. It there e.re appear l necessary to have high quality steam supplied from the hot leg ir. '
4 ., ,
- w.g *! . . -
to have high quality PORY discharge.
i f t'
.M.rge line Orientation -
1
?
If hot leg voiding does occur of the surge lint
' #9 '
influence the primary system Ir.the orientationventory at whi
. ,u ef?'
O. .
- entered the pressuriter. Surge line to hot leg connections of v4 orientations, from horizontal side entrance to vertical top entri are used in current PWR's. With the it9 entrance line, end quie
- "M' .m . .
leg conditions. minimal hot leg voiding is necessary to a77ow ab surge line flow. With a side entrance line the' hot leg rim lic.
. d. bq p' '.; .. -
In either w .o -l . .# : . . . mnt drop much toer before high quality flow begins.
- - ;" .W -
the surge line flow ray still be varied significantly if non qui.
conditions exist that disrupt strattfled flow, such as when pria4 j . 14 ' ' .dl. . ; . .
recirculatica ptanpt are turned on or a transient depressurizato s -
occurring. * -
, 51. . ,
j "Qpgp.$ [.'*,: ,f, 7,. ,
j
..w 4'1 .*-~ .
l f or typical PWR pressuriter dimensions ,the vapor velocity ( '
' 4' .g * /. ". 6.
i
.J en open PORV) in 4 vapor illled cross-section is on the.orde
- * *W '
f t/s which presents little thence of droplet entrainaut.
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. . . } .2 .. '.August 6. 1982 page 1
.ep" .; . 2 ..
.- e . .
ch. ;v......: . . .a: %.g
~
CONCLUSIONS BptfD bk 51HPt lf!CD $ALYSIS Iasedo4tsforekoing5se sien i is concludd that a sis 5dified thSMi
%MR J approacn to chter ning the feasibility or primary feed and breed in a pressurized water reactor lies in the mapping of anergy and mass flows. .
?'M: . : .. .
Moreover this technique can be used to quantitatively. assess the j
.' b ' . . - sensitivity of the operating pressure band to variations in the
- 4. *- boundary conditions of ECC5 flow. PORY flow, and decay heat. It is evident that plavsible variations and uncertainties in these caremettr!
' i. m ..,..
': ..','3.',!.
gL can lead to the eliminat{on of 4 steady state operating pressure range.
... Princioal among these uncertainties is the coolant discharge 1.hrough l the PORY. The predictability of this single parse.eter is sdiject t,o
- .':':.. much greater uncert'atnty than either, decay nest. or ECCS flom,
. a. . . .
4 'i' " . *
- lirrespective of the existence of a theoretically feasible oper3 ting r'
- pretsure 1 and, there remains tne question as to wheth.er the reac. tor-system can be safely maneuvered into this pressure range. In this regara it is clear hhat a dependence must.de placed on computer code
' ,, Y. . .
~
analyses (with suitable verification) and adequate supptrLing experi-
..~. . mental data. Such analyses and/or experiments should examine the plausible scenarios which lead the ooerator to counce prim 4ry feed and bleed, since the initial condition of the primary coolant systes
+
?c.'...
, (p,rticularly inventory) wi.11 have a significant effect on the outcome.
,y ,
6 S* ' -
'lurthermore, it would appear to be i useful exercise to examine %be
- f.M eperatin meters. g e.ap The operatino that results map forrepresents each set ofanindividual ultimate statement PWR p16nt as.t.o para- whet
.. ut.i J.'! ? ". ? feed and bleed is possible. And is the starting point for tasmining
'7g/1, ' '
specif te design features that bear on the operating bounds. .
,,, $ } ;
Ar$ TATS FROM SEHl$CALE EXPCA!MENTS u . . .. . ' ' '
f.:.'b' An 6xperiment was condueled ln the Semiscale Mod-2A feiilit) to evalust
- " P.#- . .'3 .
system behavice during primary feed and bleed operatiens. Figurt 7
' Q .'. . * - shows the primary feed and blet'd operating map representing bcundary
- ..'*. tenditions used for the experiadnt. It is seen that these prameters
~
deffne a steady-state operating band between 7.1 and 8.2 HPa. Several
... attempts were made to establish steady state feed and bleed within the
% f.' , operating hand. While it was possible to maintain pressure control by cycling the POP.Y. measurements showed a continuous loss of primary J
coolant inventory due to a low quality discharge out the FORY. The
.;... phenomena that led to this behavior are 4 scribed below. .
.;%iii f,. .:; . . -
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- :- s. - - .
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% ;. ". - . ilnoie phate, liquid full condittens were established at a pressure 1$.t NPa. At initial conditions the pressurizer heaters were used l
" .c.. ..i.t * ~ tontrol pressurai with a small steam fabble in the pressurizer, So:
- 1 s. "C','E@.-
- ~?' " ' '. s . ubcooling existed in paras of the loops due to the lack of natura' .
l ': a_ ? v.% .
circulation resultig fron having empty secondaries. At 15000 seo E @'Nf:0' . ' (lest tisme) pressurisar henters were turned off and the PORY was 1 7 open. Figure 8 shows that the tystem rapidly depressurized down t 4
'f74 " M g,i ~ '.' l f ' 'f"'
- ' appronisately & MPs. 1his corresponded closely to the saturation
~c c t(the teldest fluid in the loops. As seen frcan the pressurizer c liquid level curve, flashing of the hot pressurizer fluid initia11 ;'
l 4. i ! ": .S . *- tesulted in substantial voiding of the pressurizer. Re. ferring to i j M. . - -
' :;.v ., . -
it il sten that this is reflected in the PORY mass dinern rge rete.
i 1, P ..- -
follow {ng a brler initial mass flow surge the flow out the PORY ag ,
i i
M . . . i . ?.E . '
~ ~
. ilosely with the predteted steam flow rate ft,r 100; qua)ih. the 4:' . . .; , :, - bubble depleted of ter approximately 250 S (Ngure 8) and t%e FORY l 4 flew rate increased to approximately 5 times the steam 'rlow rate (
- e )). As teen in Figure 9, the sats flow rate out the f0RV appeared
.! dependent upon the condit{ons in the hot leg. Once substantial to of the hot leg occurred the flow out the POA.V began to agree with 4
- S
.(* predicted steam flow rate in spite of the fact that the pressuris
- @.$' TA ' h. - tesa{ned nearly liquid full (Figure 8). (The pressuciter surse li in the Hod 2A systen is connected tu the side of the het leg.)
d.b: e: ~ %. 4. . . , '
I 3.g' '#" .
- Al the time en sufficient. prl, mary toolant inventory was finally 1 to at to void the hot leg trie core was still adequAely covered at
. . .' ' cooled. As teen in Ngure 10, there was still a small deficit in
/!.
- - t. . + -
. Mass injected into the system with the HP!3 relative to the PORY s
. discharge ratt, The result was then a very slow continued loss of
.../
f khich led to eventr uncovery of the core at 6 bout 17000 seconds.
kN'@.5 .:h . the N imporl6nce bf the semiscrie resuits iles in demonstrattb 1 . .N
!. N. ;? -
dependence of the PORY discharge on hot leg conditions, and conter tystes {nyentory. The inability to maintain system inventory once j - W)d.4bCN i *
- PORY hass flew rate dropped to reflect steam flow is subject to e' l .
M Wi V $C,; e.;7 P- %- Oncertainties, since the steady-state operating band of fleure 7 tather atrrow. Uncertainties exist in the actual PORY orifice ch
. h " ,'4"'
y .- tics, hPJf, injection rate and the measurement thereof, systes hes'
- E* y2
' ?'- -
&n.d fluid nakage. .,
j Y.e : h.. b6 observed PCfty discharge relation to hot leg conddiens Nontve outside the effects cf uncertainties discussed above. The questi 7 ? g' "t.- that heed to be. addrested in intarpetting and extrapolating the r
" - a. a l ' .M. v . F ".<. ' ' '
tra largely related to the geomet.ry effects. The Kod-2A system h 1 g66,2#d".
short pressurizar relative to the de:tred scaling of L/D. The L/
en liquid vapor teparation must be analysed. The surge line nett 1
j ""f ""' '.
evaluated also, mainly with regard to tw. influence of the side e 1 . J.~ _ , . ,y g . the hot leg as opposed to other designa.
l ..M. M _
{ w - - v~ J * &, Core power was augmented to cenpensate for the $est estimate j
.- o s heat lost..
k .
1 .. . .
j
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c.. ....:
. 9. . . -
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- !"d . 4. L fillef .'** ' ,' ' l . : '- * -
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.- A0pst 6,1982 ..
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y.. / ,7 ' .' t tenctust, pits.)A$to Ott SEHiscAj.E txPtaljgjgs -
. . .-.f . .
i' 'j : .M.'. ' ". .- !n and of .theuselves,'the }itsulth, from the Miscale entrhneMS do
't. . .. ; " .
not point to the existence of a deNnile problem regardleg primary *
~W'" . P d.- .
feed and bleed. But they do tend to support & concern about the
' ' 7. *<! . - reldtive tenuousnest of the process. Further ent.lys s attempting 1:
.a . : .fl ',. wantify the potentia) er.partmental dtStortic.ns ar.s their effect on
- 1. . . . " ' the results is now la progress. These analyses, along with the
/~',
results t,fons ofofthe anlysts Semiscale. of existent experiment LOTTand data,11-scale a fv plant wfil beand com
- .M. ..ty&)) ::l docuntnted Ia 5eptember.
,y: -.; ; . f::k. . n,. .
y,,.y 'ruIy Wst i,..?.'.'.': f w,!. A, ,JA .
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P. North. Manager.
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k' ster Reactor Aesearch l s
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lust F4cilities D1, vision '
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cc:.f' h. W. Barber, DOC - 2
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R. W. lMehn, EG1G !daho
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