ML19322C422
| ML19322C422 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/14/1971 |
| From: | BABCOCK & WILCOX CO. |
| To: | |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8001170466 | |
| Download: ML19322C422 (5) | |
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J'UIO'OCE To provide the nethed for nizing the prennurizer for 1G! IIuclear Steen Systems.
II.
,GEITG!.7, Its.^unctien The prescuriter is an integral component of the prirary cysten.
A.
is to taintain system precsure uithin n'jsteu derir;1 values t>:d to abscrb syntcu fluid voluna chanf,en during all norral cad abnortal transients.
P..
This procedure is used to obtain the following values:
1.
Pec.icuriner total volume 2.
Prennurizer water volume and steam volu:.'c 3
TYeasurizer spray rate g
I.
Pilot actuated relicf valve capacity I
5-Sofety valve capacity 6.
Prcosuriner curce line size.
- (. Pressuriner electrical heater capacity.
c The following information is recpired to size the pressurizer:
C.
)teactorCoolantSystendecihitemperatureandpressure.
l.,
licactor Coolnnt expected terparature and prencure over the entire 2
load raise.
3.
Stcan cenerator accendary desicn tenparatu' c and pressure.
1 Steam cenerator c:cpacted secondary tc=per ture t.nd pressure cver 1
the entire. load rance.
5 Itenctor Coolant Systen cct.penent unter volvr.:en.
6.
Sten:n system relief and safety valve setroints, and the expected hiondoint for thecc valves.
'/. 'The Ilich I'rcscurc Injection set point.
8.
The prec:ntriner internal dia:cter.
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}HCCEDURE g
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A.
'The prenmtvi: cr $ n cited in the follo<.inc 00 1
)Yeparc n nrnph in the for':at of Pipx 1, referred to in this proendure j
. Imnrernatime o
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EllGit.73.?Ti:G C/.LUJ:J.TI0;:S DES)Cil /J.~J IOl'G.Y'i.::CE /.i'A1/1313 1RESSUill?.Ei!
a.
Curve (a) - neactor Coolant System temperature as a function of lond.
b.
Curve (b) - The band of temperaturec correcponding to the naturaticn temperaturec at the steen cystea desicn preccure and 105% of desicn pressure.
(This is the cetpoint ronce for the steam sc.fety valven. )
' c.
Ctirve (c) - The naturation temperature correnponding to the turbine bypanc nyntem cet point for reactor trip.
Thin proccure ic nor. ally 2% bc30u the seconday synten denico proccure or 50 pai balcu desica pressure, uhichever criterien results in the -higher-presstue setting.
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d.
Curve (d) - The naturation temparoture corresponding to the stecm generator secondary outlet pressure as a function of load for norcal op3 ration.
2 Prepare a craph in the format of Figure 2, referred to in this procedure as gralth 2, displaying the following information:
a.
Curve (a) - Pressurizer outcurge in cubic feet as a function of Beactor Coolant System avernge temperature decrease from the normal average toup.erature at 100% po.rer.
This cul".'e is t.reu2 red for a constent 5Q pressure equal'to high prescure injection set, point plus 200 pai.
The
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curve should extend to the AT value correspondimg to the change in average'temparature from cero power tc 15% po.:cr.
Average tempcrttures 4
uny be used at isothermal conditions for the system.
b.
Ccirve (b) - Pressuriner insurge in cubic feet as a func'[ ion of Reactor Coolant System average temperature inerense frcm the normal temperature at100/,poner.
Thic curve is prepared for a ccnctant preccure ecual to the high pressure reactor trip.
/.verage temperaturec should be evaluate 1 on a voluna neighted basis, system cection by system section.
1005 pocer AT'n should be used.
a Set t'ho pressuriner minimum Icvel at the higher of:
3.
e-n'.
150 cubic feet, or A
b.
the volume in the pressuriner lower head up to the tancent line.
> The Icycl should not drop below this point during or after a reactor trip.
s.
1 Obtnin the maxiuun outsurce.
The outsurge is accociated eith a reneter trip 1
from full power.
Ti'e reactor coolant system temperature vill drop from the reactor coolant system temperatuce at full paver to the temperature corre-cpanding to the turbine bypnen net point.
This is the difference detueen curve (a) and curve (c) on craph' 1, Inbeled AT on the craph.
g M
Go to graph 2 and obtain the myinum normal culsurce naccch.ted with 67..,,.
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froMcurve,(a).
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/.dd the level associated with this outcurso vclure to the level established
$n step 3 of this proccdure.
Thid 3cvel is the miniti= nornal pressuriner leve'1 A low 1 cycl alnra is actuated at this level.
7.
1)ctermine, froe c'.-aph 2, the uaximum surce, in or out, associated uith a S P chance in reactor systeu temperature.
8
/.dd the voluue deterr.ined in step 7 to that established in step 6.
This is the normal pressurizer unter level or volone.
9 Add the volu c from step 7 to the volume determined in step 8.
This is the maximum nornal pressurizer 1cvel.
A high levcl alarm is actuated at this
. level.
10 Obtain the taximum insurce.
The insurge is r.nsociated uith a turbine trip or clowre of the turbine control valves at full psucr.
The temperature of the secondary system heat sink increases frca the nortal tenterature, curve (d), graph 1, into the region of curve (b), graph 1.
The tr.a.kitum insu is that of raising the reactor coolant system tenperature by an acount equal
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to the d$fference bet ecn curves (b) and (d) on graph 1 This value is labeled AT on grauh 1 TT 11 From graph 2, deteruine the insurge associated with AT frr el curve (b) in cubic feet.
TT 32 Add the insurge volume established in step 11 to the voltec established in 4
step 9 This is the maximtm pressuriser level.
13.
])ivide the total unter volice cciablished in step 32 by o.9 to deternine the required presstuizer total volume and tultiply the resultant value by 1.03 to
' ' allow for shop tolerances.
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Set the location of pressurizer level indication taps by the follouing l
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criteria:
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l a.
The lower 1cvel taps must be below the uinin.m pressurizer level to avoid losa of indication during the design outsurge.
b.
The upper level taps must be above the raximum pressurizer Icycl to avoid loss of indict. tion during the design insurac.
l 15.
Set up the JJ.l? and Pouer Train cc:r.puter pregraus (see Standard 2A3-II-2A39-2!.231) for the !!SS using the iEsTY2Tncr volume establiche.1 in step 13 and check and actermine the following:
0 i
n.
Pror.f.ure u '
.ar.s.trirc.r 1crel fo.r! min.: a reacter trip from ftal ;w. r j
and uini:.nri normal presnucizer 3cvel (KAPI' or Power Tr:dn).
Check th/sc values against the criteria uned in step 3 and the following:
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- 1) The lower level ir.dication tap must not be uncovered.
- 2) The resulting pressure must not be less than the high pressurc
$njectign set point, plus 1C0 psi.
3)
If the pressurizer heaters are uncovered, the addition of makeup water to cover the pressuriser heators should nct cause tha reacter coolant sy' stem pressure to decrease to less than the high pressurc
.'j injection set point plus 50 psi.
Pressure, surce rate and proccurizer level for a turbine trip er throttle b.
valve closure frca full power at maximua normal pressuri.er level (Pover
' Train).
Check the values against the criteria used in steps 13 and lb, i.e., the maximun level must be no more than that associated with 9T,of the total pressurizer vol'. sac, and the upper pressurizer level indication taps must not be covered.
c.
)Yessure, surce rate and pressuriner level fo. the rod withdrawal accident from zero power (IMPP).
Check the results against the criteria used in 15,.b. '
[.r -I 6.
Using the ma dmum surce rate obtained in step 15, size the surge line such
)
that a pressure drop of 26 of system deciC;1 pressure is not execeded. This 7-~
,,f' criterion includes pressure drop attributable to the surge difntscr.
l'l.
Pst.imate the safety valve capacity by assiting it equal to the steam ficw required to remove the steam at the maxitnua insurge rate from step 15 10 Input the data obtained to this point into the DY31D computer program.
Use n pressure drop of 50 psi from the pressuriner st.can space to the safety valve throat to allew for rater st: alt and/oruanifoldingandusethepresrure drop *in the surge line fotud in step 16.
The resulting safety valvo enarac-teristics should meet the following criteria:
n'. Peak pressure at the reactor coolant pu:p discharge shouM be less than 1107,ofdesignpressure.
(Md the pressure drep frem the surce line tee to the reactor coolant pump discharge to the pressure at the tcc from DYS]l) output.)
b.
The safe *y valve should exhibit a c3cnn lift and rescat.
If the valves cycle open a number of times, the capacity is tco larne and can be reduced.
c.
The requirements of !.rticle 9, IYetection against Overpressure, of the liSMS Code, Sectic:1 III.
The safety v ily.'s unst be t.dequate fer: 1) the rod withdrsual accident, from lou }v.:er with no credit fer piescuriner Q
spray or pilot act.uated relief valves, and 2) turbine trip er cont.ral valve c]erure frcm.^all p:ver vit':r.o:t cr^?.it or t'.u'. f re b.me : e m re' %
D-or Iniccrated Control System runback and 3) the abilli,y w n..//c L.m...y..
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- 9. Use the Power Train computer code to determine the.following:
s The maximum ir.curge rate durir:g 107, of full power per minute ramp load n.
ch'angen between 15% and 1C07, of full peecr.
The maximum ir.curge rate for a 10% of full power step load change in the b.
' range of 15$ to 1007,of full power.
The maximu:a insurge rates during the guaranteed amount of load rejection.
c.
Use selected turbine bypass flow rates and set points.
e 20 Input the surge rate froa step 19.a. into D'ISID and determine the pressurizer spray flu.i rate required to maintain reactor coolant pressure belou the set
. point of the pilot actuated relier valves during ramp load changes.
- 21. Input the surge rates from steps 19.b and 19.c. into DYSID and determine the required capacity of the pilot actuated relief valves to hold pressure beloa the reactor high pressure trip set point.
22 P
. To. site the prosstr:izer heaters, perforp the followint; steps:
g
..s l' rom step 13, estimate the pressurizer metal mass and obtain specific heat a,
from the 2A3-II F.anual.
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b.
Datermine the guaranteed heating rate from the Proposal or Contract Inforraation Sheets.
Input pressurizer metal mass and specific heat, normal pressuriner water c.
volume (fron step 8) and estimated pressurizer heater capacity into liYSID and run a heatup transient.
Repeat this run several times using different estimated heater capacities.
Select that heater capacity ths.t gives a heating rate which averages the guaranteed value over the heatup range.
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- 23. Por those contracts with Reactor Coolant Systen loop isolation valves it will be
.a necessary to analyze single loop operation to the method and criteria of this procedure to determine adequacy of sizes for this mode of operation.
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