ML19308D690

Reactor Bldg Spray Pumps:Npsh Calculations

ML19308D690
Person / Time
Site:	Crystal River
Issue date:	06/06/1972
From:	Vaughn R GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT
To:
Shared Package
ML19308D691	List: ML19308D690 ML19308D692 ML19308D694
References
14374, NUDOCS 8003120821
Download: ML19308D690 (45)

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NET POSITIVE SUCTION HEAD 3

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CALCUIATIONS

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R. E. VAUGai JUNE 6, 1972 O

8 0 08120 hh/-

Nuclear Department Gilbert' Associates, Inc.

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NET POSITIVE SUCTION HEAD CALCULATIONS O

A.

' INTRODUCTION:

This paper was preps id in onier to properly evaluate the " Net Positive Suction Head Available" (NPSH ) relative to the " Net Positive Suction a

Head Required" (NPSE ) f the Reactor Building Spray Pumps.

r The subject paper consists of the following:

a.

Summy of input assumptions used i,

b.

'Brief evaluation of AEC Safety Guide No. 1 dated. November 2, 1970 and the DRL's proposed revision to Safety Guide No. 1 dated February 29, 1972, Minim = calculated post loss-of-coolant-accident (LOCA) water level c.

within the Reactor Building.

p,'

d.

Calculations to determine maxi =u= friction losses in the suction piping from the Reactor Building Sump to the Reactor Building Spray Pumps RBSP-3A and RBSP-3B.

Results and sumnary of the Net Positive Suction Head Calculations e.

B.

_SU!SfARY OF INPUT ASSINGTIONS:

The NPSH to the reactor building spray pumps during post *.IOCA recirculation a

Phase has been based on " Issued for Construction" piping drawings and the following assumptions:

Pipe and fitting friction losses calculated using Crane Technical a.

L Pager No. 410 b.

Total required flow in a single string (i.e., consisting of one decay heat removal pump and one reactor buil_ ding spray pump which have a l - (J3 common suction line from the reactor building sump) is 4500 gpm, 3000 gpm to the reactor buildtng spray pump.

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Sump W;t:r temperature cqual to 226' F (pesk valva from Figure 14-61 c.

h FSAR) d.

Using DRL's proposed revision to Safety Guide I[o.1 formula for calculating NPSH a

3 NPSK

=P

- P, +

H a

e g-Hf where:

Pe = reactor building pressure = Pa 4 ?v Pa = air pardal pressure P = vapor (steam) partial pressure y

P, = saturation pressure corresporMng to the temperature of water being pumped H, = elevation pressure due to the height of water above the pump inlet nozzle H

f = pressure loss due to friction in the suction' line Water level in the reactor building is at 99.83 ft. This water level e.

in the reactor building is derived from calctilations in which the

~

minimum water capable of flooding the reactor building and all dis-placements of water such as components, sumps, tunnels, etc., have been analyzed. This' water level will be referred to as the post loss-of-coolant accident (LOCA) water level throughout this NPSK review.

The NPSR's available to each' pump, as calculated on the above basis, are compared below v.'th the NPSH required by each pump at the flows indicated bove.

Required NPSE is from curves furnished by the pu=p manufacttirer.

a The required NPSE in feet of H O is an approximate figure, it is expected 2

that the actual pump perfomance of NPSE required will be somewhat less p/

4 as compared to the figures shown below:

G 4

.y,,

,-p

m,-

g Flow Calculated NPSE NPSH 1

Rate Available ft H O Required 2

Pap g

Elevation Head ft Hp0 R.B. Spray Pump A 1500 14.42' 13 00' R.B. Spray P up B 1500 13 18' 13.00' C.

BRIEF EVALUATIOU OF AEC SAFMY GUIDE NO.1 AMD DRL'S PROFOSED REVISION TO SAFEIT GUIDE HO.1 The Safety Guide states that "no increase in containment pressure from that present prior to the postulated loss-of-coolant" may be assumed.

his position can readily be applied when calculating NPSE available with a surg water at a temperature less than 212 F.

This position is 0

unrealistic when the sump water is above 212 F, in that it would mean the entire large inventory of water in the reactor buildin,7 would boil away without increasing the pressure in ' he reactor building. It is t

(".)

more realistic to assume reactor building pressure vill at least achieve equilibrium with the sump water at the se.turation' pressure of the latter.

Any abrupt loss of saturation pressure in the Containment Vessel would resultinflashingofthesumpwaterattemperaturesabove5120 F and immediate equilibrium of the reactor building pressure with the sump water at saturation pressure would be restored.

~

-r DRL's proposed revision to Safety Guide No.1 is realistic, in regards to calculating the NPSHa, in that the increase reactor building pressure, due to e' partial pressure and vapor partial pressure, is considered 1

in..the NPSE fomula.

a f

D.

RESULTS AND SLM!ARY OF THE NET POSITIVE SUCTION HEAD CALCULATIONS i

O 4

,a

-m e

4' s-1 Usingtheinputassumptions(refersection3)andcalcuh.atingthefollowing:

( '1 a.

Total volume displaced by mmponents within the Reactor En41d4ng.

b.

Total water available and capable of flooding Reactor, Building floor at elevation 95'-o".

c.

qpantity of water held-up in the primary shield with water at the Reactor Vessel nozzle elevation.

d.

Water held up in fuel transfer canal.

e.

Water held up on floor elevation 119'-o" and elevation 160'-o".

Calculating the weir flow via the openings on these elevations; assuming all floor drains to be obstructed by debris, f.

Total water contained in the atmosphere as vapor.

The results of the Net positive Suction Head review relative to the worst 2

condition with an 8.5 ft break are illustrated on Table I of this calculation O

L-review.

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Minimum Calculated Post Loss-of-Coolant accident (LOCA)WaterLevelWithinthe Reactor Bn41aing O

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V.#

Area Displactd by Compon:ntu Within the P.eactor Building o

Steam Generator Skirt (2) 2 M (5 75)2 _ ;f(5 0)2] =,(25 5)2 = 51.0 51.0 sq ft Primary Shield A ='W(16.5)2 = 855

.855 0 sq ft (3' x 3.75')2 = 126.5 sq ft 126.0 sq ft 1/2 th = [1/2 (4)(2)] 2 = 16.0 sq ft 16.0 sq ft Secondary Shield i

A = (42' x 4') = 168 sq ft

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'I(25')2-T(21')2.577.8sqft (9' x 3') = 27 sq ft 1/2 bh = 1/2 (4')(2') = 4 sq ft

(

(18'x3')=shsqft (30' x 3') = 90 sq ft (8'x3')=24sqft (12' x 3') = 36 sq ft (11' x 3') = 33 sq ft c

(22 5' x 3') = 67 5 sq ft

.(28 5' x 3') = 85 5 sq ft (6' x 3') =, 36.o sq ft (11' x 8') = 88 sq ft Secondary - Total 1)333sq'ft Total 2,481 3 sq ft o

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. Total Tcttr Availtb1h to Flood R.B. Floor at Elevation 95'-o" 3

. (.-)

y x

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= 'fatt3.720 in Reactor Vessel

. +,

N SBo P

-11,396 Ft3=49p5750lbs e

, y7.'jl '.A9J575 0

.Ro(.01680Ft3/lb)@2260 a

F=

ji f[.8 < 4

}4. n. ild,3%fi.r53 cr 226 F E

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..R k.= W w :i

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w!6:

([I hCDJ.Ft.h. 220DF=6173lbs/Ft3 3

w.<,

.t S rh ih73.1ks/Ft3) = 24692 lbs pip 92

(.01680 q,3/lbs)=414Ft3 i

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$N[a hir#,- bl.3f5 M'

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• N,2.ho {M) =f4617.8 lbs

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$}.f,:4 iii.22G'y &$17.B l'.01680) = 1p519 x 2 = 2Ao3 9 F$

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• ii% 4B 90 p,3 g,n 0

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t'iD, Boo @ 62.11 = 415'jl88 lbs

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2* h ($L551ES)(.01680 Ft /lb) = 53,007 Ft3.

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Na2 2 3' Tank 80

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8 150 F = 61.20 1500 Ft3 (61.20) = 97p20 lbs 9 2260F 97p20 lbs (.01680) = 1645 Ft.3 i

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NaOH Tank 8 150oF = 61.20 (2poo) 61.20 = 9 800 lbs 8 2260F'= 93/00 lbs (.o1680) = 1p42 5 Pt3 Total Pt3 = 67,o'81 Ft3'

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Total Volume of Water Available - Capable

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of Flooding R.B. Floor @ Elevation 95'-o" 1.

Total Water Volume in Reactor System (2 Loops) @ 643 F 11,396 Ft3 i

0 2260F 8,376 Ft 2.

Makeup Tank 9 226 F 414 Ft3 3

Borated Water storage Tank 8 226 F 53,000 Ft3 4.

NaOH Tank @ 226 F 1,542 Ft3 5

Na2 2 3 Ta d 0 226 F 1,@5 Ft3 30 6.

Core Flood Tanks (2) @ 2260F 2,104 Ft3

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67,081 Ft3 O

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- 10 0 The Following Components Will Lower

(..s.)

the Height of H O in the Reactor Building 2

1.

Instrumentation Tunnel V = 10 x 30 x 1 300 Ft3 2.

m4 w ng Sump Volume Y = 10' x lo' x 9' goo Pt3 3

1200 Ft l

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TotalgoAvailablo Total H O in R nctor Vessel 2

e 5800F = 11,396 Ft3 'Y =.0223 A 226 F, Y =.01680 11,396 (*01

-) = 8,585 Ft3

.0223 Makeup Tank 400 Ft.3 a 1200F ; Y =. 01620 a 226 F Y =.01680 400 Ft3(_.01680)=4.14.8'Ft 3

core Floor Tank (2) e1k0FY=.01629 e 226 F Y =.C 20 3 ( 01680) = 1951 9 x 2

[*",

1020 Ft 0229 P,103.8 Ft3 G

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@ 90 F = Y =.01610 8 226 F = Y =.01680 50.800 Ft3 (.01680) = 53,008 Ft3

.01010 Na 8 0 Tank 223

@ 150 F Y =.01634 0

e 2260F.Y =.01680 3[>00Ft3 (.01MO), 3f,45 pg3

.01634 NaOH Tank

@ 1500F = Y =,01634

@ 226 F = Y =.01680 3p00(h680)=1p42.2Ft3

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Quantity of Water Held-up Insh.de Primary Shield:

"1.

Cylindrical Volume V1 ='TI r2 h (3.14)(11 5)2 (21.75) = 9,o32.o 2.

Volume occuppied by cylindrical portion <

. actor Vessel:

h = (3.14)(7.823)2 (15.6') = 2p97.8 V2 ='

r 3

Volume occuppied by bottom head of reactor vessel:

V3=(1/2)(4/3)'TIr3 = (0.67)(3.14)(7.69)3 = 957 2 e

4. Volume occuppied by support skirt =

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V4 ='If DAVE tk = (3.14)(14.8)(0.67) = 37.2 5

Volume occupied by Base Ring:

Y5" 1 ~ "2 ) t2 (3.14)(8.062 - 6.73 )(0.25) = 15.5-2 7..

, y 15 5

65. - 45 3 19 7 e

9 e

s e

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=

- -.g.

V:1ume below Elsvation 104'-O"

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Cylindrical Volume 2

2 Vy = 7f *r.h = (314)(6 )(11) = J,244.1 Area Available = 5p32.0 hj)o7 5 ~

Area occupied

=

Volume Filled with H O 5024.5 2

3,244.1 6p68.6cu.fb.

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W2tsr h:1d-up in Funi Transfer Canal.

~-

• en we';er level in the primary shield.

is at the Reactor Vessel Nozzles:

Water Elevation at the reactor vessel nozzle = 125 75' Bottom of Fuel Transfer Canal Elevation

= 118.23' Height of water in Fuel Transfer Canal 7.42'

=

Area of Fuel' Transfer Canal = (17 5')(23.6') = 413 sq.ft.

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Volume of F.T.C.

= 3p64.5 cu.ft.

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Nat 119'-o'# Area to conect spray water Anet = 8097 5-1 i

Rate at which water falls 'on Anet:

R = (j'0 g )(3poo gpm) = 1804.8 gpm A

3 OF g

M.8 gpm 4,o n3/see g

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(60sec/ min)(75 gal /ft3) s 3'

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Approximate Area of Floor at Elevation 119'-o" u

A Triangle = 1/2 bh 1.

1/2 (37)(22) =

407.o

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,2.

1/2(37)(27)"=

499 5 3.

1/2 (37)(17) =

314 5

4. 1/2 (26)(14) =

182.o

~

5. 1/2(40)(10)=

200.0 6.

1/2 (40)(3)

=

60.o.

7 1/2 (38)(31) =

589 0 8.

1/2(13)(23)='

149J5

'9.

1/2 (18)(8)

=

72.0

10. 1/2 (50)(5)

=

125.0

11. 1/2(30)(11)=.

165 0

12. 1/2 (16)(6)

=

48.0

13. 1/2 (22)(8). =

88.0

14. 40 x 46

=

@o.o 15 23 x 17

=

391.0

16. 12 x 8

.=

96.0 t

17. 17 x 8

=

136.0 Total Area = 8p97 5 ft2 9

e s

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e

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M.

e Approximata Area cf Flool Tt Eltvetion 160'-0" r' r U

1.

Area of Grida a

a)

(9 5)(19) 180 5 ft

=

1 2

b)

(13)(1+.5)(2) =

377 0 ft a

Total = 557 5 ft2 Area of Elevation 119'-0" = 8p97 5 Area of Grids @ 160'-O" 557 5

.=

Is o'.o's 2

Area of Floor at ElevationA7,5140 5 ft e

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W;ir Flow via Openinga on Elsvation 119'-o" a

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Length of Horizontal Weir - 19' + 9' 1/4 " + 9' 1/4" +

3'+3"=43'-2-1/2"=432' 4 = 3 33 (L - 0.2H) H 3/2 Si.nce L is >> 0.2H Fomula reduces to 4 = 3 33 IH3/2 3/2,

,., g H = ( 1 )2/3 8*

H=

3 33L J.33 (43 2 fy H =.0917 ft

.'. H = 0.1 ft Total Area of Floor elevation 119'-0" = C,097.5 ft2 Total Water on 119',-o" = (8p97 5 ft )(0.1 ft) = 809 76 ft3 2

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W;ir Flow via Op;nings en Elsvation 160'-0*

Iength of Horizontal Weir = 14.6 ft 3/2 4 = 3 33 (1 - 0.2H) M 3/2 3/2 4

g = 3 33 LH H

3 33L 6ft/see 12/3 I

- H=(333L)2/3 2

.**g.

_333(1W.6ft[

H = 0.41 ft

,..4 Total Area of F.Loor e'levat5.oif 160'-0" = 7p40 5 ft 2

2 3

TotalVolumeofwateronelevation160'-O"=(}5405ft)(0.41ft)=3092ft e s.,

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Yalume displaced by wedg2 with H O cicvation et 96'-o" 2

c.

a = 5' e

b = 1'-

e =.1 5' tox =,;, 3 taux = ;..A=;.:.x=&

x = (5')(1.5')

= 1.25' 5' + 1' 2

Area triangle

= 1/2 xa = 1/2 (1.25')(5) = 3125 ft 2

Area 6 B = 1/2 e (a.+ b) = 1/2 (15)(5 + 1) = 4.5' ft Cire Rx Bldg. = 'IId = 3 14 (131') = 412 ft Total volume displacedbywedge:

e Area d B - Area A A = 4 5' - 3 125' = 1 375 ft Volume displaced by wedge:

s 1 375 ft3 3

x 412 tb - 566.5 ft 1l

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V:1wne displaced by wedg2 with H O elevati:n O 97"-0~'

2 l

G"V b = 2' c = 15' l

tan oc = d ; tanoc = {. *.,

c,g,.

z.,

/

x. (4')(1.5') = 1.0 4' + 2'

. Area A A = 1/2 xa = 1/2 (1.0)(4) = 2 ft2 2

Area A B =.4 5 it Cire Rr Bldg = 4.2 ft Total volume displaced by wedge:

Area A B - Area A A = 4.5 ft2 2

2

- 2 ft = 2 5 ft Volume displaced by vedge:

2 2 5 ft x 412 ft = 1030 ft3

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Volume displac d by wedg7 with H O at olevation 98'-0" 2

_a=3 k:)

.,b = 3 e=15 C

C x

ac tance g ; tanx = X..,,, = g.. x =,,

x = (3 + 33)(1.5') " *75 #D Area A A = 1/2 xa = 1/2 (.75')(3) = 1.125 fte 2

Area A B = 4.5 ft Cire Rx Bld. = 412 ft 6

Total volume displaced by wedge:

2 Area A B - Area A A = 4.5 ft - 1.125 ft2 = 3 375 ft2 Volume displaced by wedge:

2 3 375 ft x 412 ft = 1390 5 ft3

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V:1ume displaced by vsdga with go ct oisvation 99'-0,"

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=

Aread A = 1/2 xa = 1/2 (.5)(2) = 1. ft2 Area A B = 4.5 ft*

Cire Rx Bldg. = 412 Ft Total volume displaced by wedge:

A A B - Area a A = 4.5 ft - 1.0 ft2 = 3 5 ft2 Volume displaced by wedge:

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Volume diep10c d by wedge with go clavation at 100'-0"

('.)

a = 1' b = 5' c = 15'

?

ta= = a ;im =;.. & = ;.. x = ;;,

x = (l')(1.5')

.25 ft

=

l' + 3' 2

Area A A = 1/2 xa = 1/2 (.25')(1) =.125 ft 2

Area a 3 = 4.5 ft Circ Rx Bld. 412 ft 6

Total volume displaced by wedge:

2 e

Area 4 3 - Area A A = 4.5 ft

.125 ft2 = 4.375 ft Total volume displaced by wedge:

,~

t' '

4.375 ftE = 412 ft = 1802 5 ft" S

3 e

G e

4

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'.'ll

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e Volume displtced by wedge with go Elsv. at 101'-O'*

1

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-v Total Volume displaced by wedge:

4.5 fte x 412 ft = 1854 ft3 e

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c 32 2 Total water held-up

k.,

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'1 Primary Shield 6268.6 ft3

2. ' Floor Slab at El.evation H9'-0" & 160'-0" 1118.95 ft 3

3 Spray in atmosphere 401.10 ft3

4. Fuel Transfer Canal 3064.5 ft3 5

Primary System Filled at 2260F 28n et3 6.

Instrumentation Tunnel 300 ft3 3

7.

Reactor wilding Sump 900 ft 3

Total 14,863+ ft

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a Approximat3 Re:ct r Build 4ng Su:np W;ttr Entrain::d in th2 Atmo:phora as V;por Reactor Building Su=p Water temperature = 226'F Containment Free Volume = 2 x 106 3

3 b

vg 9 226'F =

20.794ft/lb Weight density of H O 8 226'F = 59 5 lbs/tt3 2

2 x 106 ft3

= 9.64 x 10N lba %0 20.794 ft3/lb 9.64 x 104 lbs

= 1618 ft3 3

595lbs/ft Total H O Hr..Ld-up = 14,864 + 1618 ft = 16,482 2

4 S

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General Equatient

( )

TOTAL WATER DISPIACDENT cf[(130')2 (67,081 ft3 3

- 16.482 ft ) + 2,481 ft3 2

h T[(130')2h = 50,599 ft3 + 2,481 ft2

~

13,266.5 ft h = 50,599 ft3 + 2,48i rt2 h = 50,599 ft3 10,785 5 ft2 h = 4.69 At floor Elevation 95'-0" + 4.69' = 99.69 ft o

At 99.69 ft the volume or water displaced by the wedge is

tanc.={.*.34= f.*.x=

tanoc = a o

• " _(1.31)(1.5)

.L.31 + 4.69

.\\

x =.33

_s AreahA=1/2xf=1/2(.33x131)

~

E Area A A'=.22 ft Area & B = 4 5 ft2 Cire Rx Building - 412 ft

~

Area A B = Area 6 A - 4.28 4.28 ft3 x 412 ft2 = 1763.4 ft3 e

N_

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g

.s General Equation

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3 f(g2 (5o,599 ft3 + 1763.4 ft ) + 2481 rte

~'~

2 2 2 13,266 5 ft h 52363.4 ft3 + 2481 ft2 2

h = 52363.4 ft3 e 10,785 5 ft h = 4.85 ft Floor elevation 9s'-o" + 4.85 = 99.85' O

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b NPSH to RSP 1A & 1B At th3 Recirculation Ph z o a

- '..,s; NPSH = Pe - Ps +

H2-Hf a

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Pe = 4.5 psig (figure 14-60,' FSAR).= 19 196 psia (2 307) = M.30' s

4 P, 9 215 F = 15 592 psia (2 307) = 35 97 H2 = H O Elevation = 99.85'. - centerline Pump elevation 77 33' = 2P-52" 2

E RSP-M = 8.10' f

Hf RSP-1B = 9 34' NPSKa RSP-M = W.30' - 35 97' + 22 52' - 8.10' = 22.75' NPSE RSP-1B = W.30' - 35 97' + 22 52' - 9 34' = 21 51' a

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NPSH,to RSP-1A & 1B ct 104 condo c

Q NPSE2=P - P, +

H2-

'E>

e Pe = 5 Psis (figure 14-60.3AR) = 19 696 psia (2 307) = 45.W '

Ps = 19 274 psia (2 307) = W.47 2 = H O Elevation e 99.0 ' - centerline Pump elevation = 7733'=22.52' H

2 5

Hf RSP-1A = 8.10' H RSP-1B = 9 34' f

NPSEa (RSP-M) = 45.W' - W.47' + 22 53' - 8.10' = 15.'39' NPSHa (RSP-1B) = 45.W' - W.47' + 22 52' - 9 34' = 14.15' 9

l O

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= P -Pg+

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Assume - P P

=

c a

NPSH

=

H2 --

Hf a

(RSP-1A)NPSHa= 22 52' - 3.10' = 14.42' (RSP-1B)NPSH = 22 52' - 9 34' = 13 18' a

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TABLE I-Available NPSH vs Required NPSE with Total H O Available 2

~

(All'componentsemptyexceptthereactorvessel)

/

Based on BSP-3A & 3n operating at 1500 gpm_

Total Elevation Potential Elev.

Head Available Total Head Required Head Available on this Bases to Pumps - Ft 1.

From post IOCA water elevation to centerline of BSR-3A Pump 8.10' Hd. Loss Suction 99.85' to 77 33' 22.52' Elev. Hd 13 00' NPSH Req'd.

22 5R' 21.10' 2

From post IDCA water elevation to centerline of B3P-3B Pump 9 34' Hd. Loss Suction 99.85' to 7/.33' 22 52' Elev. Hd 13 00' NPSH Req'd/,

22 52' 22 34

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O Calculated Head Losses in Suction Piping of Reactor Building Spray Pumps RSP-1A & IB t

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Ngy =ber 2, 1970 M

s.

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SAFETY CUIDP.1 - NET 70SITIVE SUCTION HE!? MR

~

EMERGE!!CY C07.E COLING AND CONT /sI WE! r.H?>.T REMOV/.L SYST r

Introduction A..

Proposed General Ilecign Criterion 41 requires that the emergency coolids and'contain=ent heat renoval systems be capable of accooplishing

' their required ~ safety functions assuming pcrtial loss of installed,

capacity.

In current designs the ability to acco:plish these safety functiona reliably depends in part on the proper performance of syntes pumps wh'ich, in turn, depends on the conditions under which the One of these conditienn in auction pr' essure. This

' pumpa nust operate.

c

'. '. guide dcocribes a suitabic relctionship between iner, canes in containe.cnt

.s s.

idents and 'the n,et

. pressure ccused by pootulated loss of coolant acc s.

b

" positive auction head '(NPSH) of cmergency core' cooling an'd containcent I

heae removal oyatem pu=ps which may be used to implement Ccue'ral 1

~

.~

Design Criterion 41.

~~-

Discusdion_

..r.

.. 3

-A significant consideration related to energency core coolins and containnent heat removal systems is the potential for degraded pump

'perforutuce which could be caused by a number of factors, includ'ing If the NPSH availnbic to a pu=p in not sufficient, inadequate NPSH.

cavitation of the pu= ped fluid can occur.' This cavitation?'n'ay~ reduce significantly the capability of the system to accomplish its safety,

t y, i.

functio.ns.

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.It is importent that the proper perfor'nsnee of caergency core

.s cooling and c7ntainment heat removal systems be independent of d by postulated

. calculated increases in containment pressure cause loss of coolant accidents in order to" assure reliable opc'rntion.under

~

For exanp1'e, if proper.

a vari'ety of poss21e accident conditions.

operation of the energency core cooling system dependa upon caintaining the containnent pressure above a specified ninin:um e=ount, then. too lov an internal pressure (resulting from i.mpaired contcinm2nt integrity or operation of' the contain= ant hest rc ovd1 cystet$s at too hi a

ge) could significantly affect the chility of this cyctem to accomplis In addition, the its safety functions by causing pump envitatioti.

. deliberate continudtion of a high cont 51,nment' pressure to maintain an

.gf ~

~

ade'quate pu=p NPSTI vould result in greater lenkcge. o'f fission producta i

from the contait=.cnt and higher potential offsite doses under' accident

~

~~

~

. conditionc than would othen.ise result..

~

\\

'.. ~.

Changes in NPS11 for.e=ergency core cooling aiid contaitEent heat removal system pumps caused by increases in tempera'ture of the pu= ped

• fluid under loss, of :oolant accident conditions can be accommodated i.vithoui: reliance ori the calcula'ted increase in contalement pressure.

Adequate KPSH can be assured by locating pu=ps at suitable clevations

'with respect to the storage volumes connected to their. auction sides, by using ruitistage or booster pu=ps, by a'cochination of these cathods, 2

~

or by other techniques.'

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'.to system pu:sps ecsteing exinus expected tc=peratures of put: ped fluids' and no increase in containment pressure fron 'that present S

prior to postulc.ted loss of coolant; cecidents.

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I pl p

u.

a, g

~

1.3 g

g fit" /5.*fff)MM6VWOJ Km po+ sagas =usw o.

O.

8 Q.r e

.s../Ycr_.t.GUU_..? 1 - m.r.r.o..n1Tn7. E_tcr1_0.:7 ItrN) r3.P (N::cy tri:3 c:ni.V::c 1.!io cc:ct.Trs..r li.m icc:c'!/i, sysnni rtno.'s s

e-

{-

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i

-c In b d i

r>

P G_..r.e_t cy_

A.

I g#ror.ed I::ucre.1 Det.it.n Critorion 41 requirca tisat the emergency.

i h

Ni.in. id.3 c.cntz.irmnt heat removt,1 syr,te :o be cap.bic of acconpliching A<

+ +..

rcrinired safety functions cccuming pr.rts.cl losc of innta11cd -

g:sspngi(y.

7.n curront denigns the t.bility to accomplish these cafety

.x m

t c

h. %sc*/dou%.4s relitibly depends in part on the proper perfor:inn j

,44

?

3

. ( f.,

9 f; /stm ycp}n chich, in turn, depends en the conditiene u 1

Q e,

. r qq.

c One of these conditions to nuction prc: cure. Thio

.t 9.< i d p operate.

- 5, j

I M. #4 f.jQcribe.2 a. nuitdic relatien-) hip bet.vcen inercacca in ebnt.niuvent s).

t t

. r

~

a M

.m.recrurn,ccused by postulated loss of coolant accidents cnd the uct 9.

,4

.)

e 2pfsitiv=* svetion he.:d (!TS10 of energency core cooling cad contni:omt

.Q i-j.

i...

j j.b et xx=d.vn1 cyctea puaps which c:ny be used to' impic:::ent Genera' j'

~

l

-l I

i I-g"{I-b x

~

7

.O=s$gn Dritcrion 41..

j

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N.

i i

t I p.

\\$ :.

it i.'t t

i i

I B..41=:cere:;f.t:n j.

i i.

ir i

(,Q.

I

{.

r A sis:1Eic..at ecasiderdtion related to cuargency core cooling and 3

10

.l i

%contain

f$cnt heat rcesval cyste.e is the potential for degraded puup

-a 1 c..

i

. -1 e

. including -

.tyeriormnce which could be caused by a number of factors, ! :.

I i

.. d..

If the llPSit i.vailable to a ptesp ic not c'uf[ficient, j

.e e

'.4=^=$j$t.c!.?cIl.

f, l

. i :!

M c-l es.cavW1.Gn of the pu ped fluid can. occur.

This cavitation, uny reduce

,a

.g *4 1

- a.

c s

a j

iqcnatly the espability of the systers to acco:aplish its, safety h.

[

s h

l!

i, f

9.-

4.

b i

n.

wG i;

,i i

{Gj.,.hi.-

r

- -.a.

l d,.

a S f g f i

• y;

. tf L.,

,.g\\

yp q

j/

ti

-. 7,.,.

I f* f.

f

i r

P s

ls

,I 1

1 t-9 s

../

f 8

? :l i

.?

e:'.....

l f.

l Q-

-.- ji l l

i

1. v f:

iY It is,important that the proper performance of the emergency coro 1

]

coolinh 'and containc.ca Imar EcIn' oval systems be conservatively s

s.sectrifah. -d to assure their, rcilable operation under a variety of

)

f.

~

[)

possib, e, loss of coolant accident conditions.

Therefore, the various l

ij I

I parameters uhich' determine the NPSH availabic to the pumps in these

]

,i pl 1

i q

l safety systems must be conservatively preditted. These parameters are.

i reactor building pressure = P.' + P P

=

l" yl l

s air' partial pressure P

=

j i

j i

l P,= vapor (steam) partial pressure V.

,1 i

l tl s a

L SP saturation pressure corresponding to the temperature of the

=

i s,

o t

l t

E.

3 water being pumped j

I

.Q All,= cleyntion pressure due to the height of water above the pump

/ v

-1 inlet nozzle i

i 3..

~

ou = pressure loss due to friction in the suction line f

l

~

WN' p

g.

The NPSU availabic to a pu:np is:

[ [\\"

f.

3 E

NPSHa?P

-P

+ AH - AH j

I i

l,. e.

z f

,12 a s

~

".51s v'alue must be equal to or greater than the'NSPS. required by 3

the pump under all potential operating conditions:

NPSH.> NPSH

~

a, a-r Therefore, the above para:ieters and relatiornhips should be conservative 3y

]

predicted versus time following a postulated loss of coolant accident

[

to! assure that the performance of;each sa.ftty system pump is not

-\\

.l

. i.

degraded because of cavitation.

Because of inherent uncertaintics

. r' O in' the, predict. ion of the numerical valves of these parametcrs and I

l L

it I

2 e

l.

.n-

r-f:

~

h thnir rqlaticn:; hip to cns nnuthe at c given time, a r.cargin, fcr w

v safety should be'incitided. in the'i calculations.

p l

.i j l

The deliberate continuation of containment pressurization to maintain s

i.

h an ade,qu' ate pump NPSH vould resuit in greater leakage of fission 2

N

(

,l products from the containment and higher potential offsite doses under 'ar.lcident conditions than would otherwise result and therefore, 4

i'

.l i

L l

,pj I

N g

this should not be a planned operating condition.. Rather, adequate g

p I

l NPSH sho'uld be assured by specifying pumps with low NPS1! requirements 4

4 li l 1

t e

locating punps at lov elevations with respect to the water to be

j I!I I

1 j

pumped,. :using multistage or booster pumps, by a combination of these g

methods,l or by other design techniques.

I 1

g i

1 C.

Regulato'ry Position

~

1.

hergency core cooling and containnent h' eat remov'al systems should t-4 be. d.esigned so that adequate net po,sitive suction head. (NPSH) is

.s s

l

}--

1 I

pr'oEide'd to system pumps following postulated loss of coolant b

con fW/e Nfc.

a, y

f accidents for the-morrtedverse. combination of the parameters that giir k.~ffii.a,% A:w J.4m G' le % sk. :4/ A seArt A ** } p de termine tne avalTaoIc~lifSilN5El'16e ra tipie ss'u'di::a't icitI ~of lhe '

]

' tbtrhts p.h:E4w I

l j

.re' actor building should not be consideredhas a "means of increasing

..the available NPSH.

The minimum availabic NPSR calculated.

i should be greater than the required NPS11 for the pumps by t.he.

d W!iylv E trcst}/ N'.w fle.

t 6.)st.te/e, b.

f lJp4 larger-of-c ttitu!rf&:,i s M be.

Artd j

a j

.awr-eeecre-oM.O psi

} b., 2-Nessure-corrusyattding-*to a subeboling of the-pumped fluid -.

1 hMwn yl.

co ru ' '

3-l h,

]

i l[

e 5

j 1

y: -

e -. s s I

p),-

?. - ;.

2.

I'rstvialcos ufinutd b2 tutdcr I.or monitorJng 'the perfonnance ci the

' '(,)

epfety, system pumps following a. loss of coolant accident.

A means

~

should'be availabic to ensure ade'quate pump performance at all h,. i I

times to?mect the minimum objectives of t'.e safety systems.

l ll l ll -

l

(

8 i.

l I

i I

l l

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ll J

i

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g i

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i.

t

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i 6

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l-i l

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i i

t.

i I

e l

s i

i 1

I i

i 8

I t

i 6

I t

e.

=!

ll j

h I:

i I

l

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.i e

i

i..,. i i

I

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)*

~

-- l

.l i

.i

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i g

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s L

't j

.]

3

l. -

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I.

.f I

i g g a

f t

3-

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c g

l t.

(

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w

!.h,. p r :t 3

'N

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}

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=

, s.

References:

,8

(): *d 9

1.

FSAR Crystal River Unit No. 3 FPC (Section 14;. figures 14-60 and 14-61) 2.

Crane Technical Paper No. 410 3.,

CRC Handbook of Chemistry and Physics h.

Issued for Construction' drawings 5

Safety Guide No. 1 6.

Proposed Revision to Safety Guide No.1 9

e 9

9 3

k I

l

)

DEMg

1. 4 G'r

.