ML19224C006

Forwards B&W Memo Summarizing Calculations Re Starting Natural Circulation in B Steam Generator.Adequate Head Is Available to Drive B Loop on 95% Range

ML19224C006
Person / Time
Site:	Crane
Issue date:	05/09/1979
From:	Wilson R GENERAL PUBLIC UTILITIES CORP.
To:	Arnold R GENERAL PUBLIC UTILITIES CORP.
References
TSG-157, NUDOCS 7906280160
Download: ML19224C006 (19)

Text

.1 P

}s h Inter-Office Memorandum k\\ /

cme May 9, 1979 v

[r a, Service S uo.ect 3 Steam Generator - 95% Level To R.

C.

Arnold Locanon Three Mile Island Attached is a memo from B&W summarizing calculations with regard to starting natural circulation in the B loop.

These calculations are based on an assumed level of 98% and an average increase in 0

core temperature of 25 if natural circulation should be lost in the A loop.

The results of the calculations indicate an available pressure drive to start natu al circulation in B approximately five times (for the given assumptions) the current loop A pressure drop.

At the minimum 95% level, the available pressure drop for starting circulation (B) would be approximately three times the current (A) steam generator steaming mode loop pressure drop.

The observed instability in the reactor B loop, both on May 3 and May 7, can be interpreted as further confirmation of the very low head necessary to start B loop circulation.

In summary, more than adequate head will be available to drive the B loop on the 95%

range; steaming of the B loop is a preferred fallback position since it involves minimum operator action - involves a mode of operation already tested on the plant - and will not result in un-necessary contamination.

This mode of operation is called for in

.e current Emergency Procedures approved for operation.

/

Y

\\

& !\\) Q R. 'i. Wilson RFW/al ATT cc:

B.

Rusche E1T=I2nM&seimMDRTtf J.

Herbein J.

Moore B.

Elam M.

Morrel)

L.

Pletke - B&W 258 ODB 790323ofga p

}

o GPU Service Corporaton is a stbsic.ary of General Pubhc Unhtes Corporabon

i MAY 3 1979 3n 9

Babcock &Wilcox Power Generatan Group P.O. Box 1260. Lynchburg, Va. 24505 Telechene: (804)3S4-5111 May 3,

1979

..id O(N 5 4D GEK/003 4

@TGWmnWP gm C7M GPU Service Corporation oS N

b Post Office Box 480 g

Middletown, PA 17057 SW

Subject:

Transition to Natural Circulation

Dear Mr. Wilson:

Attached for your review and information is a report entitl'ed

" Transition to Natural Circulation at TMI-2".

This analysis was prepared during the week of 30 April to better understand the plant conditions during single loop natural circulation and to establish a basis for future decisions with regard to natural circulation.

The following information is contained in the report:

1.

A-loop temperature, pressure and #1owrate during natural circulation c o n d t. t i o n s.

2.

B-loop temperature, and pressure during carrent stagnant loop conditions.

3.

B-loop temperature and pressure conditions to initiate natural circulat' ion while steaming.

4.

Projected RCS flow and temperature conditions during the next four month period under single loop natural circulation.

5.

OTSG-B natural circulation conditions for possible transition to solid water operation.

The report is intended to document the results of our discussions during the past several weeks on the subject of natural cir-culation.

If we can be of further assistance, please advise.

Very truly yours, cc:

J.

Phinney

'F}

O G.

Skillman G.

E.

Kulynyc5 C.

Pletke Program Manager, TMI-: Recovery Program R.

Keaton B.

Karrasch J.

Kelly The Babcock & Wilcox Company / Established 1867

'.)

TRANSITION TO NATURAL CIRCULATION AT TML-2

~

~

An analysis has been performed to define tl.e temperature and flowrate of the

. ~

Reactor Coolant System in its mode of single loop natural circulation.

This unalysis has been used to confirm that the current mode of operation is the most desirable for the following reasons:

Single loop natural circulation provides the highest core and loop A T 1)

This improves the overall stability of the system and reduces the core level at which possible instabilities may occur.

decay heat 2)

Removing core decay heat, steaming on one OTSG, requires minimua feedwater flowrate and minimum feedwat.r flow control by the operator.

3) The time to recover from a loss of main feedwater is much greater than in a solid water mode of operation.

4)

Single loop operation provides a backup OTSG which can be utilized if primary system heat removal with the operating OTSG is lost.

Figure 1 illustrates the present condition of the A-Loop and Reactor Vessel with thc A-0TSG steaming at 95% on the operate range and the B-0TSG isolated.

The calculation shows a temperature and pressure distribution around the A-Loop resulting in a 0.035 psi pressure gain from elevation differences.

Figure 2 shows the results of a calculation of loop flow vs loop dP.

At a OP of.035 psi, the loop flowrate is calculated to be 490,000 lbm/hr. The 490,000 lbm/hr is further confir ed with a simple heat balance across the vessel as.

[

follows:

6

2. 0 MW (.?.4 x 10 )

BTU

'00,000 lb (14 BTU ) -

~

br MW hr

~

~

i C.~~

lb r

6.8 x 10D BTU 7.0 x 106 BTU m

$ ~ ~ ~[.

~.[

hr ' + -

~

hr

' ^1 Therefore, the single loop natural' circulation flowrate on 5/1/79 for a 2.0 MW g',

s' m

=

,w core is approximately 500,000 lbm/hr at a A T = 140 F,_.,...:

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An analysis war also perfoiaed to define the temperature distribution of the '

isolated B-I. cop OTSG and determine the sequence of events for transition to B-Loop natural circulation if the A-Loop cooling is lost.

....>.,-C..

.-1 This analysis shows that the following sequence of events will establish.. -

natural r.irculation on the isolated OTSG:

1)

If the A-Loop hot leg temperature increases by 50 F, fully open the B-0TSG turbine bypass valves (OTSG-B operate range level should be at 95 - 100::. )

2) The B-0TSG will slowly begin steam.ag and cooling in the upper part of the unit, thereby establishing natural circulation in the B-Loop.

- ~,.

The calculations confirm that the sequence of events will re-establish natural circulation in the B-Loop.

Figure 3 shows the B-Loop temperature and pressure distribution in its current stagnant condition.

Hot and cold leg RTD readings and OTSG shell thermocouples were used to establish the s

temperature and pressure distribution confirming a r.tagnant condition. ~

,. v.

Figure 4 illustrates the predicted B-Loop temperature and pressure distribution *

~~'

after the turbine bypass valves,are opened in the sequence of events. The figure

~.

shows that a positive A P will be developed (.175paf)due to the cooling in the - -

1_7 center of the OTSG from ' steaming, and the heatup of the reactor vessel due to the loss of natural circulation flow.

If, during the B-0TSG steaming

~

process, the A and/or B hot leg temperatures increase an additional 50 F,

f eed OTSG-B through the auxiliary f eedwater nozzles at-approximately 300 GPM,.

to increase the level five feet... '

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s e

c.

e

. -The turbine. bypass valves should be left ' f, T'- -

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2 Figure 5 defines the additional positive driving force that would be established if feeding on the auxiliary nozzles were necessary.

The calculations show that 0.186 psi driving head would be established versus the 0.175 psi for the a

~

steam:

se:

Bqth values are more than adequate to initiate natural circulation.

It is desirable to initiate natural circulation without the use of auxiliary feedwater (i.e., use steaming only).

If auxiliary feedwater is added, operate range level will go beycad 100% and level indication will be lost.

Also, the

' operator must take positive action to initiate and control the flow rate.

Feeding on the auxiliary nozzlee will initiate natural circulation several hours sooner than merely steaming, however, the driving heads are both large enough

(.175 vs.186 psi) to substantiate the reco=mendation' to steam only.

~

The method used to establish natural circulation in the B-Loop (i.e., steaming ~ '

and/or feeding with aux feedwater) should utilize an initial steam generator level high on the operating range (95% - 100%).

This assures that the primary liquid in the tubes is hot and can be cooled to yield the required pressure drop.

Figure 6 is a plot of predicted

-Loop flow and AT versus the core decay. heat

~.

level.

At the current ore decay heat level of 2.0 W, the A-Loop flow rate is_-

approximately 490,000 lb/hr and the,AT is 14*F (179 - 165 F). As the core decay heat level drops to 1 W, the loop flow will reduce to approximately 320,000 lb/hr and the AT to ll*F.

In our opinion,..atural circulation will remain in.a stable,"_'

well defined' situation down to at ~1 east 0.f W, at which time loop flow will equal',

- m '.g.,

-., - >-. 3,.,-5,..,.

4 200,000 lb/hr and. loop oT will be approximately 5*F.

An analysis will'be '[;"

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t.

~.'^n; performed to verify the minii::um dec,ay heat value for natural circulation cooling..;.' c:,

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j B&*J recommends that the turbine bypass valves be throttled to maintain the cold leg temperature at 160*F or greater as the core decay heat level begins to drop further.

Figure 7 is a plot of OTSG outlet pressure versus the decay heat load being removed to the condenser, with the turbine bypass valves fully open. As,

of May 1, 1979, the heat load bei.'s; removed by the A-0TSG is about 1.(MWwith a pressure of.o psia.

As the heat load drops with time, the pressure will drop consistent with the curve.

On June 15, 1979, the pressure will drop to 2.8 psia which will reduce the reactor coolant temperature to 143*F.

To keep the te=perature above 160*F, the turbine bypass valves cust be throttled.

Natural circulation on the A-Loop will continue to at least 0.5 MW unless cooling of the OTSG is lost by one of the fol1 % ng possible events:

1.

Isolate A-0TSG on secondary side 2.

Loss of feedwater to A-0TSG 3.

Closing of ccudenser dumps from A-0TSG 4.

Loss of condenser vacuum (loss of air ejectors', loss of circulation water), rupture of a condenser ube 4

5.

Loss of A-0TSG, inventory (no level) c m

~

An analysis has also been completed to evaluate the feasibility of bringing OTSG-B

,r into a solid water secondary cooling mode bhile steaming on the A-0TSG.

This s-calculation shows th'at ~the B-0TSG can be slowly filled with 100*F feedwater (10 - 20 gpm) without greatly disturbing the A-Loop natural circulation.

B-Loop

~

natural circulation will begin with a very low reactor coolant system flow rate.,.

~

and re=ove up to 20% of the core decay heat. _After the steam' generator and'

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secondary system have b.een filled with water,.the secondary flow rate can be _

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increased slowly in increments of 100 gpm and the RCS conditions can be monitored:,i.'.,;.:'

-nw.,.

. ;., - q

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..y-e to determine B-Loop natural ' circulation..

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At a secondary side flow rate of 1000 gpm, B steam generator is calculated to remove 2.0 MW of decay heat with a primary side _a T = 16 At 500 gpm on the B

• SG secondary, the 2.0 MW will be removed with a primary

-~

loop AT = 18 If it is decioed to establish the B-I. cop for core cocling, it is reco:maended that feedwater flow rate be slowly increased to at least 500 gpa and possibly 1000 gpm to fully establish B-Loop heat removal.

When the flow rate reaches to 300 gpe, it is calculaced that the A steam generator temperature will drop

~

O to 15 0and the steam flow will b egin to decrease.

dA& n Prepared by s

Reviewed by

/-

4 d-M r

//

Approved by

"._ W -

Attached:

1.

Calculation for cooldown of primary water by steaming "B" OTSG s.

....~.e.

~..

m#

2.

Calculation for addition of cold feedwa'ter to start'nitural circulation

.d 3.

Calculation for "B" OTSG fill rate for going solid'on secondary side of "B" while steaming "A" OTSC 4

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=

ATTACID'ENT 1 CAI CULATION FOR COOLDOWN OF PRIMARY WATER BY STEAMING "B" OTSG 1.

The temperature profile of the water in the "B" OTSG is assumed to go from T

(180 F) at the water level down to 120 F at 80% on the operating range.

HOT B

Below this level, it is assumed to be constant at 120 F.

nm 390 Figure 1 E

380 c

H 370 v

H S

360

>o 4

350 uo 340 un3 330 o

w 320 m

120 140 160 180 S/G Water Temperature 2.

At 3.7 feet below the S/G water level, the static pressure due to the weight of the water (1.7 psia) will prevent boiling of 1200F water.

Therefore, all the heat transfer is assumed to occur above this level.

This means that the lowest primary temperature possible is:

n Figure 2 390 E

C 380 H

v 370 g

o>

360 o

3 350

,a 340 3

330 a

s M

320 110 120 130 Primary Temperature PosEible- -

Lowest

~

O A

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t

'3_,y. ;-_

^~

~s r

6 A

a T

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3.

The maximum 4T available is approximated by:

Primary average temperature from 382" to 337" (Figure 1) =

180 + 130 '

= 155 F 2

Secondary average saturation temperature from 382" to 337" (Figure 2) =

120 + 110

=15F 2

haximum AT available = 155 F - 115 F = 40 F

~

The calculation used to determine the driving heat resulting from this 4T (Figure 4 of this report) used a 30 F temperature difference.

This 10 F accounts for the fact that it will take an infinite amount of time to reach 40 F 4T.

4.

Heat available to bcil secondary side water:

A.

Tube 0.D. =.625" Tube I.D. =.555" Number of Tubes = 15,500 3

Tube Density = 500 lbm/ft w

7.

2.

From A = 7 (O.D. - I.D.) x 15,500 Total tube area = 7 ft Tube volume = 7ft /ft. of length TUBE "

• [

""8

~

C

=.11 Btu /lbm F p

e TUBE P TUBE B.

Primary Side Water Mass (mi

)

1 W

l 3

x 61.54 lb/ft

= Tube I.D. x 7 x 15,500 x 144 e

pWater

= 1602 lba/ft r.

j,}_

Where 61.54 = Density of Primary Water,

, *, '}

_ (\\ [g,.b* ~q^;.

'1 Assume C

=1 p

g

.ea O g*

s

. _...... O '

_A-

- h w.

4 *-

'i

1602 Btu / F ft. of Icngth er" C

=

p WATdR C.

Secondary Side Water Mass (" SEC Secondary volume in this range of OTSG is 42 gal / inch 3

l' in~

1 ft 3

7.48 gal. x 61.398 lbm/ft

~

m

= 42 gal / in x x

SEC ft.

SEC = 4137 lbm/ft of length Where 61.398 = Density of Secondary Water At 140 F,' Pressure = Atmospheric Assume C

=1 P

1. C

= 4137 Btu / F ft of length WATER D.

OTSG Shell M = 10,215 lbm/ft. of length C =.11 Stu/lbm F P

MC

= 1123 Btu / F.

ft. of length E.

Overall OTSG C PTOTAL

'W C

=MC

+MC

+ AB C.

+ h'1 C -

P P

P P

P TOTAL TUBES PRIMARY SECONDARY SHELL

j-,

WATER' WATER MY7 C

= 7632 Btu / F ft. of length

~

~

PTOTAL

,W. _, 7

- ~

.s7;g _.

~-

S

~

~

^. _ ;_

. _ ' -. _ A.

t.,l :.

y

F.

Available heat (Q)

Q=

C AT P

~

(30"F)

~

Q = 7632 Btu / F ft. of length x 3.7 ft. of lengt.h x 5

Q = 8.47 x 10 Btu 5.

Decrease in OTSC Water Level 5

Q = 8.47 x 10 Btu H

= 1008 Stu/lba g

Converting available heat into boiling water on secondary side, Decrease in OTSC level =

5 1

1 7.48 cal.

1 in.

8.47 x 10 Btu x x

3 x

x 308 Btu /lbm 61.39 lbm/ft 3

42 gal.

ft 2.4j Decrease in OTSG tvel =-

w 5,

'~

258 025

-- - a - a. -. ---..

ATTACINENT 2 CALCULATION FOR ADDITION OF COLD FEED'.ATER TO OTSG TO START NATURAL CIRCULATION Assume:

(1) Feedwater temperature is 100 F.

(2) Five feet of level addition.

3 (3) Tube volume primary side = 263 f t /ft.

(4) Secondary side volume inside shroud = 43 ft /ft.

(5) Primary water temperature = 180 F.

A 1 ding five feet of water through auxiliary noz::les will cool down the 1.

5 primary va 3r through conduction to:

T (mPRI) + T (m1SEC) 180(7994) + 100(13,370)

S T

=

MIX m

21,364 MIX TMIX "

2.

Assume primary temperature only goes to 140 F.

This 10 F accounts for g

the fact that it will take an infinite amsunt of time to reach 130 F.

3.

Assuming initial water level is 98% on operating range, the available driving head for natural circulation would be.188 psi (see Figure 5 of this relort).

h

==

258 026 2

~

O e

6$#^A

^

^ - -

g

ATTAC:0!ENT 3 "B" OTSG FILL RATE FOR GCING SOLID ON SECONDARY SIDE OF "B" WHILE STEAMING "A" OTSG Obj ect ive :

Fill "B" OTSG at a rate that will not exceed 20% of the heat load now on "A" OTSG.

s Assu e:

(1) Feedwater temperature is 100 F.

(2) After natural circulation starts in "B" OTSC, the feedwater I!OT (

}*

will exit at T (3) "A" OTSG current heat load is 1.3 MW.

Q = 1.3 MW = 1.3 x 3.413 Btu /MWHr x 10 6

= 4.44 x 10 Btu /hr 5

Allowablei}3 =.2 h = 8.87 x 10 Btu /hr A

Q = ~3 pc gT = q(1)(180 - 100) 3 N = 1.1 x 10 lbm/hr x x 7.48 gal /ft x 1 H' U

B 62 lba 60 min.

22 GPM Where 62 lbm/ft = Density of 100 F water at 14.7 psia Fill Rate

=

~

~

+.

=

~

25.8 027 m.m

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