ML17331A927

Provides Update to 930611 Initial Response to NRC Bulletin 93-002.Analysis Confirming That Subj Roughing Filters Will Remain Confined within Kidney Fans in Event of LOCA Inside Containment Encl

ML17331A927
Person / Time
Site:	Cook
Issue date:	08/06/1993
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AEP:NRC:1188A, IEB-93-002, IEB-93-2, NUDOCS 9308110256
Download: ML17331A927 (46)

Text

ACCELERANT 0 DOCUMENT DlSTR BU'r.'j.ox SX~"j.'j.'Xi REGULA INFORMATION DISTRIBUTIO YSTEM (RIDS)

ACCESSION NBR:9308110256 DOC.DATE: 93/08/06 NOTARIZED: NO DOCKET ¹ FACIL:50-315 Donald C.

Cook Nuclear Power Plant, Unit 1, Indiana M

05000315 50-316 Donald C.

Cook Nuclear Power Plant, Unit 2, Indiana M

05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.

Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY Document Control Branch (Document Control Desk)

I

SUBJECT:

Provides update to 930611 initial response to NRC Bulletin 93-002.Analysis confirming that subj roughing filters will remain confined within kidney fans in event of LOCA inside containment encl.

DISTRIBUTION CODE:

IE11D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Bulletin Response (50 DKT)

NOTES:

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FILE 01 EXTERNAL: NRC PDR COPIES LTTR ENCL 1

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1 1

1 RECIPIENT ID CODE/NAME DEAN,W NRR/DE/EMEB NRR/DRSS/PEPB NRR/DSSA/SRXB NRR/SCSB RES/DSIR/EIB NSIC COPIES LTTR ENCL 1

1 1

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1 D

A, D

i NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

D TOTAL NUMBER OF COPIES REQUIRED:

LTTR 15 ENCL 15

Inmana Michigan Power Company P.O. Box 16631 Coiumbus, OH 43216 Z'NDIANA NICHI64N IaOMfER Donald C.

Cook Nuclear Plant Units 1 and 2

Docket Nos.

50-315 and 50-316 License Nos.

DPR-58 and DPR-74 BULLETIN NO. 93-02'EBRIS PLUGGING OF EMERGENCY CORE COOLING SUCTION STRAINERS AEP:NRC:1188A S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC'0555 August 6, 1993

Dear Dr. Murley:

The purpose of this letter is to provide an update to our initial response to NRC Bulletin 93-02 dated June 11, 1993.

The initial response noted that additional time was required to investigate the capability of ventilation units in the containments of Cook Nuclear Plant to contain fibrous filters following a

Loss of Coolant Accident (LOCA).

Specifically, the Containment Auxiliary Cleanup Ventilation Units (kidney fans) located in the basement of the lower compartment of Cook Nuclear Plant containments needed to be analyzed.

As stated in the original letter, these were the only sources of the fibrous material addressed in the bulletin that posed a concern for blocking the containment recirculation sump.

An analysis has been completed that confirms that the subj ect roughing filters will remain confined within the kidney fans in the event of a LOCA inside containment.

As requested by your staff, a

copy of the analysis is included as an attachment to this letter.

This analysis utilized the leak before break philosophy, developed by Westinghouse as part of the resolution of unresolved safety issue USI-A2.

Leak before break is applicable to Cook Nuclear Plant via amendment no.

76 to Unit 2 and an NRC SER dated November 22, 1985.

loooaI As indicated in our original response letter referenced

above, the filters discussed

'have been found to be unnecessary for the functionality of the ventilation units.

Current plans are to ensure the roughing filters are removed from Unit 1

during the next refueling outage scheduled to begin February 1994.

If Unit 1 is forced into an unplanned outage of sufficient duration prior to this

date, every effort will be made to ensure the removal of the roughing filters sooner.

We verified by inspection that there were no roughing filters in Unit 2 during the forced outage which began August 2, 1993.

9308ii0256 930806 PDR ADQCK 050003i5 8

PDR

Dr. T. E. Murley AEP:NRC:1188A This letter is submitted pursuant to 10 CFR 50. 54(f)

and, as

such, an oath statement is attached.

Sincerely, r'~gpss)

E.

E. Fitzpatrick Vice President eh Attachment CC:

A. A. Blind - Bridgman J.

R. Padgett G. Charnoff NFEM Section Chief J.

B. Martin - Region III NRC Resident Inspector

- Bridgman

COUNTY OF FRANKLIN E.

E. Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the forgoing response to Bulletin 93-02:

Debris Plugging of Emergency Core Cooling Suction Strainers and knows the contents thereof; and that said contents are true to the best of his knowledge and belief.

Subscribed and sworn to before me this ~4 day of 199~8 OTARY UBLIC plIh 0 )il'iL NOTS aiY F'UCUC. STQE OF OHIO

ATTACHMENT TO AEP:NRC:1188A ANALYSIS OF A LOCA ON THE VENTILATIONUNITS

ATTACHMENT TO AEP:NR 88A Page 1

ANERlCAN ELECTRIC PWKR Dato July 29, 1993 sub)oct Effeet of Loss of Coolant Accident. on Ventilation Units Housing Fibrous Materials prom T. J. Crawford xo S.

A. Hover~

Responding to your memo of June 11,

1993, we have analyzed the effects of a LOCA on the ventilation units.

The maximum differential pressure across the ventilation units was calculated to be less than 0.1 psi.

The break of the accumulator line feeding the cold leg was used as the LOCA. Because of the

'Leak-before-break'riteria the double-ended cold-leg break or cross-under leg break were not considered as the LOCA scenario.

Direct impingement or dynamic effects were not included since the accumulator line enters the cold leg near elevation 615 and the number 2 steam generator and its four support columns are between the break location and the ventilation unit.

Attached for your information and record retention is a copy of the calculation. If you need additional information please do not hesitate to contact me at 1284.

cc: S.J.

E.ED G.R.

M.K.

Brewer / J.B. Kingseed / S.A. Hover Fitzpatrick Burris Jr.

Guha / C.D. Olsen / File N930601 w

attachment w/o II w/o It w/o If Intra-Syatom

ATTACHMENT TO AEP:N 188A Page 2

May 1980 Jan

1984, Rev 1

Dec 1988, Rev 2

Calculation Cover Sheet Technical Assessment Section Job No.: N930601

Title:

Effect of Loss of Coolant Accident on Ventilation Units Housin Fibrous Materials or Filters System:Emer enc Core Coolin Plant:

D.C.

Cook File No.:

Unit:

1 6

2 Design Basis:~NA By:

T. J. Crawford Review: C.

P. Lin Approval:M. K. Guha Date:~726 93 ethod: 4 ~

~

C.< > 4 8.4 Date: 7 >

3 Date:~7~

VJ Table of Contents Pacae 1.

Problem 2.

Conclusion 3

Procedure 4.

Assumption(s) 5.

Content(s) a.

Compartment Energy b.

Initial Compartment Masses c.

Flow Rates Between Compartments d.

New Compartment Masses e.

New Thermodynamic State of Superheated Compartments f.

New Thermodynamic State of Saturated Compartments g.

Heat Transfer to Containment Walls h.

Heat Transfer Within Containment Walls 10 10 12 6.

Reference(s) 7.

Attachment(s).

13 15

ATTACHMENT TO AEP:N 188A Page 3

TECHNICAL ASSESSMENT CALCULATION VERIFICATION CHECKLIST Page 0 of 'SQ Reviewer:

Q~

Section lleneger:

J~tt-~+

Date:

Review of the calculation shall include evaluation against the following questions:

YES NO Basis for Determination 1.

Was an appropriate method used?

2.

Are the results reason-able compared to the input?

~rM f CJ l< l-~SOS.

3.

Are the results numerically correct?

4.

Are the equations used correct and the reference documented?

5.

Were the correct inputs used and their sources documented?

c prP~ 5 6.

Are the assumptions reasonable and properly documented (including appro-priate references and adequate justi-fication)?

7.

Is the calculation acceptable?

P<sM

>< ~ ~oVg-

ATTACHMENT TO AEP:N 1188A I ~V Page 4

EFFECT OF L.O.C.A.

ON VENTILATIONUNITS 1.

PROBLEM In a memo of June ll, 1993(Ref; 1), Mr. S.

A. Hover of Nuclear Operations requested Technical Assessment to analyze the effects of the accumulator leg break LOCA blowdown forces on the Containment, Auxiliary Cleanup (Ventilation)

Unit located in the basement of lower containment at the D.C. Cook Plant.

The purpose of the analysis is to determine the differential pressure that may be exerted on the ventilation unit during a LOCA, and would be used by Structural Engineering to determine the ability of units to contain fibrous filter materials.

I The analysis would be in response to NRC bulletin 93-02 and would be used to support continued operation until the next refueling outage.

ATTACHMENT TO AEP:

188A

~

<</ 5Q 2.

CONCLUSION The maximum differential pressure across the cleanup or ventilation units was calculated to be less than 0.1 psi.

The break of the accumulator line feeding the cold leg was used as the LOCA.

Because of the 'Leak-before-break'riteria the double-ended cold-leg break or cross-under leg-break were not considered as the LOCA scenario.

Direct, impingement or dynamic effects were not included since the accumulator line enters the cold leg near elevation 615 and the number 2 steam generator and its four support columns are between the break location and the ventilation unit(Refs; 8

& 20).

The unit sits on elevation 598 and is about 10 feet high, bringing the top of the unit to elevation 608.

The pressure and temperature were calculated for the various containment compartments.

The initial'ressure, temperature, and relative humidity were 14.7 psia, 90.0 F, and 100% respectively.

The initial temperature of the ice condenser was 27.0 F.

The computer program written for this analysis(LOCA01) was checked for reasonableness by using it to analyze the double-ended cold leg break with the appropriate initial pressure and temperatures, and comparing it with the Westinghouse TMD results and the MPR Associates results displayed on p IV-19 of Ref. 5.

The results are tabulated below.

Peak Sub-Compartment Pressure(psia)

LOCA01 MPR TMD Peak Deck Differential Pressure(psi)

LOCAOl MPR TMD 29.0 26.0 23.9 8.4 8.3 8.6 The LOCA01 program calculates a slightly more conservative pressure and differential pressure.

The relatively close agreement of LOCAOl with TMD and MPR provides additional confidence in the results of the present analysis of the ventilation unit.

ATTACHMENT TO AEP:N 1188A

/'g o page 6

3.

PROCEDURE A. Obtain the dimensions of the air filtering unit(Ref. 2), the distances between the unit and the crane wall, the unit and the biological shield, the unit and the ceiling, and the two elevations.

Calculate flow area for steam/water mixture around the air unit.

B. Obtain the diameter of the accumulator line and the maximum blowdown flow rate from it(Fig. 2-3, Ref.

3).

Use a realistic value of temperature for cold leg water to calculate the density and quality of the steam-water mixture that would be released.

C. Obtain necessary. input data.

Much of this was taken from Refs.

4, 5, 6, 7, 8.

This included the dimensions of the containment building, sub-compartment

volumes, flow areas between compartments, wall surface areas and thicknesses, and mass and area of metal in the compartments.

D. Divide the containment building into twelve sub-compartments or regions.

The lower compartment was divided into six regions.

The two fan-accumulator rooms, the reactor cavity, and the instrument room were four more regions.

The ice condenser and the upper compartment were two more regions.

E. Divide the containment walls into slabs or nodes of increasing thickness from the surface to the interior.

F. Write a computer program to calculate the thermodynamic states and properties in each compartment, and the flow of air and steam among compartments.

This was done by incorporating some of the techniques used in t:he MARCH program(Ref.

9).

G.

Make the necessary calculations and tabulate the results.

ATTACHMENT TO AEP:N 188A 4.

ASSUMPTIONS

~

(

~

J~

Page~

7 7/7.qf> >

A. The containment building may be accurately represented as a lower compartment divided into six regions separated by a steam generator or the filtering unit, the dead ended regions and reactor cavity, the ice condenser and the upper compartment, for a total of twelve regions.

B. The pressure and temperature were uniform throughout each compartment.

The air and steam or water vapor formed a homogeneous mixture.

C ~ The flow rate of air and steam among compartments could be adequately modelled using a form of compressible flow equation(p 3-5, Ref.

10) with an appropriate flow coefficient, flow area opening, specific

volumes, and the pressure difference between the compartments.

This equation includes an acceleration pressure loss as well as form losses.

'The flow coefficients were obtained from Refs.

4 8 5. The flow coefficient for the passage formed by the filtering unit was calculated using Ref.

12, p335-335.

As was done in Ref.

6, the flow calculated for each time step was limited somewhat by a restriction factor to eliminate the excessive changes in compartment mass in each time step, and the resulting large pressure oscillations that would be observed without it.

Ref.

6 calculated the number of moles of air and vapor that must be transferred to bring the pressure of two adjacent compartments to an equilibrium pressure.

The number of moles to transfer was calculated for the largest flow passage area for a compartment; flow through smaller areas was then based on flow through this largest area.

The present calculation used a very small time step(0.0001 sec) to utilize a simple restriction factor (/1.4),

and avoid calculating moles transferred and flows based on large and small volumes and flow areas.

D. Flow of liquid or water between adjacent compartment floors was also calculated using a weir flow type equation with the difference in water depth.

This method was also used in Ref.

16.

E.

The air was treated as an ideal gas.

The value of constant pressure specific heat was assumed constant at 0.240 Btu/ibm/F. The value of constant volume specific heat was also assumed constant and was calculated using Cv = Cp R/778.16 The internal energy of air was a function of temperature only.

F. The steam/water vapor was also treated as an ideal gas when calculating the number of moles in a compartment or its average molecular weight.

Steam properties were taken from Ref.

11.

G. The containment walls were semi-infinite slabs, and heat transfer only occurred perpendicular to the thickness.

The walls were insulated on the outside surface.

They could absorb heat from the air/vapor mixture, but could not loose heat to the outside.

ATTACHMENT TO AEP:N 188A

/

Page 8

~)'~/e a H. The floor between the upper and lower compartments was treated as a

wall insulated at the center line." Each room could access half the wall thickness.

The walls separating the lower compartment from the dead-ended region was treated the same.

The walls between the upper compartment and the ice condenser were neglected.

J.

The metal equipment in the lower and upper compartments was also modelled as a slab, and heat flow and temperature were calculated similarly to the concrete walls.

K. The temperature of containment air was initially 90 F, the pressure was 14.7 psia, and the relative humidity was 100%.

L. The temperature of the containment walls was initially 90 F.

M. All ice condenser lower plenum inlet doors and outlet intermediate deck doors were assumed to be open.

N. The ice condenser baskets and ice were treated as a wall with heat transfer being calculated as in. item F.

The heat transferred from the steam/air mixture to the ice was calculated at each time step.

The corresponding amount of ice melt was then calculated.

O. Emissivity of the gas mixture to the walls was 0.3 P.

No credit was allowed for the containment spray system.

OTHER INPUTS/DATA The compartment volumes, wall surface

areas, thicknesses, physical properties, etc.

were taken from Refs 6 and 7.

The wall surface areas were re-apportioned for the new volumes based on the amount of perimeter or arc covered by the volume(Ref. 8).

These are listed in the computer output.

The containment walls are described in the Attachments.

Only a portion of the floor surface area between the upper compartment and the lower compartment was considered.

The inside diameter of the accumulator line was 8.75 inches(Ref.

19) and the maximum blowdown flow rate from it was taken as 24400 lb/sec/ft**2 (Fig. 2-3, Ref. 3).

This value corresponds to the mass flux at 2250 psia and 540 F, the conditions of cold-leg saturated liquid. It was kept constant for the entire transient to assure a very conservative flow rate.

For comparing the LOCA01 program against the Westinghouse TMD results(Ref.

4) and the MPR Associates results(Ref.

5), the cold leg diameter used was 31 inches, the blowdown flow rate used was 9882.777, and the temperature was 534.6 F.

These values gave the 103,600 lb/hr and 530 btu/ibm inputs respectively of p IV-2, Ref. 5.

ATTACHMENT TO AEP:N 188A P4g

/<9 /g~

The number of ice baskets was 1944; 'their length was 48 feet,; their diameter and pitch were 12 and 14 inches respectively (Ref. 18).

The surface of the walls and other structures within the ice condenser compartment were neglected.

Natural convection and condensation heat transfer coefficients between the walls and the steam/air mixture were calculated using the equations of pp 6-13 to 6-16(Ref.

9)

Radiation heat transfer was also included.

Where steam/air velocities were high enough forced convection heat transfer was included using Ref.

13, p148 for the walls and pl76 for the ice baskets.

Heat transfer through the slab walls was modelled by dividing each wall into adjacent layers of varying thickness, using pp 6-15 and 6-16 (Ref. 9).

The ice condenser was initially at 27 F, and it contains 2,370,000 lbs of ice also at 27 F. Ice properties were from Ref.

14.

ATTACHMENT TO AEP:N 1188A

'/>u Page 10 5.

CONTENTS A.

COMPARTMENT ENERGY..

The total internal energy of each compartment was calculated using the First Law of Thermodynamics for an open system.

The change in energy equals the mass flow of enthalpy in minus the mass flow of enthalpy out minus the heat transferred to the walls.

The new internal energy was calculated in subroutine ENERGY using U2=

mi *hi

me*he

Q

+

Ul Each flow rate in and out was averaged over two time steps using mi =

( mi(2)

+ mi(1)

) / 20 B. INITIALCOMPARTMENT MASSES The initial volume of the ice was calculated using Ref.

14 with,the initial ice mass.

The volume of air and vapor in the ice condenser was provided in Refs.

6 or 7.

The total volume of the ice condenser was calculated by adding the volumes of ice and air.

VTOT(1,7)

= W(1,5)

• VICE where W(1,7)

= Ice mass VICE

= specific volume of ice VTOT( 3 I 7 )

VTOT( 2 g 7 )

+ VTOT( 1 I 7 )

where VTOT(3,7)

VTOT(2,7)

VTOT(1,7) 7 total ice condenser volume air and vapor volume ice volume the ice condenser compartment identification no.

The initial water vapor mass in each compartment, including the ice condenser, was calculated using the steam tables with initial pressure, temperature, relative humidity, and open or void compartment volume.

W(2,NC)

= VTOT(2,NC) / VGT( T(NC)

) *

( RH(NC) / IOO.

)

where VTOT(2,NC)

= open volume VGT(T(NC)') = specific volume of vapor at temperature T(NC)

RH(NC)

= relative humidity

ATTACHMENT TO AEP:N 188A (P%

Page ll 7/~~/g s The initial air mass in each compartment was calculated using the ideal gas law with partial pressure of air, temperature, and open volume.

W(4,NC)

= P(2,NC)

• 144.

• VTOT(2,NC) / R /

( T(NC)

+ 460.

)

where P(2,NC)

= partial pressure of air

= total pressure partial pressure of water vapor R

= ideal gas constant for air C.

FLOW RATES BETWEEN COMPARTMENTS The flow rate of gas or vapor between adjacent compartments was calculated using p 3-5, Ref.

10 F()

=

(

( 2.0

• gc

• 144.

• DP()

• AREA()**2 ) /

( 2.0

• dv()

+ KLS()

• v()

) )**1/2 where DP()

AREA()

KLS()

v()

dv()

pressure difference between compartments flow area flow loss coefficient average specific volume of mixture difference between v() between compartments The amount of air and vapor mass transferred in each time step was calculated using DF()

=

F()

• TS

/ DPDFS where TS

= time step DPDFS

= a flow limiting factor(1.4) for multiple flow paths through each compartment to help avoid pressure oscillations and which helped benchmark the program against the TMD and MPR results.

The flow of'iquid water between adjacent compartments was calculated using a

version of the weir flow equation of p 479, Ref.

15.

F(l,NP,)

= Cflw

• rho

• Width *

( Z(NF(NP))

Z(NT(NP))

) / 12.

whereCflw rho Width Z(NF,)

Z(NT,)

weir flow coeff; taken large to accommodate inertia.

density of water.

a characteristic width between adjacent compartments.

depth of water in 'from'ompartment, larger than Z(NT,)

ATTACHMENT TO AEP:N 1188A

'/'3q

~ d P~s~ >>

7/z(z~

The flow of enthalpy per time step from a compartment was calculated using DH(j,NP)

= DF(j,NP)

• H(j,NC) where H(j,NC) = the enthalpy of fluid type j in compartment NC DF(j,NP)

= mass flow per time step along flow path NP j

= liquid, vapor, and air D.

NEW COMPARTMENT MASSES..

The new masses of liquid, vapor, and air were calculated using the amounts of mass transferred averaged over the last two time steps

using, W(j,NC) = W(j,NC)

+

( DF(j,in, 1)

+ DF(j,in, 2)

) / 2.0

)

( DF(jioutg1)

+ DF(jgoutg2)

) / 2 '

)

where DF()

?in out 1,2 mass flow per time step liquid, vapor, and air flow path into the compartment flow path from the compartment

previous, present time step For gas flow the 'flow from'ompartment was always at a pressure greater than the 'flow into'ompartment.

Pressure in each compartment was checked each time step to identify from and to numbers.

For 1'iquid flow the 'flow from'ompartment had a greater depth of liquid than the 'flow into'ompartment.

ATTACHMENT TO AEP:N 1188A P IV/ Pg Page 13~)~~/>>

E.

NEW THERMODYNAMIC STATE OF SUPERHEATED COMPARTMENTS The new pressure, temperature, etc., of each superheated compartment following the additions or removals of mass and energy was calculated by balancing the total volume with component(vapor and air) volumes, and balancing total energy with component, energy.

This gave two equations(

volume and energy

) and two unknowns( total pressure and temperature

). The system was solved by iteration with a Newton-Raphson technique for non-linear equations,

( pp 37-39, Ref.

17)

The two equations were expressed as the following two functions, Gl(P2,T2)

= VTOT(3,NC)

( Mg*Vg(P9,T2) + Ma*Va(Pa,T2)

) / 2.0 G2(P2,T2)

= U(4,NC)

( Mg*Ug(Pg,T2)

+ Ma*Ua(T2)

)

where VTOT(3,NC)

U(4,NC)

P2,T2 Pg,Pa Mg,Vg,Ug Ma,Va,Ua compartment total volume compartment total energy new total pressure and temperature partial pressure of vapor, air

mass, specific volume, and specific energy of vapor

mass, specific volume, and specific energy of air Additional properties such as specific enthalpy, xelative humidity, etc.

were then calculated using the new P2 and T2.

F.

NEW THERMODYNAMIC STATE OF SATURATED COMPARTMENTS The new pressure, temperature, etc., of each saturated compartment following the additions or removals of mass and energy was calculated by balancing the total energy with component energy.

This gave one equation(

energy

) and one unknown( temperature

). The system was solved by iteration with the bisection technique.(

p 18, Ref.

17)

The energy balance equation was expressed as the following function,

= compartment total energy

= new temperature

= mass of liquid, vapor, and air

= internal energy of liquid, vapor, air Gl(T2) = U(4,NC)

( Mf(T2)*Uf(T2) + Mg(T2)*U9(T2) + Ma*Ua(T2)

)

where U(4,NC)

T2 Mf,Mg,Ma Uf,Ug,Ua Additional properties such as pressure, specific enthalpy, relative humidity, etc.

were then 'calculated using the new T2 and the saturated properties.

ATTACHMENT TO AEP:N 188A G-HEAT TRANSFER TO CONTAINMENT WALLS(SLAB)

Heat transfer to the slab walls by natural convection and condensation was calculated based on the methods of Ref.

9, pp 6-13, 6-15.

A radiation heat transfer coefficient and a forced convection coefficient were also included for this calculation.

A total heat transfer coefficient was calculated by summing the individual heat flows.

qt

=

qc

+

qn

+

qr' qf ht*(Tb Tw)

= hc*(Tsat Tw)

+ hn*(Tb Tw)

+ hr*(Tb Tw) +

hf*( Tb Tw)

Solving for ht gives, ht

=

hc*(Tsat Tw)/(Tb Tw)

+

hn

+

hr

+

hf whereqtqc,qn,qr,qf hthc,hn,hr,hf Tb,Tsat,Tw total heat flux(Btu/hr/ft**2) heat flux due to condensation, natural convection, radiation, and forced convection.

total heat transfer coefficient(Btu/hr/ft**2/F) heat transfer coefficients due to condensation, natural convection, radiation, and forced convection.

bulk and saturation temperatures of gas mixture and wall surface temperature.

Condensation was assumed to occur only if the wall temperature was less than the dew point temperature.

ATTACHMENT TO AEP:N 1188A H.

HEAT TRANSFER WITHIN CONTAINMENT WALLS(SLABS) g

/ t./

v)+!

zg ~~

The walls were divided into adjacent slabs or nodes of increasing thickness as per Ref. 9.

The heat transfer coefficient for conduction heat transfer between adjacent slabs was calculated using ht(n)

= k /

( x(n) x(n-1)

)

where ht(n)

= total heat transfer coefficient(Btu/hr/ft**2/F) node n

x(n)

= location or coordinate of node n

k:

= thermal conductivity of concrete(Btu/hr/ft/F)

The conduction heat transfer entering node n from node (n-1) on the left) was calculated using, qw(n')

= ht(n)

( Tw(n-1)

Tw(n)

)

And the conduction heat transfer leaving node n to node (n+1).on the right) was calculated using, qw(n+1)

= ht(n+1) *

( Tw(n)

Tw(n+1)

)

The temperature change of the first node was calculated using a heat balance:

DTw(l) =

(

QWavg qw(2)

)*TS /

( rho

• dx(l)

• Cp

)

where QWavg qw(2)

TS rho,Cp dx(1)

( qt(TS=1)

+ qt(TS=2)

) / 2.0 time averaged heat flux entering surface of node l.

conduction heat flux leaving node 1 to node 2

time step size density and heat capacity of concrete or steel.

thickness of control volume, node 1

The temperature changes of the other nodes was calculated in a similar manner using:

DTw(n)

=

( qw(n) qw(n+1)

)*TS /

( rho

• dx(n)

• Cp

)

where qw(n)

= heat flux leaving node n-1 and entering node n

qw(n+1)

II II n

II II n+1 dx(n)

= thickness of control volume, node n

ATTACHMENT TO AEP:N 188A 6.

REFERENCES 76~))q 1 ~

Memo of May 27,

1993, from S.A. Hover to T.J. Crawford, titled 'Effect of Fibrous Material on Recirculation Pump Screen'.

2 ~

3.

Drawing No.

107C-890301-H, from American Air Filter Co., Inc.,

Louisville, Ky., 1972.

Larson, J.R.,

System Analysis Handbook, NUREG/CR-4041, EGG-2354, Revision 1,

November, 1985.

4.

5.

6.

Updated F.S.A.R. for D.C. Cook Plant, Tables 14.3.4-15, 14.3.4-16, and Figure 14.3.4-18 MPR Associates, Inc., Ice Condenser Containment Independent Analysis Program Final Report, MPR-340, April, 1972.

Technical Assessment Section calculation N-921001, Containment Building Pressure and Temperature in Event of DHR Failure While in Mid-Loop Operation,

January, 1993.

7

~

8.

9.

Containment Data Collection Notebook, D.C.

Cook Nuclear Plant I.P.E.,

prepared by Fauske 6 Associates, Inc., January, 1992.

A.E.P. drawings 12-3181-14, 1-5688-10, and 1-5699-10.

NUREG/CR-3988, BMI-2115, MARCH 2 Code Description and Users Manual.

10.

Steam, Its Generation and Use.,

40th ed.,

Babcock 6 Wilcox Company, Barberton,

Ohio, 1992.

A.S.M.E. Steam Tables, Thermodynamic and Transport Properties of Steam, 2nd ed.,

1967.

12.

13.

Idelchik, I.E., and Fried, E., Flow Resistance:

A Design Guide for Engineers.,

Hemisphere Publishing Co.,

New York, 1989.

Holman, J.P.,

Heat Transfer, 3rd. ed. McGraw-Hill Book Co.,

New York, 1972.

14. Perry, R.H.,

and Chilton, C.H., Chemical Engineer's

Handbook, 5th ed.,

Table 3-275.

15. Streeter, V.L., Fluid Mechanics, 5th ed., McGraw-Hill Book Co.,

New York, 1971.

16. Technical Assessment Section calculation N-920101, Fire Protection Water Storage Tanks for Unit 1

6 Unit 2 at D.C. Cook Plant,

January, 1992.

ATTACHMENT TO AEP:N 188A

17. Grove, W.E., Brief Numerical Methods., Prentice-Hall, Inc 1966.

18. Various written communications between Nuclear Safety Section and Technical Assessment(Attached).

19. Verbal communications between S.A. Hover of Nuclear Operations and T.J. Crawford of Technical Assessment.

20.

Tubeco Inc., drawing 1-51-31, isometric pipe drawing.

ATTACHMENT TO AEP:N 188A Page 18 J>pf~

7.

ATTACHMENTS A.

Sketch of Containment with Compartments and Flow Paths B.

Descriptions of Compartment Volumes and Containment Walls or Slabs C.

Flow Diagram of Computer Program LOCA01.

D.

Selected References.

E.

Program Listing of LOCA01.

F.

Program outputs for; accumulator leg break(d=8.75),

run time = 0.1112 sec cold leg break(d=31.),

run time = 0.2752 sec

ATTACHMENT TO AEP:N 188A

"'"(w~

Page 19 l jg o

REACTOR COOLANT SYSTEM COMPARTMENT AREA

,NO.

3 DOOR ICE CONDENSER

~ )

<c

)

~

STEAM GENERATOR 2'og r')

~

~

C l3 AREA 2 DOOR

~t

/

~ ~

A v

V1

') e$

,i C

h

~

~ ~

'V C'

l 3

~ a ARE.

NO. 4 D

~ ~~ ~

~ H

)

0+ ~

'v~r-

~ ~ )

~ (

r

% ~

~l-l

\\

ui

C ~

i~

r OR r ~

~

~,

~ (y )

AREA NO. I DO REACTOR COOLANT SYSTEM RUPTURE

~

k

~ s ~

l,5

~..a..~.

~

~I r C

~

FLOV/'UCT UNDERNEATH REFUELLING CANAL ~

AREA jl NO.

5 DOOR

>(). ~7zs'e J

+(z. 2Y'vr la i3 -.'/0 <>~

V<q=2y u~ v V yP

>5. X"Q~

PLANT DESIGN - PLAN VIE%V SECTION OF REACTOR CCO3 ANT SYSTEM.i COhiPARTi.fENT

~O

.7

) Qv ryg

ATTACHMENT TO AEP:N 188A 0

fg

)

00 l IP/g~

f'age 20

~Jz.~gg~

ee 0,

F1N COMPARTMENT /

'(. 6 I

r

'v 1CC UPPER COKP ARTIST g5 61TK 33 (0

1CC Qr I

IS,Q I

I C

.G.i Qr 1CC Jg~ o

/p

< 8 FiN CDllPMWKNT

~/

O 0

g. -

~

ATTACHMENT TO AEP'NRC'1188A Page 21

= 9~~$

SG

) Rgb~

..-vg 27<$ 0 i=7) ltu'0

~

i

~ M

~

7 lq 0 = )~"

7

~ /v h= ) ~'t IC3 0

MS A=)o 9o o'4

/i""

SG 3 QiC.

)VSY9b P ~Zgo3

)ro>g =

) Z4 1~>~

7 R

D4 IC4

>7'r$3 ~

w n )(

Jj A-)) 3 Ir ti: i-r SG DUCT R

5 I C5 4=72.

2,Z 4'o,i 0~ )5c.

REACTOR CONTAINMENTSUBVOLUMES AND F'LOW PATHS

ATTACHMENT TO AEP:

1188A COMPARTMENT NUMBERS AND VOLUMES(Refs.

4 a

5

)

< /pp Page 22

~ ~/~~

No.

Description Break region in Lower Compartment between Refueling Canal and Steam Generator No.

2 (S/G 2)

Volume between S/G 2 and Ventilation Unit.

Volume (ft**3) 27 250.

19 000.

Volume between Ventilation Unit and S/G 3

Volume between S/G 3 and S/G 4

Volume between S/G 4 and S/G 1

Volume between S/G 1 and Refueling Canal 19 000.

90 000.

38 000.

22 500.

Ice Condenser(void volume)

Upper Compartment Dead Ended Region Housing Accumulators 2 and 3

126 940.

745 896.

27 450.

10 Dead Ended Region Instrument Room Dead Ended Region Housing Accumulators 1 and 4

17 111.

27 450.

12 Reactor Cavity 19 731.

ATTACHMENT TO AEP:N 188A Page 23 z/z ~g>

DESCRIPTION OF CONTAINMENT WALLS OR HEAT SINK SLABS(Refs.

4 5: 5)

No.

Description Surface Area (ft**2)

Thickness (ft)

Removes Heat From Cmpt 1

Between Cmpts 1 a'nd 9

2 Between Cmpts 2 and 9

3 Between Cmpts 3 and 9

\\

4 Between Cmpts 4 and 9

5 Between Cmpts 4 and 10 6

Between Cmpts 4

7 Between Cmpts 7

and ll I

and 7

8 Between Cmpts 5 and ll 9

Between Cmpts 6 and ll 10 Between Cmpts 9 and 1

11 Between Cmpts 9 and 2

12 Between Cmpts 9 and 3

13 Between Cmpts 9 and 4

14 Between Cmpts 10 and 5

15 Between Cmpts 11 and 4

16 Between Cmpts ll and 5

17 Between Cmpts 11 and 6

18 Interior of Cmpt 1

19 Interior of Cmpt 2

20 Interior of Cmpt 3

21 Interior of Cmpt 4

22 Interior of Cmpt 5

23 Interior of Cmpt 6

24 Floor of Cmpt 1

25 Floor of Cmpt 2

1 392.

915.

1 006.

1 336.

3 165.

1 301.

293 148.

1 878.

1 288.

1 392.

915.

1 006.

1 336.

3 165.

1 301.

1 878.

1 288.

508.

244.

269.

1 549.

501.

447.

539.

259.

3.0/2 3.0/2 3.0/2 3.0/2 3.0/2 3.0/2 N/A 3.0/2 3.0/2 3.0/2 J

3.0/2 3.0/2 3.0/2 3.0/2 3.0/2 3.0/2 3.0/2 2.25 2.25 2.25 2.25 2.25 2.25 5.00 5.00 10

ATTACHMENT TO AEP:N 188A Page 24 26, Floor of Cmpt 3

27 Floor of Cmpt 4

28 Floor of Cmpt 5

29 Floor of Cmpt 6

30 Between Cmpts 1 and 8

31 Between Cmpts 2 and 8

285.

1 641.

531.

474.

2 511.

1 301.

32 Between Cmpts 3

33 Between Cmpts 4

I and 8

and 8

1 327.

7 654.

34 Between Cmpts 5 and 8

2 477.

35 Between Cmpts 6 and 8

2 208.

36 Between Cmpts 8 and 1

2 511.

37 Between Cmpts 8 and 2

1 301.

't 38 Between Cmpts 8 and 3

1 327.

39 Between Cmpts 8 and 4

7 654.

40 Between Cmpts 8 and 5

2 477.

41 Between Cmpts 8 and 6

2 208.

42 Between Cmpt 8 and Outside 24 567.

43 Between Cmpt 9 and Outside 4 829.

44 Between Cmpt 10 and Outside 3 288.

45 Between Cmpt ll and Outside 4 640.

5.00 5.00 5.00 F 00 2.875/2 2.875/2 2.875/2 2.875/2 2.875/2 2.875/2 2.875/2 2.875/2 2.875/2 2.875/2 2.875/2 2.875/2 3.5 3.5 3 '

3.5 10 46 Metal in Cmpt 1

47 Metal in Cmpt 2

48 Metal in Cmpt 3

49 Metal in Cmpt 4

50 Metal in Cmpt 5

51 Metal in Cmpt 6

52 Metal in Cmpt 8

9 479

~

4 556.

5 009.

28 889.

9 349.

8 334.

38 435.

0.134 0.134 0.134 0.134 0.134 0.134 0.012

ATTACHMENT TO AEP:N 188A c/p Page 25 7/re/~ ~

DESCRIPTION OF FLOW PATHS/AREAS BETWEEN COMPARTMENTS(REFS.

4

& 5)

No.

Description Flow Area (ft**2)

Loss Coeff 1

From Cmpt 1 to 2

2 From Cmpt 2 to 3

3 From Cmpt 3 to 9

4 From Cmpt 3 to 4

5 From'Cmpt 6

From Cmpt 4 to 5

6 to 5

7 From Cmpt, 1 to 6

8 From Cmpt 2 to 9

9 From Cmpt 9 to 10 10 From Cmpt ll to 10 ll From Cmpt 5 to ll 12 From Cmpt 4 to 12 13 From Cmpt 1 to 7

14 From Cmpt 2 to 7

15 From Cmpt 3 to 7

16 From Cmpt 4 to 7

17 From Cmpt 5 to 7

18 From Cmpt 6 to 7

19 From Cmpt 7 to 8,

20 From Break Line to 1

635.0 1 079.0 77.0 585.0 585.0 635.0 72.0 77.0 10.0 10.0 154.0 144.0 122.0 72.0

'2.0 487.0 155.0 155.0 2 003.0 0.4 0.300 0.170 4.200 0.340 0.340 0.300 1.450 4.200 3.000 3.000 4.200 1.500 0.890 0.890 0.890 0.890 0.890 0.890 1.430 N/A

ATTACHMENT TO AEP:N 1188A Walls and Related Compartments; file=LOCA01 Areas are from HALFLP02

& N.O.D. note book

'>(3" Page 26 Walls 1:

8 between L.C. and D.E.

ALC:= 12280.

iRC~

~

~

~

g q

6(

g Arco:= 32.1 +21.1 +23.2 +30.8 '+73.0 +30.0 +43.3 +29.7

/

ci I

/Q

/1 1I Arco = 283.2 32.1 A:=

'LC Arco 21.1 A:=

'LC Arco 23 '

A:=

'LC Arco 30.8 A:=

ALC 4 'rco 43.3 A:=

ALC Arco 73.0 A:=

'LC Arco 29.7 A:=

ALC Arco 30.0 A:=

'LC Arco Wall 7 is Ice Baskets in Program LOCAOI A9

'.=

293148.

g(( ~

- g Walls 10:

17 between D.E.

and L.C.

j2:=

10.. 17 (j2 - 9)

J>lt M=

Q I 9 Q

~Q

)1 I )

)g Walls 18:

23 are Xnterior of L.C.

>I(.~

=

I z.

Arci:= 43.9 +21.1 +23.2 +133.8 +43.3 +38.6 A18:=

3517.

43.9 A:=

'18 18 'rci 21.1 A:=

~ A18 Arci 23 '

A:=

'A18 Arci 133.8 A21

'AIS Arci 43.3 A:=

A18 22 'rci 38.6 A:=.'18 Arci

ATTACHMEMT TO AEP:N 188A Walls 24:

29 are Floor of L.C.

A24:=

3728.

y~c.y~

~>ri <

- l)Cm =

43.9 A:=.A24 24 Arci 21.1 A:=.

A24 Arci 3

A:=

A24 23-2 26 'rci 133.8 Arci A:=

. A24 43.3 28 Arci 38.6 A:=

A24 Arci l'I ('.)m

=

/

43.9 A:=

.A30 Arci z

21. 1 A:=

A30 Arci Walls 30:

35 are between L.C. and U.C.

A30:=

16246.

+ 1139.

3 23

~ 2 A:=

A30 Arci 133.8 Arci 43.3 A:=.'30 34 Arci 38.6 A:=.'30 Arci Walls 36:

41 are between U.C.

and L.C.

j3:=

36.. 41 (j3-6) l>c~= 4<8 Wall 42 is between U.C. and Outside A42

'=

24567.

)'l c.m

=

8 Walls 43:

45 are between D.E.

and Outside A43:=

12757.

(234.

126. 8)

Ared 1(

(30.0 +43.3 +29.7) 45 Arco A43

/~

73.0 A:=

'43 44 Arco n:= 43..45 Sum:= 7 An Sum

= 12757

ATTACHMENT TO AEP:N 188A Walls 46:

51 are Metal in L.C.

/So Page 28 A4

=

65616.

~/"h~

p/ c.~

43.9 A:=.'A46 46 Arci Z-21.1 A:=.A46 Arci 3

23 2

A:=.'A46 48 Arci 133.8 49 Arci n:= 46..51 43.3 A:=.A46 Arci S

Sum:=

An A:=..

A46

38. 6 Arci I

Sum

= 65616 Wall 52 is Metal in U.C.

A52

'.=

38435.

Summary of Wall Areas nl:= 1..

9 n2:=

10.. 17 n3:=

18.. 23 n4:=

24.. 29 nl 1391.907 914.929 1005.989 1335.537 3165.395 1300.847 1877.556 1287.839 293148

)

3 J

'I 7

n2 1391.907

)O

)3 Ig

)5)I

))

914.929 1005.989 1335.537 1300.847 1877.556 1287.839 3165.395 A

508.05 244.188 268.491 1548.452 501.106 446 '13

) &

KQ 5) z3 n4 538.53 258.838 284.599 1641.35 531.169 473.514 z.Y xl E7 z 'P n5:=

30.. 35 n6:=

36.. 41 n7:=

42.. 45 n8:=

46.. 52 n5 30 3) 7L 33 3 bg 3g 2511.357 1207.053 1327.187 7654.205 2477.034 2208.164 n6 2511.357 1207.053 1327.187 7654.205 2477.034 2208.164 3L 77 75 35 9'0 L/ /

n7 24567 4828.921 3288.351 4639.728 lf+

v/7 n8 9478.586 4555.767 5009.185 28889.177 9349.038 8334.247 38435 b

Y7 y V~

5e X)

ATTACHMENT TO AEP:N 1188A COMPUTER PROGRAM LOCA01

/9p Page 29

+/2 r/~

MAIN F, L, LT, N

READ TEND, LEDT Calc WR,

.LW CALL INITL UHVALS I'NITLS METAL DO 135 NC = 1, NCMPT CALL CLOSE1(NC) 135 CALL CLOSE2 CALL CLOSE3 1234 CALL ENERGY SATEST DO 137 NC = 1, NCMPT IF LSPRHT THEN CALL TEMPl(NC)

ELSE IF NC=7 THEN CALL TEMP7(NC)

ELSE CALL TEMP2(NC) 137 CALL SLAB CALL FLOWS IF()

GO TO 1234 CALL WRIT1 IF() CALL WRIT2 IF()

PLOT1(M)

IF()

PLOT2(M)

DATA SL, F, LT, NS, N

I I

I I

I INITL F, LT, N

Calc break flow area CALL SOLID()

CALL FCONVC1(HF())

Calc W(l:4,1:12),

P(1:3,1:12) and MOLES(),

MWC()

for all CMPTS 1:12 Estimate TRCS UHVALS F,

N Calc v(), h(), u()

for NCMPTS INITLS F,

SL, NS Calc DX(), HT()

SET TW(NS)=T(NC)

DTW(NS)=0.0 for all slabs.

ENERGY F, LT, N

Calc U(4,NC=l:12) mi*hi me*he Q(NC)

+ U(4,NC) for all Cmpts Set Q(l:12)=0.0, will calc in SLAB I

J SOLID()

(Ti, vs, hs)

Calc vs, hs of ice TEMP1(NC)

F, SL, L, LT, N

Calc new T, P, v, h for NCMPT if it is superheated.

CALL CLOSE1(NC)

TEMP2(NC)

B, F, L, LT, N

Calc new T, P, v, h for NCMPT if it is saturated.

-CLOSE1 for CLOSE EDITS TEMP7(NC)

B, F, LT, N

Calc new T, P, v, and WMELT(2)

Calc W(l:3,7), u()

VTOT(), h, etc.,

FT7=F(1:,NP,) for condensed vapor.

CALL CLOSE1(NC)

ATTACHMENT TO AEP:N 188A LOCA01..continued...

FLOWS B~ PLI 1 ~ FI SLg LTI LI N Set NF(N)=NCFT(N,1),

DFRX()=1.0, Set F(...,1)= F(...,2),

DF(...,1)=DF(

,2)

DH(...,l)=DH(...,2)

F(...,.2)=0.0, DF(...,2)=0.0, DH(

,2)=0.

Calc Z(NC), F(l,NP,.) for liquid Calc F(4,NBK,.), then F(l:2,

), DF(l:2,

),

DH(1:2,

) for the break flow path.

Calc DP(),

DV,, VBAR, F(4,NP,.) all flow paths Calc PLPS(),

NSNL(), DN(), DFRX(), all paths.

Calc DF(1,NP,.)

& DH(1,NP,.)

Calc DF(4,NP,.)

based on DF(4,1,.), various NP Calc F(2:3,NP,), DF(2:3,NP,.),

& DH(2:3,NP,.)

Calc W(3:4,NC), MOLES(), MWC() for all compartments NC=1,12 CLOSE3 for CLOSE EDITS TVOL(NC)

F, LT SLAB AI BI Fg SLI LTI NS~

N Set QW(NS,1)=QW(,2)

QW(NS,2)=0.0 Calc ASFR,TDEW,T CALL FCONVC(HF)

Calc HN, HC, HT, QW TW, Q(NC) for slabs NS=1,52 CLOSE2 for CLOSE EDITS METAL FI SLg LTg NS Calc WMTL, DXM for metal equip slabs NS=46,52 as DATA in INITLS WRITl AI BI NSI LT Write T, P, U, H, W,

F, DF, DH, QWg Qg TW(ND=l,NS=1:52) for all CMPTS WRIT2 A, LT Write TW(ND=l:S,NS=1:52)

Calc empt T* using VTOT(3,NC) and W(2:3,NC); used in SBRS SLAB & SATEST PLOT1(M)

PL Plots P(3,1:12)

T(1:12) vs Time PLOT2(M)

PL Plots P(3,1:12) on finer scale SATEST F, L, LT, N

Calc U(NC) above saturated; Is NC saturated?

FCONVI FI.SLI LTI NI NS Calc 'cross area of each empt for RE no

-ENTRY FCONVC ( HF )

Calc HF(1:52) for each slab.

P 0

Q r

r r

r ATTACHMENT TO AEP:N 1188A r

r r

Page 7 Yipes z~> 6'P~~~

lv'4>"~

I 9!

1 e

r e

3>

y. gs)

~J).+/fp

- p~z gVv f+

~

v

(

~

h QQ'0 7lg>"

v g

gS g(~

~Pry T 59~ -PPg~"

/

27-<

@0~-(5 5

m (S'"

) t C>o'~9 lv) - )Zebra AT

)v-('tv$ 0 -7 /, )

(gyes 9>) ) J j- (

33.1 ].

)q l >7p v j)

ATTACHMENT TO AEP:N 188A

/

Page 32 7gtyf~: l Bodies ofdifferent shapes in a tube; three-dimensional low; Sm/F, < 0.3 [29,38)

Diagram 10-9

~os SmlFo 2r "o 1.15cx ',

1 po/

(1 rSmlFo)

Do wodm Re' Name of a body and scheme Convex hemispherewup (without srdm~

end phne) Sm m

4 Drag coefflcient c>>

Re'=4 X 10', c>>=0.36; Re'=SX 10', c>>=0.34; r ~0.5 forr, see Diagram 10-1 7fdm Hemispher~one Sm =

m 4

Wo Fo ZO'e'=

1.35 X 10'; cx = 0.088; r ~0.5 Concave hemispherewup (without Tom end plane) Sm =

m 4

Re'=4X 10; c>>=1.44; Re' 5 X 10', cx = 1.42; r ~1.5 4mdm'onekemisphere Sm=

m 4

Wo,Fo pZO'e'=1.35 X 10', c>>=0.16; r ~0.5 Circular smooth cylinder in a flow

~

~dm parallel to the axis Sm m

4 r/dm 08 1

2 3

4 5

6 7

cx 1.0 0.91 0.85 0.85 0.87 0.90 0.95 0.99 r ~1.0 Q(o)

Ws 0

ZO 4.0 6'0 t/der 333

g

~

0

~

~

~

I

~

~

~

~

~

~ ~ t

~

I

~

~

s I

~

9

~

~

I t

I t

I I

I t

I I

I I

I I

I r

le I

It I' t

I I

Pi

~5

~ t

~

~

I

~

I I

I I

I I

I I

-lm I

I

~

I I 'I I

I I

~

~

~r~

mam laà 855

~

~

~

~

~

~

I I

~Fs~

I I I

I I

I I

lie I

I I I

ATTACHMENT TO AEP:NI 188A Page 34 DISPLAY COMPONENT DATA COMPONENT NO.: 1-PP-45-2 COMPONENT TYPE:

PUMP CENTRIFUGAL SIZE AND UNITS:

88500 GALLONS/MINUTE PLANT SYSTEM:

REACTOR COOLANT CABLE SYSTEM:

FUNCTIONAL NAME: REACTOR COOLANT PUMP g2 UNIT:

1 BUILDING: CONTAINMENT FLOOR ELEVATION: 598 ROOM:

LOWER CONTAINMENT, QUADRANT NO.

2 FEG FEG BOUNDARY:

1 0 2 02 jg1 2 RCP (REACTOR COOLANT PU PAGE 1

OF 21 CONTAINMENT AZIMUTH: 130 CONTROL PANEL: 1-RCP OTHER LOCATION ON SOUTHEAST SIDE OF STEAM GENERATOR g2-OME-3-2 INFORMATION:

ENTER NEXT COMPONENT NO.:

PF3/15=DISPLAY NEXT COMPONENT PF5/17=DISPLAY ASSEMBLY DATA PF9/21=SYSTEM MENU PRINTER ID:

PAGE NO.:

PF4/16=PRINT ALL DATA WITH M

& E NOS.:

N PF6/18=DISPLAY M

& E DATA PF8/20=PAGE FORWARD PF12/24=EXIT LU g4

ATTACHMENT TO AEP:N 1188A Page 35 FDBM043 DISPLAY COMPONENT DATA PAGE 1

OF 9

COMPONENT NO.: 1-SI-170-L2 COMPONENT TYPE:

VALVE CHECK SIZE AND UNITS:

10 INCH PLANT SYSTEM:

RESIDUAL HEAT REMOVAL CABLE SYSTEM:

FUNCTIONAL NAME: ACCUMULATOR TANK OME-6-2 OUTLET

& ECCS TO REACTOR COOLANT LOOP g2 COLD LEG CHECK VALVE UNIT: 1 BUILDING-CONTAINMENT FLOOR ELEVATION: 617 CONTAINMENT AZIMUTH-140 ROOM:

LOWER CONTAINMENT, QUADRANT NO.

2 FEG:

FEG BOUNDARY:

102.00 RCS (REACTOR COOLANT SYSTEM CONTROL PANEL:

OTHER LOCATION INFORMATION:

BETWEEN REACTOR COOLANT PUMP g1-PP-45-2 AND THE SHIELD WALL, 2 FEET BELOW THE 617 ELEVATION PLATFORM ENTER NEXT COMPONENT NO.:

PF3/15=DISPLAY NEXT COMPONENT PF5/17=DISPLAY ASSEMBLY DATA PF9/21=SYSTEM MENU PRINTER ID:

PAGE NO.:

PF4/16=PRINT ALL DATA WITH M

& E NOS.:

N PF6/18=DISPLAY M

& E DATA PF8/20=PAGE FORWARD PF12/24=EXIT LU P4

f14, Jll'VJla4441 j JV lli a

~ Jilt@ ~ s kVV4'1 ACUiCJLAT1.MCD 7/28/93 j O$C 4V p.l CALCULATION CHECK

• Maximum Differential Pressure across the Ventilation Unit

• by C. P. Lin A. Input Information ORIGIN :=

1 i := 1..2 j :=

1..3 1; Region 1 region between refueling canal and steam generator No 2, in which the accumulator line breaks.

Volume, V:= 27250 (ft 3) 1 Flow path(11) to the region between steam generator No 2 and ventilation unit,

Area, A

= 635 (ft 2) l,l Flow path(12) through refueling canal,

Area, A

= 72 (ft 2) 1,2 Flow path(13) to ice condenser through inlet doors,

Area, A

= 95 (ft 2) 1,3

2. Region 2

region betweem steam generator No 2 and ventilation unit,

Volume, V

= 19000 (ft 3) 2 Flow path(21) to the region between ventilation unit and steam generator No 3,

Area, A

= 1079 (ft 2) 2,1 Flow path(22) to ice condenser through inlet doors,

Area, A

= 64 (ft 2) 2I2 Flow path(23) to dead end region housing accumulators 2 and 3,

Area, A

= 77 (ft 2) 2/3

3. Lower Containment Conditions Plc := 14.7 (psia)

Tlc := 90 (F)

Water vapor partial pressure, Pw Air partial pressure, Pa Water vapor mass contained in Region Pw. 144 ~ V 1

Mw Mw =

i 1545

~ (Tlc + 460) 18 Air mass contained in Region 1 and 2, Pa-144

~ V RHlc := 100.0

= 0.698

= Plc Pw 1 and 2, Pa = 14. 002 t

58-0181 40.4533 (lb)

Mai 1545 (Tlc + 460) 28.97 I1873.167I Ma =

L1306.061]

(lb)

ATTACHMENT TO AEP:N 188A B. Flow Path Resistance 36 y := 12.8 2:= 1.0 Using Cx := 0.702 Sm

1. Flow Path through Steam Generator from Idel'Chik P.335, FO:= 1203 dm:= 11.5 l

DO := 23.2 DO Page 37 p 2 Sm:= dm. 1 Sm = 414 y= 1.2

.3333 RES:= 1.15-Cx-FO Sm 1-r FO 2

2 1

3 DO RES = 0.95 FO - Sm K:= RES.

1,1 FO K

= 0.408 l,l

2. Flow Path through Ventilation Unit from Idel'Chik P.335, FO := 1203 dm := 9.9 1 := 13.8 Sm := dm 1 DO := 51.84 DO dm y

~

y = 20.97 2

2 Using Cx := 1.11 z := 1.5 Sm

.3333 Sm = 136.62 RES:= 1.15. Cx.

FO Sm 1

FO 2

2 1

3 DO RES = 0.146 FO Sm K:= RES-2,1 FO K

= 0.115 2,1

3. Flow Path through Refueling Canal Entrance loss and velocity head, K

=

1 + 0.5 1,2 Dh = 7.299 Crane wall thickness, From Idel'Chik, P.144, 1

0.411 Dh K:= K 2,2 1,3 K

= 2.59 1,3

4. Flow Path through Ice Condenser Inlet Doors Lower inlet door opening, 84"x91.5" Hydraulic diameter, 4 (84 91.5) 1 Dh 2 (84 + 91.5) 12 1:= 3

ATTACHMENT TO AEP:N 1188A Page 38 p 3

5. Flow Path to Dead Ended Housing Accumulators 2

a 3

From FSAR Table 14.3.4-16, K:= 4.2 2/3 C. Assumptions

1. Pressures in the areas outside of region 1 a 2 are the same.

2.

From Tom s calculation results for region 1, air in the region 1 and 2

is depleted in 0.3 sec.

4. All the steam generated in the region 1 is carried out through flow paths.

D. Flow Calculations

1. Region 1

Critical flow rate from accumulator line break,-

D := 8.75 (in)

RCS cold leg conditions, Pres

= 2250 (psia)

Tres

= 541 (F) hrcs

= 536.07 (Btu/lb)

From "System Analysis Handbook",

mf := 24400 (lb/sec/ft 2) 2 n

D MFR:= mf.

MFR =

4 12 Steam generation, hrcs 58.018 Gs := MFR 1100.8 58.018 Air depletion rate, Ma 1

Sa Sa 1

0.3 1

Steam/air mixture density, Gs + Sa 1

4 1.019.10 (lb/sec) 3 6.244 F 10 (lb/sec) 3 Gs = 4.671.10 (lb/sec)

MW Sa Gs 1

18 28.97 Plc 144 MW

= 22.977 1

p

= 0.057 (lb/ft 3) 1 p

a 1

1545

~ (Tlc + 460)

MH 1

• • • • Assume region 1

& 2 pressure ****

Pl := 0.211 (psi above outside pressure)

P2 := 0.033 (psi above outside pressure)

ATTACHMENT TO AEP:

1188A Page 39P.4 Pressure differential across flow paths, DP

= P1 P2 1,1 DP

= Pl DP

= Pl 1,2 1,3 Steam/air flow through a flow path can be calculated by the following

equation, DP.p.144. 2-32.2 MFR:= A 0

l,j l,j Kl,j Flow ratio of path (1,2) and (1,3) to (l,l),

Al,j DPl,j Kl,j FR 1,

FRl,j 0.064 0.065 DPl,l A

1,1 Kl,l flow rate throu h 3

MFR

= 9.667.10 l,l MFR Steam/air g

path (1, 1),

Gs + Sa 1

(lb/sec)

Kl,j MFR

. FR j

Pressure differential across flow paths, 2

DP 1,'P l(j 2

A

.p l,j 1

2. 32.2 144 0.211 0.211 3

Sa

= 9.883 10 2

2. Region 2

Incoming steam flow from Region 1, Gs 3

STi := MFR STi = 4.137 '0 l,l Gs + Sa 1

Incoming air flow from Region 1, AIRi := MFR STi 1,1 Air depletion rate in Region 2, Ma 2

Sa

= + AIRi 2

0.3 (lb/sec)

(lb/sec)

(lb/sec)

ATTACHMENT TO AEP:N 188A Page 40 p.5 Steam/air mixture density, STi + Sa 2

MW

= 24.554 2

MW Dp.p 144 2.32.2 MFR:= A a

2/j 2/j K

2 /

Flow ratio of path (2,2)&(2,3) to (2,1),

2 Sa STi 2

18 28.97 Plc 144 p

p

= 0.061 (lb/ft 3) 2 1545 2

~ (Tlc + 460)

MW 2

Steam/air flow through a flow path can be calculated by the following

equation, A

2 /

FR2/j A

2,1 St K

2,1 K

2/ g te thr FR 2/

0. 012 0.012 (2/1) /

4 MFR

= 1.369 10 2,1 MFR 2,1 earn/air flow ra ough path STi + Sa 2

(lb/sec) j Pressure differential across flow paths, 2

K 2 /

DP 2/g 2

A

~ p 2/g 2

MFR FR 2 32.2 144 DP 2/

0.033 0.033 I Differential pressure across ventilation unit is less than 0.1 psi I

ATTACHMENT TO AEP:N 188A Page 41 AMERlCAN KLECTRlC POWKR Data July 30, 1993 subject Cook Nuclear Plant Containment Building, EL. 598'-9 3/8" HV-CFT Ventilation Units From C. E. Shute/

. L. Ball To J.

B. Eingseed/S.

A. Hover NEDS has performed a GT-STRUDL finite element analysis of the filter house portion of the HV-CFT ventilation units as requested by S.A.

Hover in his June 16, 1993 memo.

The analysis found that the filter house can withstand a jet impingement pressure of 0.25 psi based on the capacity of the floor anchorage and of 1.13 psi based on the capacity of the housing.

The Technical Assessment Section has established that the maximum pressure that the units can be expected to receive is less than 0.10 psi.

Therefore, the HEPA filters housed inside the box will not be dislodged in the event of a LOCA or steam line break.

The original design criteria for the filter house required that it be able to withstand a jet impingement pressure of 2 psi.

The above findings by NEDS show pressures much less and it should be noted that NEDS did not use a conservative approach in their analysis.

During the next refueling outages, a walkdown will be performed by NEDS to gather additional structural data on these filter houses.

Recommendations will then be made for modifications necessary to bring these structures up to their original design requirements.

Approved by r

cJcc lA N

R ccIa - Man er' clear Design - Structural Er, Analytical CES/ JAR: dm xc:

J. A. Kobyra/R.

C. Armstrong Ref stru'thv+ftms Intra4ystam