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:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 PD 1 1 DEAN,W 1 1 INTERNAL: AEOD/DOA 1 1 NRR/DE/EMEB 1 1 NRR/DRPW/OGCB 1 1 NRR/DRSS/PEPB 1 1 N

REG G

~ II-2 NRR/DSSA FI FILE 02 01 1

1 1

1 1

1 1

1 NRR/DSSA/SRXB NRR/SCSB RES/DSIR/EIB 1

1 1

1 1

1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 D

A, D i D

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!

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 AEP:NRC:1188A 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 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.

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.

loooaI 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 VENTILATION UNITS

ATTACHMENT TO AEP:NR 88A Page 1 ANERlCAN ELECTRIC PWKR Dato July 29, 1993 sub)oct Ef feet 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 the double-ended cold-leg break or cross-under

'Leak-before-break'riteria 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. Brewer / J.B. Kingseed / S.A. Hover w attachment E.ED Fitzpatrick w/o II G.R. Burris Jr. w/o It M.K. Guha / C.D. Olsen / File N930601 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 Date:~726 93 Review: C. P. Lin ethod: 4 ~ ~ C.< > 4 8.4 Date: 7 > 3 Approval:M. K. Guha 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 10

f. New Thermodynamic State of Saturated Compartments 10

g. Heat Transfer to Containment Walls

h. Heat Transfer Within Containment Walls 12

6. Reference(s) 13

7. Attachment(s). 15

ATTACHMENT TO AEP:N 188A Page 3 TECHNICAL ASSESSMENT CALCULATION VERIFICATION CHECKLIST Page 0 of 'SQ Reviewer: Q~ Date:

Section lleneger: J~tt-~+

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- ~rM f able compared to the input? 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 c used and their sources documented? 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-

I ~V ATTACHMENT TO AEP:N 1188A Page 4 EFFECT OF L.O.C.A. ON VENTILATION UNITS

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.

~

<</ 5Q ATTACHMENT TO AEP: 188A

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) Peak Deck Differential Pressure(psi)

LOCA01 MPR TMD 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.

/'g o ATTACHMENT TO AEP:N 1188A 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.

~ (

~ J~

ATTACHMENT TO AEP:N 188A Page~ 7 7 /7.qf> >

4. ASSUMPTIONS 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.

'/>u ATTACHMENT TO AEP:N 1188A 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. INITIAL COMPARTMENT 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) total ice condenser volume VTOT(2,7) air and vapor volume VTOT(1,7) ice volume 7 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

(P%

ATTACHMENT TO AEP:N 188A 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() pressure difference between compartments AREA() flow area KLS() flow loss coefficient v() average specific volume of mixture dv() 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.

where Cflw weir flow coeff; taken large to accommodate inertia.

rho density of water.

Width a characteristic width between adjacent compartments.

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

Z(NT,)

'/'3q ~ d ATTACHMENT TO AEP:N 1188A 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() mass flow per time step

?

liquid, vapor, and air in flow path into the compartment out flow path from the compartment 1,2 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.

P IV/ Pg ATTACHMENT TO AEP:N 1188A 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) (

= U(4,NC)

Mg*Vg(P9,T2) + Ma*Va(Pa,T2) ) / 2.0 G2(P2,T2) ( Mg*Ug(Pg,T2) + Ma*Ua(T2) )

where VTOT(3,NC) compartment total volume U(4,NC) compartment total energy P2,T2 new total pressure and temperature Pg,Pa partial pressure of vapor, air Mg,Vg,Ug mass, specific volume, and specific energy of vapor Ma,Va,Ua 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, Gl(T2) = U(4,NC) ( Mf(T2)*Uf(T2) + Mg(T2)*U9(T2) + Ma*Ua(T2) )

where U(4,NC) = compartment

= new temperature total energy T2 Mf,Mg,Ma = mass of liquid, vapor, and air Uf,Ug,Ua = internal energy of liquid, vapor, air 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 where qt total heat flux(Btu/hr/ft**2) qc,qn,qr,qf heat flux due to condensation, natural convection, radiation, and forced convection.

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

Tb,Tsat,Tw bulk and saturation temperatures of gas mixture and wall surface temperature.

Condensation was assumed to occur only the dew point temperature.

if the wall temperature was less than

g / t./ v)+!

ATTACHMENT TO AEP:N 1188A zg ~~

H. HEAT TRANSFER WITHIN CONTAINMENT WALLS(SLABS)

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:

qw(2) )*TS /

DTw(l) = ( QWavg ( rho

• dx(l)

• Cp )

where QWavg ( qt(TS=1) + qt(TS=2) ) / 2.0 time averaged heat flux entering surface of node conduction heat flux leaving node 1 to node 2 l.

qw(2)

TS time step size rho,Cp density and heat capacity of concrete or steel.

dx(1) 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 II node n-1 and II II entering II node n qw(n+1) n n+1 dx(n) = thickness of control volume, node n

ATTACHMENT TO AEP:N 188A 76~))q

6. REFERENCES 1 ~ Memo of May 27, 1993, from S.A. Hover to T.J. Crawford, of Fibrous Material on Recirculation Pump Screen'.

titled 'Effect 2 ~ Drawing No. 107C-890301-H, from American Air Filter Co., Inc.,

Louisville, Ky., 1972.

3. Larson, J.R., System Analysis Handbook, NUREG/CR-4041, EGG-2354, Revision 1, November, 1985.

4. 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

5. MPR Associates, Inc., Ice Condenser Containment Independent Analysis Program Final Report, MPR-340, April, 1972.

6. Technical Assessment Section calculation N-921001, Containment Building Pressure and Temperature in Event of DHR Failure While in Mid-Loop Operation, January, 1993.

7 ~ Containment Data Collection Notebook, D.C. Cook Nuclear Plant I.P.E.,

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

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

9. 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. Idelchik, I.E., and Fried, E., Flow Resistance: A Design Guide for Engineers., Hemisphere Publishing Co., New York, 1989.

13. 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

"'"(w~

ATTACHMENT TO AEP:N 188A Page 19 l jg o AREA REACTOR COOLANT DOOR SYSTEM COMPARTMENT ,NO. 3 ICE CONDENSER

~ )

<c STEAM GENERATOR

) ~

r') l3 2'og ~ ~

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REA CTOR COOLANT FLOV/'UCT SYSTEM RUPTURE UNDERNEATH REFUELLING CANAL ~

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

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ATTACHMENT TO AEP:N 188A l IP/g~

f'age 20 fg ) 0 ~Jz.~gg~

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ATTACHMENT TO AEP'NRC'1188A Page 21

= 9~~$

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..-vg 0 = )~" ~

/v 27<$ 0 i=7) ltu'0 7 h= ) ~'t IC 3 9o o'4 0 /i "" QiC. )ro>g =

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4=72. 2,Z 4'o,i REACTOR CONTAINMENT SUBVOLUMES AND F'LOW PATHS

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/pp ATTACHMENT TO AEP: 1188A Page 22

~ ~/~~

COMPARTMENT NUMBERS AND VOLUMES(Refs. 4 a 5 )

No. Description Volume (ft**3)

Break region in Lower Compartment 27 250.

between Refueling Canal and Steam Generator No. 2 (S/G 2)

Volume between S/G 2 and 19 000.

Ventilation Unit.

Volume between Ventilation Unit and 19 000.

S/G 3 Volume between S/G 3 and S/G 4 90 000.

Volume between S/G 4 and S/G 1 38 000.

Volume between S/G 1 and Refueling 22 500.

Canal Ice Condenser(void volume) 126 940.

Upper Compartment 745 896.

Dead Ended Region Housing 27 450.

Accumulators 2 and 3 10 Dead Ended Region Instrument Room 17 111.

Dead Ended Region Housing 27 450.

Accumulators 1 and 4 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 Thickness Removes Heat (ft**2) (ft) From Cmpt 1 Between Cmpts 1 a'nd 9 1 392. 3.0/2 2 Between Cmpts 2 and 9 915. 3.0/2 3 Between Cmpts

\

3 and 9 1 006. 3.0/2 4 Between Cmpts 4 and 9 1 336. 3.0/2 5 Between Cmpts 4 and 10 3 165. 3.0/2 6 Between Cmpts 4 and I

ll 1 301. 3.0/2 7 Between Cmpts 7 and 7 293 148. N/A 8 Between Cmpts 5 and ll 1 878. 3.0/2 9 Between Cmpts 6 and ll 1 288. 3.0/2 10 Between Cmpts 9 and 1 1 392. 3.0/2 J

11 Between Cmpts 9 and 2 915. 3.0/2 12 Between Cmpts 9 and 3 1 006. 3.0/2 13 Between Cmpts 9 and 4 1 336. 3.0/2 14 Between Cmpts 10 and 5 3 165. 3.0/2 10 15 Between Cmpts 11 and 4 1 301. 3.0/2 16 Between Cmpts ll and 5 1 878. 3.0/2 17 Between Cmpts 11 and 6 1 288. 3.0/2 18 Interior of Cmpt 1 508. 2.25 19 Interior of Cmpt 2 244. 2.25 20 Interior of Cmpt 3 269. 2.25 21 Interior of Cmpt 4 1 549. 2.25 22 Interior of Cmpt 5 501. 2.25 23 Interior of Cmpt 6 447. 2.25 24 Floor of Cmpt 1 539. 5.00 25 Floor of Cmpt 2 259. 5.00

ATTACHMENT TO AEP:N 188A Page 24 26, Floor of Cmpt 3 285. 5.00 27 Floor of Cmpt 4 1 641. 5.00 28 Floor of Cmpt 5 531. 5.00 29 Floor of Cmpt 6 474. F 00 30 Between Cmpts 1 and 8 2 511. 2.875/2 31 Between Cmpts 2 and 8 1 301. 2.875/2 32 Between Cmpts 3 and 8 1 327. 2.875/2 33 Between Cmpts I

4 and 8 7 654. 2.875/2 34 Between Cmpts 5 and 8 2 477. 2.875/2 35 Between Cmpts 6 and 8 2 208. 2.875/2 36 Between Cmpts 8 and 1 2 511. 2.875/2 37 Between Cmpts 8 and 2 1 301. 2.875/2

't 38 Between Cmpts 8 and 3 1 327. 2.875/2 39 Between Cmpts 8 and 4 , 7 654. 2.875/2 40 Between Cmpts 8 and 5 2 477. 2.875/2 41 Between Cmpts 8 and 6 2 208. 2.875/2 42 Between Cmpt 8 and Outside 24 567. 3.5 43 Between Cmpt 9 and Outside 4 829. 3.5 44 Between Cmpt 10 and Outside 3 288. 3 ' 10 45 Between Cmpt ll and Outside 4 640. 3.5 46 Metal in Cmpt 1 9 479 ~ 0.134 47 Metal in Cmpt 2 4 556. 0.134 48 Metal in Cmpt 3 5 009. 0.134 49 Metal in Cmpt 4 28 889. 0.134 50 Metal in Cmpt 5 9 349. 0.134 51 Metal in Cmpt 6 8 334. 0.134 52 Metal in Cmpt 8 38 435. 0.012

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

DESCRIPTION OF FLOW PATHS/AREAS BETWEEN COMPARTMENTS(REFS. 4 & 5)

No. Description Flow Area Loss Coeff (ft**2) 1 From Cmpt 1 to 2 635.0 0.300 2 From Cmpt 2 to 3 1 079.0 0.170 3 From Cmpt 3 to 9 77.0 4.200 4 From Cmpt 3 to 4 585.0 0.340 5 From'Cmpt 4 to 5 585.0 0.340 6 From Cmpt 6 to 5 635.0 0.300 7 From Cmpt, 1 to 6 72.0 1.450 8 From Cmpt 2 to 9 77.0 4.200 9 From Cmpt 9 to 10 10.0 3.000 10 From Cmpt ll to 10 10.0 3.000 ll From Cmpt 5 to ll 154.0 4.200 12 From Cmpt 4 to 12 144.0 1.500 13 From Cmpt 1 to 7 122.0 0.890 14 From Cmpt 2 to 7 72.0 0.890 15 From Cmpt 3 to 7 '2.0 0.890 16 From Cmpt 4 to 7 487.0 0.890 17 From Cmpt 5 to 7 155.0 0.890 18 From Cmpt 6 to 7 155.0 0.890 19 From Cmpt 7 to 8, 2 003.0 1.430 20 From Break Line to 1 0.4 N/A

'>(3" ATTACHMENT TO AEP:N 1188A Page 26 Walls and Related Compartments; file=LOCA01 Areas are from HALFLP02 & N.O.D. note book 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 A:=

32.1 'LC Arco A:=

21.1 'LC Arco A:=

23 '

Arco

'LC A:=

4 'rco 30.8 ALC A:=

73.0 'LC Arco A:=

30.0 'LC A:=

Arco A:= 43.3 29.7 ALC ALC Arco Arco Wall 7 is Ice Baskets in Program LOCAOI A9 '.= 293148. g(( ~ -

g Walls 10: 17 between D.E. and L.C.

M= I 9 )1 I j2:= 10 .. 17 J>lt Q Q ~Q ) )g (j2 - 9)

Walls 18: 23 are Xnterior of L.C.

>I(.~ = I z.

A18:= 3517.

Arci:= 43.9 +21.1 +23.2 +133.8 +43.3 +38.6 18 'rci A:= 43.9 '18 A:=

21.1 Arci

~

A18 A:=

23 '

Arci

'A18 A21 '

133.8 'AIS Arci A:='rci 22

43.3 A18 A:= .

38.6 '18 Arci

y~c.y~ ~>ri <

ATTACHMEMT TO AEP:N 188A Walls 24: 29 are Floor of L.C. A24:= 3728.

l)Cm =

-

A:=

24

.

43.9 Arci A24 A:= .

21.1 Arci A24 26 'rci A:=

3 23-2 A24 133.8 Arci A:=

28

43.3 Arci

. A24 A:= 38.6 Arci A24 Walls 30: 35 are between L.C. and U.C. A30:= 16246. + 1139.

l'I ('.)m A:=

=

43.9 Arci

/

.A30 A:= z 21.

Arci 1

A30 A:= 3 23 ~ 2 Arci A30 133.8 Arci A:=

34

.

43.3 '30 Arci A:= .

38.6 '30 Arci Walls 36: 41 are between U.C. and L.C.

j3:= 36 .. 41 l>c~= 4<8 (j3- 6)

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.

A:=

/~

(234. 126. 8) 73.0 '43 Ared 44 Arco 1(

(30.0 +43.3 +29.7) 45 A43 Arco n:= 43..45 Sum:= 7 A n Sum = 12757

/So ATTACHMENT TO AEP:N 188A Page 28 Walls 46: 51 are Metal in L.C. A4  := 65616. ~/"h~

p/ c.~ Z- 3 A:=

46

.

43.9 'A46 Arci A:= .

21.1 Arci A46 A:=

48

.

23 2 Arci

'A46 49 133.8 Arci A:= .

43.3 Arci A46 A:= .. 38.

Arci 6

A46 S I n:= 46..51 Sum:= An 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 n2 A 1391.907 ) n4 914.929 1391.907 )O 508.05 ) & 538.53 z.Y 914.929 244.188 258.838 1005.989 3 1005.989 1335.537 268.491 KQ 284.599 xl 1335.537 )3 1548.452 5) 1641.35 E7 3165.395 J 3165.395 Ig 1300.847 501.106 531.169 1300.847 )5 446 '13 z3 473.514 z 'P 1877.556 1287.839 'I 1877.556 )I 1287.839 ))

293148 7 n5:= 30 .. 35 n6:= 36 .. 41 n7:= 42 .. 45 n8:= 46 .. 52 n5 n6 n7 n8 2511.357 30 2511.357 3L 9478.586 b 1207.053 3) 24567 lf+

1207.053 77 4828.921 v/7 4555.767 Y7 1327.187 7L 1327.187 75 7654.205 3288.351 5009.185 y V~

33 7654.205 35 28889.177 2477.034 3 bg 4639.728 2208.164 3g 2477.034 9'0 9349.038 5e 2208.164 L/ / 8334.247 X) 38435

/9p ATTACHMENT TO AEP:N 1188A Page 29

+/2 r/~

COMPUTER PROGRAM LOCA01 MAIN INITL SOLID()

(Ti, vs, hs)

F, L, LT, N F, LT, N Calc vs, hs of ice Calc break flow area I READ TEND, LEDT CALL SOLID() J Calc WR, .LW CALL FCONVC1(HF()) TEMP1(NC)

CALL INITL Calc W(l:4,1:12), F, SL, L, LT, N UHVALS P(1:3,1:12) and I'NITLS I MOLES(), MWC() Calc new T, P, v, h for NCMPT if it I

METAL I

for all CMPTS 1:12 I Estimate TRCS is superheated.

DO 135 NC = 1, NCMPT I CALL CLOSE1(NC) CALL CLOSE1(NC) 135 UHVALS CALL CLOSE2 CALL CLOSE3 F, N TEMP2(NC) 1234 Calc v(), h(), u() B, F, L, LT, N CALL ENERGY for NCMPTS SATEST Calc new T, P, v, h for NCMPT if it DO 137 NC = 1, NCMPT is saturated.

IF LSPRHT THEN INITLS CALL TEMPl(NC) -CLOSE1 ELSE IF NC=7 THEN F, SL, NS for CLOSE EDITS CALL TEMP7(NC)

ELSE Calc DX(), HT()

CALL TEMP2(NC) SET TW(NS)=T(NC) 137 DTW(NS)=0.0 for TEMP7(NC) all slabs.

CALL SLAB B, F, LT, N CALL FLOWS Calc new T, P, v, IF() GO TO 1234 ENERGY and WMELT(2)

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

CALL WRIT1 F, LT, N VTOT(), h, etc.,

IF() CALL WRIT2 FT7=F(1:,NP,) for IF() ."" PLOT1(M) Calc U(4,NC=l:12) condensed vapor.

IF() PLOT2(M) mi*hi me*he Q(NC)

+ U(4,NC) CALL CLOSE1(NC) for all Cmpts DATA Set Q(l:12)=0.0, will calc in SLAB SL, F, LT, NS, N

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

FLOWS SLAB B~ PLI 1 ~ FI SLg LTI LI N AI BI Fg SLI LTI NS~ N Set NF(N)=NCFT(N,1), DFRX()=1.0, Set F(...,1)= F(...,2), DF(...,1)=DF( ,2) Set QW(NS,1)=QW(,2)

DH(...,l)=DH(...,2) QW(NS,2)=0.0 F(...,.2)=0.0, DF(...,2)=0.0, DH( ,2)=0.

Calc ASFR,TDEW,T Calc Z(NC), F(l,NP,.) for liquid CALL FCONVC(HF)

Calc F(4,NBK,.), then F(l:2, ), DF(l:2, ),

DH(1:2, ) for the break flow path. Calc HN, HC, HT, QW Calc DP(), DV,, VBAR, F(4,NP,.) all flow paths TW, Q(NC) for Calc PLPS(), NSNL(), DN(), DFRX(), all paths. slabs NS=1,52 Calc DF(1,NP,.) & DH(1,NP,.)

Calc DF(4,NP,.) based on DF(4,1,.), various NP CLOSE2 for CLOSE EDITS 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 METAL CLOSE3 FI SLg LTg NS for CLOSE EDITS Calc WMTL, DXM for metal equip slabs NS=46,52 as TVOL(NC) DATA in INITLS F, LT Calc empt T* using SATEST WRITl VTOT(3,NC) and W(2:3,NC); used in F, L, LT, N AI BI NSI LT SBRS SLAB & SATEST Calc U(NC) above saturated; Write T, P, U, H, W, Is NC saturated?

F, DF, DH, QWg Qg PLOT1(M)

TW(ND=l,NS=1:52) PL for all CMPTS FCONVI Plots P(3,1:12) &

T(1:12) vs Time FI .SLI LTI NI NS Calc 'cross area of WRIT2 PLOT2(M) each empt for RE no PL A, LT -ENTRY FCONVC ( HF )

Plots P(3,1:12) on Calc HF(1:52) for Write TW(ND=l:S,NS=1:52) finer scale each slab.

0 Q r r r r r r r e r e P

ATTACHMENT TO AEP:N 1188A Page 3> y. gs)

~J).+/fp 7 Yipes z~> 6'P~~~ 9! 1 lv'4>"~ - p~z I

gVv f+

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ATTACHMENT TO AEP:N 188A Page 32 7gtyf ~: l Bodies of different shapes in a tube; three-dimensional low; Diagram Sm/F, < 0.3 [29,38) 10-9

',

~os SmlFo 2r "o 1.15cx 1 po/ (1 rSmlFo) Do Re' wodm

@

Name of a body and scheme Drag coefflcient c>>

Convex hemispherewup (without Re'=4 X 10', c>>=0.36; end phne) Sm m srdm~

Re'=SX 10', c>>=0.34; 4

r ~0.5 for r, see Diagram 10-1 Hemispher~one Sm Wo Fo ZO'e'= m =7fdm 4

1.35 X 10'; cx = 0.088; r ~0.5 Concave hemispherewup (without end plane) Sm m = Tom 4

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

=

ZO'e'=1.35 Smm 4mdm'onekemisphere 4

X 10', c>>=0.16; Wo,Fo p r ~0.5 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 Circular smooth cylinder in a flow r ~1.0

~

parallel to the axis Sm m

~dm 4 Q(o)

Ws

!

0 ZO 4.0 6'0 t/der 333

0 ~ ~

g ~ ~

I ~ ~ ~ ~

~ ~ ~ t ~ I . ~

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~ ~ ~ ~ ~

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~ Fs~ I I I I I I I lie I I I I

ATTACHMENT TO AEP:NI 188A Page 34 DISPLAY COMPONENT DATA PAGE 1 OF 21 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 CONTAINMENT AZIMUTH: 130 ROOM: LOWER CONTAINMENT, QUADRANT NO. 2 FEG FEG BOUNDARY:

1 0 2 02 jg 1 2 RCP ( REACTOR COOLANT PU CONTROL PANEL: 1-RCP OTHER LOCATION ON SOUTHEAST SIDE OF STEAM GENERATOR g2-OME-3-2 INFORMATION:

ENTER NEXT COMPONENT NO.: PRINTER ID: PAGE NO.:

PF3/15=DISPLAY NEXT COMPONENT PF4/16=PRINT ALL DATA WITH M & E NOS.: N PF5/17=DISPLAY ASSEMBLY DATA PF6/18=DISPLAY M & E DATA PF8/20=PAGE FORWARD PF9/21=SYSTEM MENU 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 BETWEEN REACTOR COOLANT PUMP g1-PP-45-2 AND THE SHIELD WALL, INFORMATION: 2 FEET BELOW THE 617 ELEVATION PLATFORM ENTER NEXT COMPONENT NO.: PRINTER ID: PAGE NO.:

PF3/15=DISPLAY NEXT COMPONENT PF4/16=PRINT ALL DATA WITH M & E NOS.: N PF5/17=DISPLAY ASSEMBLY DATA PF6/18=DISPLAY M & E DATA PF8/20=PAGE FORWARD PF9/21=SYSTEM MENU PF12/24=EXIT LU P4

f14, Jll'VJla4441 j JV lli a ~ Jilt@ ~ s kVV4'1 j O$ C 4V ACUiCJLAT1.MCD 7/28/93 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)

Flow path(12) l,l 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 2

= 19000 (ft 3)

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 2/3

= 77 (ft 2)

3. Lower Containment Conditions Plc := 14.7 (psia) Tlc := 90 (F) RHlc := 100.0 Water vapor partial pressure, Pw := 0.698 Air partial pressure, Pa := Plc Pw Pa = 14. 002 Water vapor mass contained in Region 1 and 2, Pw. 144 V ~

1 58-0181 Mw i

1545 18

~

(Tlc + 460)

Mw = t40.4533 (lb)

Air mass contained in Region 1 and 2, Pa- 144 V ~

Ma i

1545 28.97 (Tlc + 460)

Ma =

I1873.167I L1306.061] (lb)

ATTACHMENT TO AEP:N 188A Page 37 p 2 B. Flow Path Resistance

1. Flow Path through Steam Generator  :

from Idel'Chik P.335, FO:= 1203

= 23.2 dm:= 11.5 l 36 Sm:= dm. 1 Sm = 414 DO y := 12.8 DO y= 1.2 2

Using Cx := 0.702  := 1.0 Sm

.3333 RES:= 1.15- Cx-FO 3

1 2 DO RES = 0.95 1-r Sm FO 2

-

K:=

1,1 RES.

FO FO Sm K

l,l

= 0.408

2. Flow Path through Ventilation Unit from Idel'Chik P.335, FO := 1203 dm := 9.9 1 := 13.8 Sm  := dm 1 Sm = 136.62 DO := 51.84 DO dm y ~

y = 20.97 2 2 Using Cx := 1.11 z := 1.5 Sm

.3333 RES:= 1.15. Cx.

FO 3

1 2

DO RES = 0.146 Sm 1

FO 2

K:=

2,1 RES-FO Sm FO K

2,1

= 0.115

3. Flow Path through Refueling Canal Entrance loss and velocity head, K  := 1 + 0.5 1,2

4. Flow Path through Ice Condenser Inlet Doors Lower inlet door opening, 84"x91.5" Hydraulic diameter, 4 (84 91.5) 1 Dh Dh = 7.299 2 (84 + 91.5) 12 Crane wall thickness, 1:= 3 From Idel'Chik, P.144, 1

Dh 0.411 K 1,3

= 2.59 K:=

2,2 K

1,3

ATTACHMENT TO AEP:N 1188A Page 38 p 3

5. Flow Path to Dead Ended Housing Accumulators 2 a 3 K:=

From FSAR Table 14.3.4-16, 2/3 4.2 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 4 MFR:= mf. MFR = 1.019.10 (lb/sec) 4 12 Steam generation, hrcs 58.018 3 Gs  := MFR Gs = 4.671.10 (lb/sec) 1100.8 58.018 Air depletion rate, Ma 1 3 Sa Sa 6.244 10 F

(lb/sec) 1 0.3 1 Steam/air mixture density, Gs + Sa 1

MW MW = 22.977 Sa 1 Gs 1 18 28.97 Plc 144 (lb/ft 3) p 1

a

1545 MH

~

(Tlc + 460) p 1

= 0.057 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 39 P.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 K l,j Flow ratio of path (1,2) and (1,3) to (l,l),

DP A

l,j l,j Kl,j FR 1,

FR l,j DP 0.064 0.065 A

l,l 1,1 K Steam/air l,l flow rate throu path (1, 1),

gh Gs + Sa 1 3 MFR MFR = 9.667.10 (lb/sec) l,l Pressure j

differential across flow paths, 2 DP K MFR . FR l,j 1,'P 0.211 l(j A 2

.p

2. 32.2 144 0.211 l,j 1

2. Region 2 Incoming steam flow from Region 1, Gs STi := MFR l,l Gs + Sa STi = 4.137 '0 3 (lb/sec) 1 Incoming air flow from Region 1, AIRi := MFR STi 1,1 (lb/sec)

Air depletion rate in Region 2, Ma Sa 2

= AIRi 0.3 2

+ Sa 2

= 9.883 10 3

(lb/sec)

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

MW MW = 24.554 2 Sa 2 STi 2 18 28.97 Plc 144 (lb/ft 3) p 2

1545 MW

~

(Tlc + 460) p 2

= 0.061 2

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

A K FR 2/ 2,1 2/

FR 2/j A K 0. 012 2,1 2/ g 0.012 St earn/air flow ra te through path (2/1) /

STi + Sa 2 4 MFR MFR = 1.369 10 (lb/sec) 2,1 2,1 Pressure j

differential across flow paths, 2

K MFR FR DP 2/ 2/

DP 2/g 2 2 32.2 144 0.033 A ~

p 0.033 2/g 2 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