ML20236K908

Forwards Revised Pages to 861217 Application for Amend to License SNM-1067,per 870713-14 Meeting,For Review & Approval

ML20236K908
Person / Time
Site:	07001100
Issue date:	07/24/1987
From:	Sheeran R ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
To:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
28435, NUDOCS 8708100044
Download: ML20236K908 (41)

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July 24, 1987

'x License SNM-1067 x.._ /

Docket 70-1100 U.S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. L.C. Rouse, Chief Fuel Cycles Safety Branch

Subject:

Changes to SNM-1067

Reference:

Letter from H.V. Lichtenberger, CE, to W.T. Crowe, NRC, dated December 17, 1986

Dear Mr. Rouse:

On July 13-14, 1987, R. Klotz and I met with you and G. Bidinger at our facility to discuss the subject license changes submitted with the referenced letter.

At the meeting it was agreed that certain additional changes would be made to the referenced submittal.

Accordingly, a new submittal, containing the agreed on changes, is attached for your review and approval.

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Combustion Engineenng. Inc 1000 Prospect Hrli Road (203) 688-1911 Post Ofhce' Box' 500

~" - Telex 9-9297 8708100044 870724 Windsor. Connecticut 06095 PDR ADOCK 07001100 f[

C PDR

s U.S. Nuclear Regulatory Commission 2

License SNM-1067

(

Br. L.C. Rouse Docket 70-1100 i

I DELETED PAGE ADD PAGE PAGE N0.

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II.8-74 3

In addition, Appendices C and D have been updated and are included as part of this submittal.

Very truly yours, l

OCc J%~

R.E. Sheeran Manager, Nuclear Licensing, Safety Accountability and Security RES/kfs Attachement

I' l

1 i

i PART II SAFETY DEMONSTRATION (Cont'd.)

7.0 Nuclear Criticality Safety 7.1 Use of Surface Density Technique 7.2 Validation of Calculational Methods for Criticality Safety 8.0 Process Description and Safety Analysis I

l i

8.1 UO2 Powder Processing 8.2 Scrap Recycle 8.3 Storage and Transfer l

8.4 Pre-Treatment of Low Level Liquid Wastes

{

8.5 Rod Loading and Assembly Fabrication 8.6 High Enriched Uranium l

8.7 Maximum Moderator Density in Air From Automatic l

Sprinklers Installed in Assembly Room, Building No. 17 9.0 Accident Analysis 9.1 Spectrum and Impact of Accidents Analyzed 9.2 Analysis of Postulated Incidents Having Off-Site Impact 9.3 Worst Case Scenario APPENDIX A:

Decommissioning Plan APPENDIX B:

Form 10-K Annur.1 Report l

APPENDIX C:

Validation of Criticality Methods for Calculating the l

Effective Multiplication Factor Under Low Hydrogen Density Moderation Conditions APDENDIX D:

Mist Density Evaluation for a Single Sprinkler Head Figure B-1:

Floor Plan Building #17 License No. SNM-1067, Pocket 70-1100 Rev. 3 Date:

7/24/87 Page: 3

r y

1 l

l 4.2.4 Safety Margins - Individual Units - Safety margins applied to units calculated to be critical (with up to 2% uncertainty),

)

and incorporated in the SIU's shall be as follows:

Mass 2.3 Volume 1.3 l

Cylinder Diameter 1.1 Slab Thickness 1.2 These values shall be further reduced where necessary to j

assure maximum fraction critical values of 0.4 for 1

geometrically limited units, and 0.3 for mass limited units (based on optimum water moderation).

An additional reduction has been applied to several mass and volume limits to assure that spacing requirements remain constant for all enrichments.

4 For validated computer calculations, the highest K eff for a single unit or array shall be 0.95 including a 2-sigma statistical uncertainty and including all applicable 4

I o

uncertainties and bias.

j o

a The basic assumptions used in establishing safe parameters for single units and arrays shall be as follows:

1 The possibility of accumulation of fissile materials in inaccessible locations shall be minimized.

o Nuclear safety shall be dependent on the degree of o

moderation within the process unit. Additional moderating materials, when considered to be credible, will be o

included in the analysis, o

'l License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page: I.4-6

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I Nuclear safety shall be independent of neutron reflector thickness for the reflector of interest.

Optimum conditions (limiting case) of water moderation

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and heterogeneity credible for the system shall be determined in all calculations.

The analytical method (s) used for criticality safety analysis and the source of validation for the method (s) shall be specified.

Safety margins for individual units and arrays shall be based on accident conditions such as flooding, multiple batching, and fire.

The method of deriving applicable multiplication factors shall be specified.

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page: I.4-7

i l

4.2.4 A Moderation Control (Areas B and C of NFM-C-4440)

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l For moderation control systems a maximum K of 0,95 shall apply

)

eff for validated computer calculations.

The 0.95 K value shall be eff reduced by (1) the applicable 2 sigma statistical uncertainty I

l associated with Monte Carlo calculations and (2) the applicable uncertainties and bias associated with the bench marked calculations.

The basic assumptions used in establishing safe parameters for single units and arrays shall be as follows:

Nuclear safety shall be independent of the degree of moderation between units up to the maxixum credible mist density of 0.1% H 0) 2 (0.001 gm H 0/cc) as demonstrated in Secticns 7.2.1 and 8.7.

2 Criteria used in the choice of fire protection in areas of potential criticality accidents (when moderators are present) shall be justified in writing.

An audit of the existing fires sprinkler system (as shown on dwg. NFM-C-4440) in the building 17/21 complex shall be conducted once a quarter (Sprinkler Heads, Risers, Distribution Lines, and Pumps) to see to it that it has not been modified or added to in any way that would impair its performance 1

or have an effect on calculated mist density.

All proposed changes i

to the fire sprinkler system, that could affect the building 17/21 complex, will be reviewed and approved by the manager NLSA&S for their effect on mist density, before such changes are implemented.

l 1

Plastic bags which are placed around the fuel assembly shall be left open at the bottom at all times including the period in which the assembly is in storage or which the assembly is being shipped to the reactor site.

l Combustible materials in the area shall be minimized at all times.

I License No. SNM-1067, Docket 70-1100 Rev.0 Date: 7/24/87 Page: I.4-7A l

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1)

A 19 x 34 array of assemblies was conservatively l

modeled at a 9.75 inch center-to-center spacing of fuel assemblies within the double rows. The actual average minimum center to center distance within the fuel storage racks is 10 inches.

The distance between rows of fuel assemblies within any given double rack is 35 inches center-to-center while the aisle between the double racks is 37 inches (center-to-center).

This calculational array effectively brings the 25 additional assemblies closer together and provides greater interaction with the 440 assemblies in the storage area than is actually possible.

The calculational array thus contains 646 assemblies while the maximum number in the room is limited to 465.

(See Appendix B-1, drawing No. NFM-E-4229, " Criticality l

Model Fuel Assembly Storage Room."

By squaring off the racks and totaling the number of fuel assemblies the number 646 is arrived at).

i i

2)

All steel construction material was neglected.

3)

The water mist density has been calculated to be 0.000075 grams per cubic centimeter (see section 8.7).

For conservatism a water-mist density of 0.001 grams per cubic centimeter was assumed to be in and around l

l the fuel assemblies in the storage array. (This is a factor of about 13 times higher than the mist density calculated in section 8.7 or about 17 times higher than the mist density calculated in Appendix D for a single sprinkler head at maximum flow and pressure). A uniform License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-27 4

1 I

a

I water film thickness of 0.094 millimeters (which includes a 15% uncertainty) was assumed on the fuel assembly surface 0

(see section 8.8). This film thickness is for 50 F water, while the minimum ambient temperature is actually higher.

l 4)

One hundred twenty three (123) DLC-16 energy group cross sections were used to calculate the reactivity for an infinite fuel storage array using KENO.

The 123 group was collapsed to 16 groups using XSDRNPM and the reactivity calculated for an infinite fuel storage array.

The resultant reactivities were 1.00158 1 0.00608 and 1.00074 i j

0.00569 for the 123 and 16 groups, respectively.

Since the reactivities are essentially the same within the statistical q

1 uncertainty of KENO the finite fuel storage array was done j

J using 16 energy groups.

4 I

5)

The 16 energy group cross sections were generated using l

1 XSDRNPM for the 8" concrete walls, 16 inch concrete floor, 4 inch concrete ceiling and the external water mist between the fuel assembly array and the ceilings and the walls.

The 16 group cross section sets described above were then l

used in KENO-IV to determine the reactivity of the fuel assembly storage area under the above noted conditions for the most reactive assemblies (the 16 x 16 type with the i

grids being neglected).

Dimensional details of the calculational model and results obtained are shown in j

Figures 8.24 and 8.25.

I The resulting Keff for the finite fuel storage array is l

0.732 1 0.004 (interpolated value) which is well below a

\\

Keff of 0.95.

Using the same methodology additional cases I

were analyzed where the l

l l

i l

o fuel assembly center to center spacing and the water film 1

0 thickness were varied to determine the effect on reactivity.

o A tabulation of Assembly Spacing / Mist Density / Film Thick-ness / Reactivity Values follows:

Assembly Mist Film Reactivity for a c/c Spacing Density Thickness Finite Array 9.75" 0.001 gms/cc 0

0.69575 1 0.00397 0

9.75" 0.001 gms/cc 0.0094 cm 0.732 1 0.004 (see note 1) 9.75" 0.001 gms/cc 0.025 cm 0.77224 1 0.00349 l

9.75" 0.001 gms/cc 0.055 cm 0.89932 1 0.00341 10" 0.001 gms/cc 0

0.69913 1 0.00422 l

10" 0.001 gms/cc 0.055 cm 0.904562 1 0.00367 j

l i

A validation of the methodology used to calculate the reactivity values noted is contained in Appendix C.

\\

The local fire departments have been instructed to use only dry chemical extinguishing methods in the fuel assembly storege room NOTE 1-This is an interpolated value License No. SNM-1067, Docket 70-1100 Rev.0 Date: 7/24/87 Page:

II.8-28 A

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i License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-56 l

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l The material on this page and all other pages up to and including page II.8-78 has been deleted and replaced with material shown on pages II.8-60 through II.8-74.

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License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-59

l Section 8.7 i

COMBUSTION ENGINEERING, INC.

i Windsor, Connecticut i

AN ESTIMATION OF THE WATER VOLUME FRACTION PROVIDED IN THE ASSEMBLY ROOM OF BUILDING NO. 17, WINDSOR FACILITY, COMBUSTION ENGINEERING, INC.

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-60

FACTORY MUTUAL RESEARCH CORPORATION S2148.93 l

l I

ABSTRACT l

i A method is described for estimating the water volume fraction (water l

j discharge density) provided by automatic sprinklers in the Assembly Room of 3

l Building'17 at the Windsor facility of Combustion Engineering, Inc.

Water l

volume fraction in three selected regions in the Assembly Rcom were l

evalucted separately.

The volume fraction was estimated to be about I

l 0.0075% of the space volume in the three selected regions.

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l License No. SNM-1067, Docket 70-1100 Rev.4 Date: 7/24/87 Page:

II.8-61

FACTORY MUTUAL RESEARCH CORPORATION S2148.93 The objective of this project was to estimate the water volume I

fraction in air which can be provided by the sprinkler system in the Assembly Room of Building 17 at the Windsor facility of Combustion Engineering, Inc.

l l

1.

SCOPE OF EST1MATION I

l The estimation was performed exclusively for the sprinkler systems and room configuration shown in Figure 1.

The sprinkler system in Figure 1 is in conformance with the NFPA Standard for Sprinkler Systems.

The system was installed according to the pipe schedule for ordinary hazard occupancy.

The water volume fraction in l

air was estimated separately for Regions A, B,

and C indicated in Figure 1.

These regions are delineated by the walls and dashed lines shown in the figure.

2.

ASSUMPTIONS OF ESTIMATION The estimation was based on the following assumption:

1)

Both the diesel and electrical pumps are running to provide sprinkler water.

2)

The vertical distance from the base of the riser at Building 17 to the elevation of the sprinklers is about 27 ft, which is equivalent to an elevation head difference of 11.7 psi.

3)

The water discharge rate in'a region of interest can be obtained from the water supply test data of Building 17 in conjunction with the Factory Mutual Pipe Schedule Sprinkler System Demand Tables (1).

4)

The pressure drop due to friction loss from the top of the riser to the region of interest can be estimated from the Factory Mutual Pipe Friction Loss Tables (2).

5)

Water drops are homogeneously distributed in the air of the region of interest.

License No. SNM-1067, Docket 70-1100 Rev.4 Date: 7/24/87 Page:

II.8-62

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i FIGURE 1 SCHEMATIC OF SPRINKLER SYSTEM AND ROOM CONFIGURATION OF THE ASSEMBLY ROOM IN BUILDING NO. 17, WINDSOR FACILITY, COKBUSTIOh ENGINEERING, INC.

i License No. SNM-1067, Docket 70-1100 Rev. 3 Date:

7/24/87 Page: 11.8-63 1

1

1 I

i FACTORY MUTL'AL FESEARCH CORPORATION S2148.93 3.

PROCEDURE OF ESTIMATION The procedure used to estimate the water volume fraction in air is I

described sequentially as fo13cws:

1)

Obtain the tabulated water discharge rate from a sprinkler system at the tabulated water pressure at the starting point of the system from the Factory Mutual Pipe Schedule Sprinkler System l

Demand Tables.

In the tables, water discharge rates and water pressures are tabulated such that the water pressure at the end sprinkler in the branch line is 5 psi.

2)

Calculate the actual water discharge rate and the corresponding water pressure from the tabulated values obtained in Procedure 1, based on the water supply test data fog Building 17 (see Figure 2).

For water densities of 0.2 gpm/ft and above, the actual water discharge rate (0 ) and water pressure (P ) are related to 2

2 the tabulated water discharge rate (Q ) and watGr pressure (P )

y y

by (0 /Q )1 85, p jp (y) 1 2

The water pressure drop due to friction loss from the top of the riser to the region of interest is obtained from the Factory Mutual Pipe Friction Loss Tables.

3)

Approximate the actual water pressure at the end sprinkler in the branch line using Eq. (1).

Since the water pressure at the end sprinkler is 5 psi in the tables, the actual water pressure is 2 = 5(Q /Q )l.85 (2)

P 2

1 4)

Take the average of the water pressure at the starting point of the system of interest and the water pressure at the end sprinkler as the average water pressure of the system.

5)

Estimate the volumetric median drop size at the average water pressure of the system.

6)

Calculate the water volume fraction in air for the region of interest based on the water discharge rate, space volume in the region, and average vertical downward velocity of the water drops of median size.

Use the equation:

a er s.

ae me or rop o

rom Ceil / Flood Water Vol. Frac.

=

Space Vol. In Region Below Sprinklers License No. SNM-1067, Docket 70-1100 Rev.4 Date: 7/24/87 Page:

II.8-64 l

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1 License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II. 8-65

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FACTORY MUTUAL RESEARCH COllPORATION S2148.93 4.

CALCULATIONS The estimation of water volume fraction in air was performed separately for Regions A, B, and C shown in Figure 1.

The following calculation procedures for each region are identified by numbers in accordance with those of Section 3.

Region A 1)

From the Factory Mutual Pipe Schedule Sprinkler System Demand Tables for Ordinary Hazard Occupancy, we obtain:

tabulated water discharge rate:

185 gpm tabulated water pressure:

17 l

end sprinkler pressure:

5 psi.

2)

Actual water discharge rate = 446 gpm Actual water pressure (446 gpm/185 gpm)1.85 (17 psi) x

=

j

= 86.6 psi.

Pressure drop along 80 ft (from a to c in Figure 1) of 3-in, pipe (0.219 psi /ft) x (80 ft)

=

= 17.5 psi.

Water pressure at the base of the riser l

= 86.6 psi + 17.5 psi + 11.7 psi

=115.8 psi.

This pressure agrees with the water supply test data for Building 17 in Figure 2.

3)

Actual water pressure at the end sprinkler is 1.85 P=

(5 psi) (446 gpm/185 gpm)

= 25.5 psi.

4)

Average water pressure in Region A (86.6 psi + 25.5 psi)/2

=

= 56.1 psi.

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-66

s l

I FACTORY MUTUAL RESEARCH CORPORATION S2148.93 l

I i

5)

For 1/2-in. sprinklers, the volumetric median drops size at 30 psi is about 0.86 mm (3).

Since the median drop size is inversely proportional to 4

the one-third power of water pressure, the median drop size at 56.1 psi is (0.86 mm) (30 psi /56.1 psi)1/3 j

=

= 0.70 mm.

6)

The dewnward drop velocity is about 11.5 ft/s for drops of 0.7 mm in diameter (3).

The time needed for 0.7-mm drops to fall from the sprinkler to the floor

= 27 ft/11.5 ft/s I

= 2.35 s.

l 1

(446) (0.039) (0.13368) i Therefore, the water =

x 100 volume fraction (27) (30) (39) i 1

= 0.0074%

Region B l

1)

From the tables, obtain:

l l

1 Tabulated water discharge rate = 185 gpm Tabulated water pressure = 17 psi End sprinkler pressure = 5 psi.

2)

Actual water discharge rate = 467 gpm Actual water pressure = 17 (467/185)1.85 pgg

= 94.3 psi.

Pressure drop along 40 ft (from a to b in Figure 1) of a 3-in. pipe

= 0.238 x 40 psi

= 9.50 psi i

Water pressure at the base of the riser

= 94.3 + 9.50 + 11.7 psi

= 115.5 psi.

This agrees with the water supply test data for Building 17, 3)

Actual water pressure at the end sprinkler

=5 (467/185)1.85 psi

= 27.7 psi.

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-67

4 i

l FACTORY MUTUAL RESEARCH CORPORATION

)

S2148.93 l

4)

Average water pressure in Region B (94.3 + 27.7)/2 psi l

=

= 61 psi.

5)

Median drop size at 61 psi

= 0,86 (30/61)/13 pgf

= 0.68 mm.

i 6)

The downward velocity for water drops of 0.68 mm is about 11.5 ft/s.

The time needed for G.68-mm water drops falling from the sprinkle'r to the floor

= 27/11.5 s

= 2.35 s.

(467) (0.039) (0.13368)

The water volume fraction =

x 100 (27) (30) (40)

= 0.0075%.

K 1

J Region C l

l 1)

From the tables, obtain:

f Tabulated water discharge rate = 400 gpm Tabulated water pressure = 17 psi End sprinkler pressure = 5 psi.

2)

Actual water discharge rate = 992 gpi.85 i

Actual water pressure = 17 (992/400) psi t

=91.2 psi.

{

Assume pressure drop sue to friction loss from the base of riser to

}

Region C can be neglected, j

Water pressure at the base of the riser j

i

= 91.2 + 11.7 psi

= 102.9 psi

..i I

This agrees with the water supply test data for Building 17.

j i

3)

Actual water pressure at the end sprinkler l

=5 (992/400)1.85 pgg

= 26.8 psi.

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i License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-68 i

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bA

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I FACTORY MUTUAL RESEARCH CORPORATION S2148.93 4)-

Average water pressure in Region C (91.2 + 26.8)/2 psi

=

59 psi

=

5)

Median drop size at 59 psi 0.86 (30/59) 1/3,,

=

0.69 mm.

=

6)

The downward velocity for water drop of 0.69 mm is about 11.5 ft/s.

The time needed for 0.69 mm water drops falling from the sprinkler to the floor

= 27/11.5 s

= 2.35 s.

(992) (0.039) (0.13368)

{

The water volume fraction =

x 100 (27) (64) (40)

= 0.0075%.

SUMMARY

The water volume fractions in Regions A, B and C in the Assembly Room of Building 17 (see Figure 1) were estimated separately based on the sprinkler system and room configuration illustrated in Figure 1, and the water supply test data shown in Figure 2.

The estimated water volume fractions in air in the above three regions are about 0.0075%.

l License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-69 o

l

FACTORY MUTUAL RFSEARCH CORPORATION S2148.93 1)

Pipe schedule sprinkler system demand tables, Loss Prevention Data Sheets 2-76, The Factory Mutual System.

2)

Pipe friction loss tables, Loss Prevention Data Sheets 2-89, The Factory Mutual System.

3)

You, H.

Z.,

" Sprinkler Drop-Size Measurements, Part II: An Investigation of the Spray Patterns of Selected Commercial Sprinklers with the FMRC PMS Droplet Measuring System," FMRC Technical Report, J.I. OGIE7.RA, 1983.

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License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-70

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SECTION 8.8

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COMBUSTION ENGINEERING, INC.

l

(

WINDSOR, CONNECTICUT AN ESTIMP_ TION OF THE WATER FILM THICKNESS ON FUEL RODS (IN FUEL BUNDLES) DURING A RELEASE OF WATER FROM THE SPRINKLER SYSTEM.

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License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-71 a

l INTRODUCTION The following are the calculations used to determine water film thickness on fuel rods (in fuel bundles) in storage when the storage room sprinkler system is activated.

The following assumptions have been made:

- No effect due to grids in the fuel bundles I

- All tater drops falling on the fuel bundle accumulate at the top of l

the fuel bundles and flow along the fuel rod surfaces.

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- Water distribution is uniform in the fuel bundle.

BASIC INFORMATION Fuel Arrangement (Geometry)

Fuel O.D.

0.382 inches

=

Fuel Pitch =

0.506 inches Flow Rate For Region B of the storage room = 467 gal / min. (See Section 8.7) 2 Area of storage room

= 30 x 40

= 1200 ft Physical Properties at 14.7 psia and 77 F Water Density k

= 62.3 lb/ft3

-5 2

Water Viscosity,LL = 2.0 x 10 lb

-sec/ft y

at 14.7 psia and 50 F Water Density k

= 62.3 lb/ft 3

-5 2

Water Viscosity R = 2.73 x 10 lb

-sec/ft y

Area of A Single Fuel Lattice (0.506)2/144

=

0.00178 ft2 A

=

License No. SNM-1067, Docket 70-1100 Rev.3 Date: 7/24/87 Page:

II.8-72

Clad Perimeter of A Single Fuel Lattice k=

(0.382)/12

= 0.1 ft Water Flow Rate Per Fuel Lattice

-6 467 GPM x 0.13368 FT x 0.00178 ET

= 1.54 x 10 FT 60 El 1200 FT" Ec Formula for Film Thickness For this calculation reference 1 and 2 are used.

b Art}c. 1/3 1

+

im D

E

>7 e 4;x7OF

<ormo mmm

.,o r

e. @m m

wCwM rF*

o

s APPDENIX D

" MIST DENSITY CALCULATION FOR A SINGLE SPRINKLER HEAD" Discharge from a single sprinkler head anywhere in region A, B, or C

[see drawing NFM-C-4440," Layout of sprinkler system in Pellet Shop Annex (Region A) and Fuel Bundle Assembly Room (Regions B & C) in l

building 17].

i Discharge Flow from 1 Sprinkler = 0 = K(P) i Where Q=

Discharge Flow I

K=

Constant for 1/2" Sprinkler Head = 5.6 l

P=

Discharge Pressure at head = 100 psi (assumes max. possible line pressure regardless of sprinkler location).

I l

l 0 = 5.6 (100)l/2 = 56 gal / min (say 60 gal./ min.)

= 60 gal / min. x 1 ft /7.5 gal.

l 3

3 0

= 8 ft / min.

Assembiv Room Ceiline 1

Soriniler Line M

A l

28' 24' Y

l l'

i Assembly Rocn Floor 1

July 24, 1987

s VOLUME OF SPRINKLER FLOW PARABOLOID = V = 1/2 ' F R H Where TJ' =

A constant = 3.14 Radius of spray at floor = 12' l

R

=

Distance from sprinkler head to floor = 28 ft.

H

=

= 1/2 (3.14) (12)2 (28) l i

3 l

V = 6330 ft WATER DROP SIZE FROM 1/2" SPRINKLER HEAD D

D2=-

y 2

Where D

= Unknown water drop size 2

Dy = Known water drop size = 0.86 mm Py = Reference pressure @ known drop size = 30 psi P

= Reference pressure @ unknown drop size = 100 psi 2

(

\\

3

/

(0.86)

D (Drop size @ 100 psi)

=

2 0

j 0.77 mm @ 100 psi 2=

(0.89) (0.86)

D

=

DROP VELOCITY Reference drop velocity for 1 nu drop = 13 ft/sec Drop Velocity @ 0.77 mm = 0.77 x 13 = 10 ft/sec.

TIME FOR DROP TO REACH FLOOR 7' = Drop time from 2 8 ft -

2.8 sec.

=

WATER VOLUME FRACTION 0T Water Volume Fraction =

y Where Q = Discharge Sprinkler Flow in ft / min.

T = Time for Drop to go from Sprinkler to Floor V = Paraboloid Volume (8)

) W 60)

Water Volume Fraction =

Water Volume Fraction = 0.000059 Grams /cc Supplied by FMIC 2

July 24, 1987

1 8

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