ML20205F460
| ML20205F460 | |
| Person / Time | |
|---|---|
| Site: | 07001100 |
| Issue date: | 03/18/1987 |
| From: | Sheeran R ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 27976, NUDOCS 8703310166 | |
| Download: ML20205F460 (26) | |
Text
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, &&q'5 Ml00 RETURN TO 393-53 RECEIVED 3
2 MAR 19190 )!
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esasBUSTION ENGINEERING C $$P
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pa satimT\\q March 18, 1987
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A W
License SNM-1067
~ ~ ~
U.S. Nuclear Regulatory Commission 4
Washington, DC 20555 c'
Docxtrto Usue 9
Attention:
Mr. W. T. Crowe, Acting Chief y'2 Uranium Fuel Licensing Branch
. Q I 9lS87 ) T Division of Fuel Cycle and Material Safety, NMSS,? Q QWL sfc nuss Subj ec t:
Changes to SNM-1067
/
Reference:
Letter from H. V. Lichtenberger, CE, to W. T.- Crowe, NRC, Cl' dated December 17, 1986
Dear Mr. Crowe:
/
On February 19, 1987, R. Klotz and I met with N. Ketgach of your organ-ization to discuss the subject license changes attached to the referenced
' letter. At the meeting it was agreed that certain additional changes would be made. Accordingly, a new submittal, containing the agreed on changes, is attached for your review and approval.
Please note that only certain pages in the referenced submittal were changed and these have been indicated by an asterisk.
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U!d L J
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. ~. -. - -__
Power Syste:ns 1000 Prospect Hill Road (203) 688-1911 Comtxastion Engineering, Inc.
Post Office Box 500 Telex: 99297 8703310166 870318 PDR ADOCK 07001100 C
g-r h
i U. S. Nuclear Regulatory Commission License SNM-1067 r:
'Mr. W. T. Crowe' Docket 70-1100 i
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12/05/86 Also included are Appendix C, " Validation of Criticality Methods for Calculating the Effective Multiplication Factor Under Low Hydrogen Density Moderation Conditions," and Appendix D, " Mist Density Calculation for Single Sprinkler."
These appendices will become part of Section II of the SNM-1067 license and have been included, as such, in the Table of Contents.
Very truly yours, 3
l A_1 _ _ -
R. E. Sheeran Manager, Nuclear Licensing, Saf ety, Accountability and Security RES/lyc Attachment
PART II SAFETY DEMONSTRATION (C5nt'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 8.1 UO2 Powder Processing 8.2 Scrap Recycle 8.3 Storage and Transfer 8.4 Pre-Treatment of Low Level Liquid Wastes 8.5 Rod Loading and Assembly Fabrication 8.6 High Enriched Uranium 8.7 Maximum Moderator Density in Air From Automatic 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 Annual Report APPENDIX C:
Validation of Criticality Methods for Calculating the Effective Multiplication Factor Under Low Hydrogen Density Moderation Conditions APPENDIX D:
Mist Density Evaluation for a Single Sprinkler Head Figure B-1:
Floor Plan Building #17 License No. SNM-1067, Docket 70-1100 Rev. 3 Date:
12/05/86 Page: 3
4.2.4 Snf^ty Margin, - 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 Cylinder Diameter 1.1 Slab Thickness 1.2 These values shall be further reduced where necessary to assure maximum fraction critical values of 0.4 for 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.
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 uncertainties and bias.
A maximum Keff of 0.95 with the above described uncertainties shall apply for calculations performed for a mist condition.
The basic assumptions used in establishing safe parameters for single units and arrays shall be as follows:
The possibility of accumulation of fissile materials in inaccessible locations shall be minimized.
Nuclear safety shall be dependent on the degree of moderation within the process unit. Additional moderating materials, when considered to be credible, will be included in the analysis.
Nuclear safety shall be independent of the degree of License No. SNM-1067, Docket 70-1100 Rev.3 Date: 12/5/86 Page: I.4-6
todsratien betw:cn units up to tha anxitum cr:dible miet-0-
density of 0.1% H2O (.001 gm H20/cc) as demonstrated in sections 7.2.1 and 8.7.
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 fire sprinkler system.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 or have an effect on calculated mist density.
All proposed changes 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 they are implemented..
Nuclear safety shall be independent of neutron reflector thickness for the reflector of interest.
Optimum conditions (limiting case) of water moderation 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, Docke t 70-1100 Rev.3 Date: 12/05/86 Page: I.4-7
8.24)..
0 1)
A 19 x 34'crrty cf cec;mblics was cencsrvativaly c
modeled at a 9.75 inch. center-to-center spacing of fuel assemblies within the double rows. The actual average O
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 Model Fuel Assembly Storage Room."
By squaring off the racks and totaling the number of fuel assemblies the number 646 is arrived at).
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 l
per cubic centimeter was assumed to be in and around 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: 12/5/86 Page:
II.8-27
w; tar filn thickn:co of 0.083 tillimetarc wac c cumed en tha fual costmbly curfsca (ces cection 8.8). This film thicknsse is for 50 F' water, while the minimum ambient temperature is actually higher.
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 1 0.00569 for the 123 and 16 groups, respectively.
Since the reactivities are essentially the same within the statistical uncertainty of KENO the finite fuel storage array was done using 16 energy groups.
5)
The 16 energy group cross sections were generated using 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.
o The 16 group cross section sets described above were then 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 grids being neglected).
Dimensional details of the calculational model and results obtained are shown in Figures 8.24 and 8.25.
The resulting Keff for the finite fuel storage array is 0.715 1 0.004 which is well below a Keff of 0.95.
Using the same methodology additional cases were analyzed where the License No. SNM-1067, Docket 70-1100 Rev.3 Date: 12/5/86 Page:
II.8-28
.fu21' cca mbly cantar to.cnntar ep:cing cnd th:a w ter fil:e
.. o -'
c
-thicknaco wera varied to datsrminn the offcct on r:Ectivity.
O A tabulation of Assembly Spacing / Mist Density / Film Thick-O 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 9.75" 0.001 gms/cc 0.025 cm 0.77224 1 0.00349 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 10" 0.001 gms/cc 0.055 cm 0.904562 1 0.00367 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 storage room l
l License No. SNM-1067, Docket 70-1100 Rev.0 Date: 12/5/86 Page:
II.8-28 A l
.s FACTORY MUTUAL RESEARCH CORPORATION S2148.93 ABSTRACT III o
A method is described for estimating the water volume fraction (water discharge density) provided by automatic sprinklers in the Assembly Room of Building 17 at the Windsor facility of Combustion Engineering, Inc.
W ter volume fraction in three selected regions in the Assembly Room were evaluated separately.
The volume fraction was estimated to be about 0.0075% of the space volume in the three selected regions.
I (1) See page II.8-89A for an independent assessment of FNMC's Methodology for calculating mist density.
i l
License No. SNM-1067, Docket 70-1100 Rev.1 Date: 12/5/86 Page:
II.8-80
g f
o e
e c
o.
. (,
l 1
0 O
SCALE: 1 CM = 5 FT-0 t
=
X REGION A ll 4
0 o
l o
I 64 FT f=
-o w
l i
k C
C o--O-- C----C 0
W I
=X l
REGION C
=
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l O
t l
"e REGION B l
c 0
0 0
o--<:
l S
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FIGURE 1 SCHEMATIC OF SPRINKLER SYSTEM AND ROOM CONFIGURATION OF THE I
ASSEMBLY ROOM IN BUILDING NO. 17, WINDSOR FACILITY, COMBUSTION ENGINEERING, INC.
l l
l License No. SNM-1067, Docket 70-1100 Rev.1 Date: 12/5/86 Page:
II.8-82
T,5Mh Factory Mutual Research
,',.o,',ggifl' vid'ac' 7"' api
'58 a
Norwood, Massachusetts 02062 March 6, 1987 Telephone (617) 762-4300 Telex 92-4415 Mr. Robert E. Sheeran
. Combustion Engineering P.O. Box 500 Windsor, CT 06095
Subject:
Project S2148.93 Dr. Hong-Zeng You Gentlemen:
The subject report was prepared by Dr. Hong-Zen You and it is entitled "An Estimation of Water Volume Fraction Provided by Automatic Sprinklers in the Assembly Room of Building No. 17, Windsor Facility, Combustion Engineering, Inc.
We understand that an inquiry has been received from the U.S. Nuclear Regulatory Commission regarding Quality Assurance procedures associated with the preparation of this report.
You and they must recognize that this project and others associated with this general subject are at the frontiers of automatic sprinkler research. As such, there is no documentation or " cookbook" procedures available. What is available is that Dr. You is Factory Mutual Research Corporation's expert on the subject and that he holds a PhD from Penn State University in Mechanical Engineering, and has been a Senior Research Scientist for approximately six years. His report has been reviewed by myself in my capacity as Engineering Manager of MAERP Reinsurance Association and by Mr. Wayne Holmes of American Nuclear Insurers and we jointly recommend the report as
" State-of-the-Art."
Very truly ou s,;
)
/
i
). E. Weldon, P.E.
ineering Specialist GEW/ep cc:
Mr. Wayne Holmes, American Nuclear Insurers GEW License No. SNM-1067, Docket 70-1100 Rev. O Date:
12/05/86 Page:
II.8-89A
APPENDIX C Validation of Criticality Methods for Calculating the Effective Multiplication Factor Under-Low Hydrogen Density Moderation Conditions By Mohamed A. Elmaghrabi Consulting Physicist Approved by:
R.
J.
Klotz Principal Consulting Scientist l
l l
l r
I 1
March 12, 1987
SUMMARY
Critical experiments for the interposition of hydrogenous compounds between four assemblies of 18 x 18 U(4.75%)
0, rods were reported in Reference 1.
The purpose of this report is t5 define and validate a detailed calculational model which would be suitable for MONTE CARLO calculations to design and license fuel storage under mist (low hydrogen density) conditions.
'Results of this analysis are as follows:
1.
A calculational model based on a homogenized fuel assembly representation and 16 neutron energy groups which is suitable for use in KENO analyses to design and license fuel storage under mist conditions has been defined and verified against critical experiments.
2.
This model yields multiplication factors for critical experiments which are comparable to those obtained by other methods (APPOLLO-MORET) used-in Reference 1.
ABSTRACT The objective of this task is the development and validation of an analytical model for use in the design and licensing of Fuel Storage under mist conditions.
Combustion Engineering, Inc.
has performed analyses using the KENO computer code, which show that neutron multiplication factors obtained for the case of interposition of low hydrogen density compounds between four 18 x 18 fuel assemblies, are in good agreement with other calculations models and the experiments.
The bias between prediction and measurement is reasonable and quantifiable over the range of experimental parameters.
March 12, 1987
CONTENTS Section Page 1.
INTRODUCTION 1
2.
BENCIH4 ARKS 2,3 3.
MODEL EVALUATION 4,5 3.1 Computer Codes 3.2 Cross-Section Generation 3.3 KENO IV Models 4.
CONCLUSIONS 6
5.
REFERENCES 7
6.
Figure I 8
i March 12, 1987 i
,-,,_,-,-..m--
.o Section I INTRODUCTION This task has a.its primary objective the development and validation of an analytical model for use in the criticality analysis of fuel storage under mist (low hydrogen density) conditions.
Experimental criticality data were measured on four assemblies ofil8 x 18 (U4.75%)
0, rods at 13.5 mm square pitch with variable low hydrogen density compoQnds interposed between them.
The experimental data and subsequent analyses of these experiments were reported in Reference 1.
The analyses were carried out using the APPOLLO-MORET computer codes in 16 neutron energy groups.
It was the objective of this task to define an analytical model for design and licensing of fuel storage under mist conditions.
1 March 12, 1987
Section 2 BENCHMARKS Critical experiments on the interposition of low hydrogen density materials between four assemblies of 18 x 18 U(4.75%) 0 r ds at 13.5 2
mm square pitch, were performed by the department of Nuclear Safety of the French Atomic Energy Commission.(Reference 1).
.The assemblies were arranged in a 2 x 2 array in the experimental tank.
A mobile device enabled them to move along the x and y axes in the horizontal plane. (Figure 1).
Cross-shaped watertight containers in various thickness (25.5 to 100 mm) with 3 mm thick aluminum walls are then interpositioned between the four assemblies and successively filled with air and various hydrogenous compounds which are:
1.
Air 2.
Expanded polystyrene (C "8 n 8
3.
Polyethylene power (CH )n 2
4.
Polyethylene balls (CH )n 2
5.
Wtter Water is then introduced into the bottom of the tank and the critical height determined for each configuration.
The resulting values are
-summarized in Table 1.
The calculated results shown in Table 1 were performed by the criticality service of the French Atomic Energy Commission.
Two-step calculations were performed using the APPOLLO and MORET codes:
1.
Calculation of the neutron constant by APPOLLO.
2.
Calculation of the K by MORET.
eff The APPOLLO code is used with the " transport" option to calculate the 2
material buckling B and the K of an infinite lattice of rods in its ambient medium (waterorafbfandtodeterminethemacroscopic l
cross-section of the homogenized lattice based on the 16 energy groups of Hansen and Roach.
The cross-section library used in the code is ENDF/B-III based and consists of 99 groups (52 fast and 47 thermal groups).
The MORET code is a Monte Carlo code that calculates the K of any configuration.
The collisions are treated isotropically bOffanico-tropy is taken into account by means of the transport corrections.
2 March 12, 1987 I
TABLE 1 L
Results of Experiments and Benchmark Calculations in the Case of Interposition of Hydrogenous Compounds Between Four Assemblies i
of 18 x 18 U(4.75%) 0 Rods at 13.5mm Square Pitch 2
i Experimental Results Compounds Calculated Results Concentration Water Critical Densigy Hydrogen Height APOLLO-MORET a
(cm)
Nature (g/cm )
(g/cm )
(mm) k,ff i2e 0
1.
Water 1.0 0.1119 238 i 0.6 1.010 0.011 l
2.
Box + air 0
0 290.3 0.9 1.005 1 0.010 3.
Box + (C H )n 0.0323 0.0025 286.1.
0.8 0.987 1 0.010 8
2.5 4.
Box + powdVr (CH 7)n 0.2879 0.0414 269.8 i 0.6 5.
Box + balls (CH 7n 0.5540 0.0800 255.4 0.6 0.995 1 0.010 2
6.
Box + water 1.0 0.1119 256.6 0.7 7.
Water 1.0 0.1119 244.8 0.6 1.006 1 0.011' 8.
box + air 0
0 344.8 i 0.7 9.
Box + (C H )n 0.0262 0.0020 343.9 i 0.8 8
5.0 10.
Box + powdVr (CH )n 0.3335 0.0480 301.6 1 0.6 11.
Box + balls (CH n 0.5796 0.0833 307.3 i 0.8 2
12.
Box + water 1.0 0.1119 327.8 0.8 13.
Water 1.0 0.1119 314.7 t 0.6 1.000 i 0.012 14.
Box + air 0
0 460.8 0.7 0.996 1 0.010 15.
Box + (C H )n 0.0288 0.0022 456.2 ! 0.8 0.987 1 0.010 8
10.0 16.
Box + powdVr (CH )n 0.3216 0.0464 420.5 0.6 1.011 1 0.012 7
17.
Box + balls (CH 7n 0.5680 0.0816 499.4 t 0.6 1.010 1 0.010 2
18.
Box + water 1.0 0.1119 641.2 0.9 19.
Water 1.0 0.1119 643.4 i 0.8
" The symbol a is the value of the gap width between the assemblies, thus it is the value of cross-shaped box width.
The actual thickness of hydrogenous compounds is a (H) = a - 0.6 cm.
'~
Section 3 MODEL EVALUATION
- 3. l-Computer Codes The computer codes employed in this evaluation were KENO IV (2),
NITAWL, and XSDRNPM (5).
The reference microscopic cross section library was the 123 group super - XSDRN library, DLC-16 (6),
which was obtained from the Radiation Shielding Information Center.
3.2 Cross b.
n Generation The NITAWL h XSDRNPM Codes (5) were used to generate 16 neutron energy group u oss sections.
NITAWL was used to generate self shielded 123 group cross sections from the 123 group super-XSDRN library (DLC-16).
The resulting working library is then collapsed into homogenized 16 energy group library in a typical fuel pin cell environment using XSDRNPM.'
XSDRNPM is also used to obtain separate 16 group cross section sets for structural and external moderators.
3.3 KENO IV Models Homogenized fuel pin representation was utilized in the assembly interior.
The cross shaped box, the outside moderator, tank wall, lattic grid, fuel pin lower plug, bottom plate and support plate were all explicitly represented.
The structure details are shown in Figure 1 (which were obtained from Reference 1).
Table 2 summarizes the multiplication factors computed by KENO IV for 6 critical experiments together with the reported K values eff as calculated in Reference 1 using the APPOLLO-MORET approach.
Among the five critical experiments which are analyzed only 3 had calculated APPOLLO-MORET results.
For these three experiments the KENO IV, MORET APPOLLO and experimental results agree within less than 0.5% Keff*
4 March 12, 1987
4' TABLE 2 KENO IV Results for a Gap Width of 2.5 cm Between Assemblies Hydrogen Degsity Keff Description gm/cm KENO IV APPOLLO-MORET Aluminum Box
+ Air 0.0 0.99641 1 0.00407 1.005 1 010 Aluminum Box
' + (C N ) n 0.0025 0.99913 1 0.00384
'0.987 1 010 88 Aluminum Box
+ powder (CH )n 0.0414 1.01567 1 0.00378 2
Aluminum Box
+ Water 0.1119 1.02362 1 0.00362
- Water (No Aluminum Box) 0.1119 0.99775 1 0.00391 1.006 1 011 5
March 12, 1987
.I Section 4 CONCLUSIONS-A'16. neutron energy group. calculation model which employs a homogenized fuel assembly representation has been defined and. verified against critical experiments..This model gives. multiplication factors which are' comparable to those obtained using the APPOLLO-MORET
.approacn.
6 March 12, 1987
~
Section 5 REFERENCES 1.
Dissolution and Storage Experiment with 4.75 wt% U(235) enriched UO Rods, J. C. Manarandre et al, (Nuclear Technology Vol. 50, 2
September 1980, Page 148.
2.
L. M.
Petrie and N. F. Cross, KENO IV, An Improved MONTE CARLO Criticality Program, ORNL-2938, November 1975.
3.
W. R. Cable, 123-Group Neutron Cross Section Data Generated from ENDF/B-II Data for Use in the XSDRN Discrete Ordinates Spectral Averaging Code, DLB-16, Radiation Shielding Information Center, 1971.
4.
Scale:
A Modular Code System for Performing Standardized Computer Analysis for Licensing Evaluation - Book II, NUREG/CR-0200.
5.
N. M.
Green et al, AMPX:
A Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B, ORNL/
TM-3706, March 1976.
6.
123-Group Neutron Cross Section in CCC-123/XSDRN Format Based on ENDF/B-II Data, DLB-16/COBB, Radiation Shielding Information Center.
(These cross sections may be the same as in Reference 3, existing documentation received from RSIC does not allow a definitive conclusion).
7.
A. M.
Hathout et al, Validation of three Cross-Section Libraries Used With the Scale System for Criticality Safety Analysis,
- NUREG/CR-1917, June 1981.
l l
l l
7 March 12, 1987
m.
--.="%.-=.--=e-..__
z b
Plan view E
Half end view
>m N
>200 a
+
o r-o i,
,-- Fuel rods Box o
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Water 200 m
4 e
>200
>200 2
- p. -
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Water 2.5 o
.f Box wall
/1 E
x n
(AI)
% Lattice grid (stainless steel)
/
v
% ower plug L
3,,
_ _ _ _ _ _ -/.
J s
w wu/4_WN\\WNN/
4 M
_o 7-a 0
g g
Bottom plate (stainless steel) 2 Dimensions in millimetres.
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Support plate (stainless steel) cu su n'
..p2p 3
~ro
~g Figure 1
~a
--a.
._.w.,
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 building 17].
Discharge Flow from 1 Sprinkler = Q = K(P)
Where Q=
Discharge Flow K =- Constant for 1/2" Sprinkler Head = 5.6 P=
Discharge Pressure at head = 100 psi (assumes max. possib3 c line pressure regardless of sprinkler location).
O = 5.6 (100)1/2 = 56 gal / min (say 60 gal./ min.)
3
= 60 gal / min. x1 ft /7.5 gal.
3 Q
= 8 ft / min.
Assembly Room Ceilina MprinklerHead S
Sorinkler Line h
28' 24' y
/<
, \\ Assembly Room Floor 1
March 12, 1987
VOLUME OF SPRINK2.ER FLOW PARABOLOID = V = 1/2 ~7T-R H Where 77~ = A constant = 3.14 Radius of spray at floor = 12' R
=
Distance from sprinkler head to floor = 28 ft.
H
=
V = 1/2 (3.14) (12)2 (28) 3 V = 6330 ft WATER DROP SIZE FROM 1/2" SPRINKLER HEAD f p.
1 1/3 D
D 2 =I4 p12/
1 Where D
= Unknown water drop size 2
D
= Known water drop size = 0.86 mm y
Py = Reference pressure @ known drop size = 30 psi P2 = Reference pressure @ unknown drop size = 100 psi 3
/
D (Drop size @ 100 psi)
(0.86)
=
2 0
2= (0.89)
(0. 8 6) = 0.77 mm @ 100 psi D
DROP VELOCITY Reference drop velocity for 1 mm drop = 13 ft/sec Drop Velocity @ 0.77 mm = 0.77 x 13 = 10 ft/sec.
TIME FOR DROP TO REACH FLOOR T = Drop time from 28ft = 28f t = 2. 8 sec.
10ft WATER VOLUME FRACTION 0
Water Volume Fraction =
Where Q = Discharge Sprinkler Flow in ft / min.
T = Time for Drop to go from Sprinkler to Floor V = Paraboloid Volume I8I I2 8 (1/60)
Water Volume Fraction =
j Water Volume Fraction = 0.000059 Grams /cc Supplied by FMIC 2
March 12, 1987
I o
104'
.i 40' S'
30' m
O' 8'
I S'-
TYP TYP TYP go,e n
i U
t t
_ + _____e-__---e
-- -e t
10' REGION A 3
- 6. SPRINKLER SYSTEM SUPPLIED BY 250,000
-e GALLON ELEVATED STORAGE TANK.
--____e._____e I
PRESSURE ON SYSTEM IS MAINTAINED BY g--
l A MARATHON ELECTRIC PUMP (MODEL l
10.:
TO445TOO2G1 BACKED UP BY A GM OIESEL 1
PUMP IMODEL PTA-IS0-503 Ato TWO l
0 F
MAX
-_.---._----a
-e o 100 PSI MAX 5,---SIGNIFIES SEPARAT MN 2ONE l
(SEE NOTE 6)
BETWEEN SPRINKLER LINES I
g,
- - ~ ' -'j /'
4.----- S I GN i f I ES SPR I NKLER
}
DISTRIBUTION LINE.
~
^
7' e
TYP 3.
SIGNIFIES MAIN W ATER FEED LINE. E O'
8' 6
8 1
.----e-----+-----u---+ - - - - + -
-a-----+-----
S*-
r TYP TYP TYP
- 2. ALL SPRIPELERS ARE RELIABLE 10'I 1
AUTOMATIC, MODEL G, 1/2" STAPOARD
)
j ORIFICE, UPRIGHT UNIT.
M REGION C 13
~
~
- 1. UNLESS OTHERWISE SPECIFIED, ALL OIMENSIONS ARE IN FT.
,o REGION B 10' NFM-C-4440
'4'.
10'
,.y T,P I
I I
i3 10'!
7'
~~*"
a TYP t
,.. a
- c. j i
i l
I C.
- _i 4* MAIN 2" MAIN 8" MAIN
[ 500 GPM MAy 300 GPM MAX 1000 GPM MAX 6 100 PSI MAX e 100 PSI MAX
- 100 PSI MAX p
(SEE NOTE G)
(SEE NOTE 63 (SEE NOTE 61 1
mnen asEL.italw 3ll3/d 7 Mk'%.,-tres "SEs O
YL I MS ;g. i.G
. ::GHM."ITuG S.gg CUST0h(R TITLE LAYOUT OF SPRINKLER SYSTEM NUCLEAR FUELS IN PELLET SHOP ANNEX MANUFACTURING (REGION A) AND RKL eteCLE WINOSOR ASSEMBLY ROOM (REGIONS S & Cl IN BUILDING 17 j-.
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