ML17346B249
| ML17346B249 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 10/10/1986 |
| From: | Hoskins K, Knuckles E, Poteralski D FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17346B248 | List: |
| References | |
| NUDOCS 8610280091 | |
| Download: ML17346B249 (57) | |
Text
FLORIDA POWER 6 LIGHT EVALUATION OF THE BROOKHAVEN NATIONAL LABORATORY 15x15 LATTICE STANDARD PROBLEM Prepared By: Kevin C. Hoskins
- Engineer, Core Physics Date:
D' Reviewed By:
Ed Knuckles Supervisor, Core Physics Approved By:
D.C. Poteralski
- Manager, Nuclear Fuel Technology Date: P
/6' Date:
>> >> Z4 8&i02800'P i 861 02i PDR ADOCK 05000250 )'
PDR ~
~
I
~ I
Department of Nuclear Energy BROOKHAVEN NATIONALLABORATORY ASSOCIATED UNIVERSITIES, INC.
Upton, Long Island, New York 11973 (516) 282'595 FTS 666'ugust 8,
1986 Mr. Edward Knuckles Fuel Resources Florida Power and Light P.O.
Box 029100 Miami, Florida 33102
Dear Mr. Knuckles:
As you requested, I have enclosed a copy of the BNL 15x15 W type fuel assembly Standard Problem.
As indicated in the definition, the analysis of "the Standard Problem requires an assembly depletion calculation together with a series of reactivity defect calculations.
The problem includes a
burnable-poison rod assembly, and both rodded and unrodded assemblies.
The burnable-poison rod and rodded assemblies include strong local absorbers
- and, as we discussed, are not an appropriate application of the methods presently being reviewed.
If you have any questions concerning the modeling or execution of this
- problem, please do not hesitate to contact us.
Sincerely, JFC/lr Encs.
/
.F. Carew, Group Leader Core Performance Group cc:
J.
G.
Guppy w/o W. Y. Kato w/o L. Lois M. S. Dunenfeld
FUEL ASSEMBLY STANDARD PROBLEM The standard problem is to be calculated in two dimensions, in an iterated-,
source mode using reflecting boundary conditions in the horizontal plane ne-glecting axial leakage.
The following series of assembly depletion and re-activity defect calculations are to be calculated.
I.
DEPLETION CALCULATIONS Provide the following edited quantities for an assembly with and without burnable poison rods at BOL, 500,
- 5000, 10000,
- 20000, 30000 and 40000 MWD/MT*.
For the controlled assembly only provide the pin powers (item-l), reaction rates (item-3) and assembly characteristics (item-4) at BOL and 30,000 MWD/MT.
1.
Relative pin powers 2.
Assembly yolume averaged fuel pellet isotopics;
- U235, U238,
- Pu239, Pu~"
Pu 4
Pu242 and calculated fission product densities
[atom/barn-cm] at 500 and 40,000 MWD/MT 3.
Assembly total reaction rates (A-absorption, F-fission) a.
Fuel u235 (A)
U235 (F)
U238 (A)
U238 (F)
Pu239 (A)
Pu239 (F) b.
Clad (A) c.
Burnable Poison (A) d.
Water (A) e.
Control Rod (A) 4.
Assembly Characteristics Pu240 (A)
Pu240 (F)
Pu241 (A)
Pu241 (F
Pu242 (A)
Pu242 (F) a.
k
- Infinite Multiplication Factor b.
M~ - Migration Area
[cm ]
c.
BM - Material Buckling [cm ]
d.
B - Delayed Neutron Fraction e.
Two-Group Inverse Neutron Velocityi'sec/cm]
5.
Two-Group Collapsed Assembly Averaged Cross Sectionsi'
[cm],)a[em
], fr[em ],
v)ffcm- ], ~Q [watt/cm],)f[cm" ]
These are editing points and do not necessarily correspond to the depletion steps.
t Thermal breakpoint assumed at 0 625 [eV]
May 8, 1985
FUEL ASSEMBLY STANDARD PROBLEM II~
REACTIVITY DEFECT CALCULATIONS Provide the following reactivity defects (Xd k/k) for an assembly with and without burnable poison rods at BOL and EOL (30,000 'Mwd/MT):
UNPERTURBED PERTURBED REACTIVITY DEFECT
{gb, k/k
- CASEt CASE 1.
Fuel TemPerature (Tfuel
)
fuel Tbase moderator 2.
Moderator Temperature (Tmoderator) 3.
Moderator 8 Fuel Temperaturett (TModerator
& TFuel) 4.
Moderator
& Fuel Temperaturett (TModerator
& TFuel) base moderator base fuel base moderator base fuel 68oF 68'F 300oF 300'F 5.
Boron Concentration (Nboron) base boron 0 ppm 6.
Xenon Concentration (Nxenon) 7.
Control Rod Equi 1 ibrium Unrodded 0
Rodded f11 f1 for each state-point.
t Unperturbed parameters are at their base values indicated in the Standard Problem definition.
g In the case of the W (17xl7) assemb'ly only the unpoisoned assembly is required.
tt Pressure is to be maintained at base value.
TABLE-1. TYPE-1 FUEL ASSEMBLY DATA 15 x 15 W Type Fuel Assembly 4
1 1
111 1113 31111 113113 1111111 11111111 1 - Fuel Rod 2 - Burnable Poi son Rod (BPR) 3 - Guide Thimble 4 - Instrument Thimble Note:
1.
For an unrodded or unpoi soned case replace all BPRs (2) with guide thimbles (3).
2.
For a rodded case control rods are inserted in guide thimbles (3).
2.
Fuel Assembl Data Rod ar ray Fuel rods per assembly Rod pitch (in)P Assembly pitch (in)**
Assembly length (in)
Active fuel length (in)
Number of spacer grids~
Composition of space grid Weight of spacer grids (lb)
Number of guide thimbles Number of instrument thimbles 15 x15 204
- 0. 563 8.466 x 8.466 151. 0 144.0 7
83'A Inconel
- 718, 175 Stainless Steel
- 15. 5 20 1
All dimensions are given at cold (68'F) conditions.
i'even in active length.
- Center to center assembly pitch.
TABLE-1. TYPE-1 FUEL ASSEMBLY DATA (Cont.)
15 x 15 W Type Fuel Assembly 3.
Fuel Rod Data Clad O.D. (in)
Clad thickness (in)
Diametral gap (in)
Clad mater ial 0.422 0.0243 0.0075 Zi real oy-4 4.
Fuel Pellet Data Haterial Density (5 of theoretical)
Enrichment (w/o)
Diameter (in)
U02 - Undished 95 2.25 0.3659 5.
Guide Thimbles and Instrument Thimble Data Number of guide thimbles Number of instrument thimbles Composition of thimbles Guide Thimble O.D. (in)
Guide Thimble I.D. (in)
Instrument Thimble O.D. (in)
Instrument Thimble I.D. (in) 20 1
Zi real oy-4
- 0. 545
- 0. 515
- 0. 545
- 0. 515 6.
Eontrol Rod Data Neutron absorber (w/o)
Absorber diameter (in)
Absorber density (lb/in3)
Cladding material Cl ad O.D.
( i n)
Clad thickness (in)
Number of control rods 5$ Cd, 155 In, 80% Ag 0.347 0.367 304 Stainless Steel 0.445 0.019 20
INTRODUCTION TO ANALYSIS RESULTS This transmittal contains the results of FPL's evaluation of Brookhaven's 15xl5 lattice Standard Problem using FPL's CHEETAH/PDQ methodology.
As agreed, the analysis was performed only for the unpoisoned/unrodded lattice.
Due to the structure of FPL's CHEETAH/PDQ methodology, some of the data provided is slightly different from that requested:
1)
Instead of providing absorption rates for all of the water in the
- assembly, absorption rates for the guide and instrumentation thimbles are given.
This modification was agreed-to previously.
2)
Reactivity defect data was generated using CHEETAH only.
It is FPL's position that the pincell CHEETAH and unit-assembly CHEETAH/PDQ agree closely on these calculations, and thus CHEETAH data is sufficient for the calculation.
3)
Both CHEETAH and CHEETAH/PDQ isotopics were provided for the conditions requested.
It is felt that the CHEETAH data is slightly more accurate because FPL's PDQ uses simplified isotopic chains, which causes a
small but acceptable difference in Pu isotopic calculations.
I t
~
~
A 4)
CHEETAH does not edit information for the fast group inverse neutron velocity; code modifications would be required to edit this value.
Therefore, only thermal group inverse velocities are provided.
Inverse neutron velocity data has never been used explicitly in PPI" s physics calculations, and its need is not apparent.
Therefore, it is felt that CHEETAH's 'shortcoming'n this respect is of little consequence.
5)
CHEETAH does not edit delayed neutron fractions, and of
- course, PDQ does not calculate them.
The delayed neutron data was generated by hand using fission rates from PDQ and documented isotope-dependent delayed neutron fractions.
If you have any questions on the attached
- data, please contact E. Knuckles (305) 552-3444 or K. Hoskins (305) 552-3437.
m 2
W
BNL STANDARD PROBLEM ANALYSIS TABLE OF CONTENTS Ficiures Title Relative Pin Powers 9 150 MWD/MTU Relative Pin Powers 9 500 MWD/MTU.
, 3 Relative Pin Powers 9 5000 MWD/MTU....................
Relative Pin Powers 9 10000 MWD/MTU.
Relative Pin Powers 9 20000 MWD/MTU.... ~
~
~
~
~
~
~
~
~
~
~
~
~
Relative Pin Powers 6 30000 MWD/MTU...................
Relative Pin Powers 8 40000 MWD/MTU...................
Tables Title CHEETAH vs.
CHEETAH/PDQ Koo vs. Burnup................
Assembly Volume-Averaged Isotopics.......
Assembly Total Reaction Rates 150 MWD/MTU.............
Assembly Total Reaction Rates 500 MWD/MTU....
i Assembly Total Reaction Rates 5000 MWD/MTU...
Assembly Total Reaction Rates 10000 MWD/MTU...........
Assembly Total Reaction Rates 20000 MWD/MTU...........
Assembly total Reaction Rates 30000 MWD/MTU...........
Assembly Total Reaction Rates 40000 MWD/MTU...........
10 12 Guide 6 Instrument Tube Absorption Rates..'............
Assembly Characteristics (koo, M,
B
, ~,etc.........
2 2
Delayed Neutron Fractions 150 6 500 MWD/MTU...........
13 Delayed Neutron Fractions 5000 6 10000................
MWD/MTU
TABLE OF CONTENTS (Cont'd)
Tables Title Delayed Neutron Fractions 20000 S 30000...............
MWD/MTU 15 16 17 Delayed Neutron Fractions 40000 MWD/MTU...............
Thermal Group Inverse Neutron Velocity................
Two-Group Collapsed Assembly Averaged Xsecs...........
18 Reactivity Defect Calculations.
1
FIGURE 1
'BNL'TANDARD PROBLEM 15xl5 W LATTICE RELATIVE PIN POWERS 150 MWD/MTU
.983
.979 1.000 1.012 1.043 1.060 1.067 1.065 1.039 1.050 1.040 1.032
.989 1.010
.985
.984
.997
.965
.957
.961
.961
.955
.953
.945 CHEETAH/PDQ DATA
FIGURE 2
'BNL'TANDARD PROBLEM 15xl5 W LATTICE RELATIVE PIN POWERS 500 MWD/MTU 1.005
.983
.979
.979 1.000 1.025 1.012 1.043 1.060 1.067 1.065 1.039 1.040 1.050 1.040 1.032
.977
.989 1.010
.985
.984
.997
.965
.954
.957
.961
.961
.955
. 953'945 941'HEETAH/PDQ DATA
1
FIGURE 3
'BNL'TANDARD PROBLEM 15x15 W LATTICE RELATIVE PIN POWERS 5000 MWD/MTU 1.000 1.039 1.061 1.060 1.036 1.037 1.029 1.010
.987
.986
.998
.968
.964
.964
.958
.957
.949
.946.
CHEETAH/PDQ DATA
FIGURE 4
sBNLe STANDARD PROBLEM 15xl5 W LATTICE RELATIVE PIN POWERS 10000 MWD/MTU
.987
.984 1.001 1.011 1.033 1.046 1.051 1.050 1.031 1.038 1.032 1.025
.992 1.008
.989
.988
.998
.972
.966
.970
.969
.965
.963
.956 CHEETAH/PDQ DATA
FIGURE 5
'BNL'TANDARD PROBLEM 15xl5 W LATTICE RELATIVE PIN POWERS 20000 MWD/MTU 1.002 1.021 1.031 1.030 1.020 1.020 1.016 1.005
.994
.993
.997
.982
.981
.981
.978
.976
.971
.969.
CHEETAH/PDQ DATA
FIGURE 6
'BNL'TANDARD PROBLEM 15x15 W LATTICE RELATIVE PIN POWERS 30000 MWD/MTU
.996
.996 1.002 1.005 1.011 1.015 1.016 1.016 1.012 1.012 1.011 1.009
.998 1.002
.997
.997
.998
.990
.989
.990
.990
.988
.987
.984 CHEETAH/PDQ DATA
FIGURE 7
'BNL'TANDARD PROBLEM 15xl5 W LATTICE RELATIVE PIN POWERS 40000 MWD/MTU 1.000
.997
.997
.997 1.000 1.004 1.002 1.007 1.009 1.010 1.010 1.007 1.006 1.008 1.007 1.006
.997
.998 1.001
.998
.998
.999
.994
.992
.993
.994
.994
.993
.992
.991 CHEETAH/PDQ DATA
TABLE 1 BNL STANDARD PROBLEM Koo VS BURNUP CHEETAH PXNCELL VS.
CHEETAH/PD Burnup (MWD/MTU) 150 500 1000 5000 10000 20000 30000 40000 CHEETAH
~On 1 1.14129 1.10463 1.09916 1.09589 NC 1.00496
.91865
.84832
.79355 Koo CHEETAH/PDQ 15x15 Lattice 1.14058 1.10300 1.09764 1.09425 1.05562 1.00347
.91672
.84626
.79194 55 133 125 136 147 229 286 256 Total QK
( pcm) 0-40 K Bu (PCM) 38396
(.5% diff) 38598
- Koo Includes Gap
+Q,= (Kl-K2) x 10 /(K1K2)
NC = Not Calculated
TABLE 2 BNL STANDARD PROBLEM ASSEMBLY VOLUME AVERAGED ISOTOPICS +
(ATOMS/BARN-CM)
ISOTOPE U-235 U-238 Pu-239 Pu-240 Pu-241 Pu-242 F.P.
500 mWD/MTU CHEETAH*
1.52783 6.72361-3 2.15215-6 3.3.2530-8 8.50277-10 4.33328-12 3.62248-6 CHEETAH/PDQ 1.52846-4 6.72366-3 2.10674-6 2.99997-8 7.80787-10 2.78212-12 3.56379-6 40000 NHD/MTU CHEETAH*
1.62489-5 6.49624-3 3.18613-5 1.74465-5 9.84268-6 6.83477-6 2.76862-4 CHEETAH/PD 1.64792-5 6.49561-3 3.23974-5 1.73614-5 9.96180-6 6.80422-6 2.76709-4
+ Does not include gap
- CHEETAH values multiplied by to generate Assembly Average Number Density 204 225
J t
TABLE 3 BNL 15x15 W LATTICE ASSEMBLY TOTAL REACTION RATES Buznu 150 MWD/MTU CHEETAH/PD
~Ieoto e
U235 U238 Pu239 Pu240 Pu241 Pu242 Fuel Clad Guide Thimble +
Absoz tion (sec 1) 1.56352+15 9.45297+14 2.00797+13 8.35486+10 3.49011+8 I
Negligible 3.73028+13 7.28549+13 Fission (sec 1) 1.29104+15 8.43912+13 1.28006+13 1.77856+8 2.56530+8 Negligible N/A N/A
+ Includes all guide and instrument thimbles
l f
,J
TABLE 4 BNL 15xl5 W LATTICE ASSEMBLY TOTAL REACTION RATES Burnu 500 h&H)/MTU
~Iso'to 8
U235 U238 Pu239 Pu240 Pu241 Pu242 Fuel Clad Guide Thimble +
Absor tion (sec 1) 1.52719+15 9.48370+14 6.55157+13 9.48220+11 2.27823+10 1.20408+7 3.73862+13 7.25663+13 CHEETAH/PD Fission (sec 1) 1.26049+15 8.49224+13 4.17759+13 2.02607+9 1.67431+10 1.58321+5 N/A N/A
+ Includes all guide and instrument thimbles
1'I '
TABLE 5 BNL 15x15 M LATTICE ASSEMBLY TOTAL REACTION RATES Burnu 5000 MWD/MTU CHEETAH/PD
~Ieoto e
Absor tion (sec 1)
Fission (sec 1)
U235 U238 Pu239 Pu240 Pu241 Pu242 Fuel Clad Guide Thimble +
1.19578+15 9.82341+14 4.60838+14 5.36008+13 1.26463+13 1.09866+11 3.84739+13 7.18785+13 9.84034+14 8.94758+13 2.94725+14 1.33530+11 9.30947+12 1.44502+9 N/A N/A
+ Includes all guide and instrument thimbles
TABLE 6 BNL 15x15 N LATTICE ASSEMBLY TOTAL REACTION RATES Burnu 10000 MWD/MTU CHEETAH/PD
~Isoto e
Absor tion (sec 1)
Fission (sec 1)
U235 U238 Pu239 Pu240 Pu241 Pu242 Puel Clad Guide Thimble +
9.53631+14 1.03321+15 7.04087+14 1.26690+14 5.56667+13 1.10237+12 4.02897+13 7.40278+13 7.83317+14 9.43427+13 4.51209+14 3.74773+11 4.10199+13 1.44792+10 N/A N/A
+ Includes all guide and instrument thimbles
BNL 15xl5 N LATTICE ASSEMBLY TOTAL REACTION RATES Burnu 20000 MND/MTU CHEETAH/PD
~Isoto 8
Absor tion (sec 1)
Fission (sec 1)
U235 U238 Pu239 Pu240 Pu241 Pu242 Fuel Clad Guide Thimble
+
6.14829+14 1.13881+15 9.66854+14 2.42656+14 1.76133+14 8.06785+12 4.42858+13 8.10735+13 5.04276+14 1.02962+14 6.20990+14 8.82582+11 1.29898+14 1.08373+11 N/A N/A
+ Includes all guide and instrument thimbles
TABLE 8 BNL 15xl5 N LATTICE ASSEMBLY TOTAL REACTION RATES Burnu 30000 MWD/MTU CHEETAH/PD
~Ieoto e
Absor tion (sec 1)
Fission (sec 1)
U235 U238 Pu239 Pu240 Pu241 Pu242 Fuel Clad Guide Thimble +
3.78592+14 1.24103+15 1.11670+15 3.30378+14 2.85334+14 2.10127+13 4.83097+13 8.90989+13 3.10399+14 1.10509+14 7.18031+14 1.32205+12 2.10482+14 2.95212+11 N/A N/A
+ Includes all guide and instrument thimbles
TABLE 9 BNL 15xl5 W LATTICE ASSEMBLY TOTAL REACTION RATES Burnu 40000 MWD/MTU CHEETAH/PD
~Ieoto e
Absor tion (sec 1)
Fission (sec 1)
U235 U238 Pu239 Pu240 Pu241 Pu242 Fuel Clad Guide Thimble
+
2.16928+14 1.32572+15 1.21128+15 3.93506+14 3.65295+14 3.67806+13 5.18130+13 9.64036+13 1.77837+14 1.16663+14 7.79313+14 1.64580+12 2.69482+14 5.45228+11 N/A N/A
+ Includes all guide and instrument thimbles
TABLE 10 BNL STANDARD PROBLEM GUIDE Er INSTRUMENT TUBE ABSORPTION RATES*
CHEETAH/PDQ BURNUP (MWD/MTU) 150 500 5000 10000 20000 30000 40000 2.41258+14 2.42935+14 2.57197+14 2.72720+14 3.00919+14 3.26786+14 3.54857+14'.60425+13 3.58549+13 3.52328+13 3.61529+13 3.95556+13 4.35380+13 4.70856+13 7.14340-4 7.14340-4 4.19280-2 4.19280-2 7.14340-4 7.14340-4 7.14340-4 7.14340-4 4.19280-2 4.19280-2 4.19280-2 4.19280-2 7.14340-4 4.19280-2 ABSORPTION (SEC-1) 7.28549+13 7.25663+13 7.18785+13 7.40278+13 8.10735+13 8.90989+13 9.64036+13 r
- Calculated by Vol
( $'.6' Vol = 43.27507 cm2
) of Guide and Instrument Tube REGION
l k
1
TABLE ll BNL 15xl5 W LATTICE ASSEMBLY CHARACTERISTICS*
BURNUP (MWD/MTU) 150 500 5000 10000 20000 30000 40000 1.10300 1.09764 1.05562 1.00347
.91672
.84626
.79194 M
(cm')
54.22 54.13 53.55 53.07 51.86 50.90 50.15 (cm-
)
1.900-3 1.804-3 1.039-3 6.539-5
-1.606-3
-3.020-3
-4.149-3
( x10(g 7.02 6.93 6.15 5.64 5.06 4.71 4.48 Inverse Neutron Velocity Thermal Grou 2.56409-6 2.56266-6 2.56321-6 2.56742-6 2.57818-6 2.58759-6 2.59468-6
+ Koo includes gap
~
\\
7 TABLE 12 BNL STANDARD PROBLEM DELAYED NEUTRON FRACTIONS
~Burnu (MWD/MTU) 150 Isoto e i U235 U238 Pu239 Pu240 Pu241 TOTAL
.0065
.0157
.0021
.0026
.0052 Fission Rate i 1.29104+15 8.43912+13 1.28006+13 1.77856+8 2.56530+8 1.38823+15 Fission Rate i 8.39176+12 1.32494+12 2.68813+10 4.62426+5 1.33396+6 9.74358+12 500 Isoto e i U235 U238 Pu239 Pu240 Pu241 TOTAL
.0065
.0157
.0021
.0026
.0052
~
~
7 0 i'FRi/g FRi
=
. 00702 l
I Fission Rate i 1.26049+15 8.49224+13 4.17759+13 2.02607+9 1.67431+10 1.38721+15 P
Fission Rate i 8.19319+12 1.33328+12 8.77294+10 5.26778+6 8.70641+7 9.61429+12 P
=
> t i'FRi/$ FRi
=
.00693
I l'
1
TABLE 13 BNL STANDARD PROBLEM DELAYED NEUTRON FRACTIONS
~Buruu (MWD/MTU) 5000 Isoto e i U235 U238 P0239 P0240 P0241' TOTAL
.0065
.0157
.0021
.0026
.0052 Fission Rate i 9.84034+14 8.94758+13 2.94725+14 1.33530+11 9.30947+12 1.37767+15 Fission Rate i 6.39622+12 1.40477+12 6.18923+11 3.47178+08 4.84092+10 8.46867+12 10000 Isoto e i
= 6Pi FRi/g,FRi
=.00615 I
i Fission Rate i Fission Rate i U235 U238 Pu239 P0240 P0241 TOTAL
.0065
.0157
.0021
.0026
.0052 7.83317+14 9.43427+13 4.51209+14 3.74773+11 4.10199+13 1.37026+15 t i FRi/5~ FRi
=
. 00564
~
~
I I
5.09156+12 1.48118+12 9.47539+11 9.74410+8 2.13303+11 7.7416+12
F TABLE 14 BNL STANDARD PROBLEM DELAYED NEUTRON FRACTIONS
~Bur nu (MWD/MTU) 20000 Isoto e i U235 U238 Pu239 Pu240 Pu241 TOTAL
.0065
.0157
.0021
.0026
.0052 Fission Rate i 5.04276+14 1.02962+14 6.20990+14 8.82582+11 1.29898+14 1.35901+15 Fission Rate i 3.27779+12 1.61650+12 1.30408+12 2.29471+9 6.75470+11 6.87613+12 30000
'I Pi
~ FRi/g FRi =.00506 I
Fission Rate i
'ission Rate i U235 U238 P0239 P0240 P0241 TOTAL
.0065
.0157
.0021
.0026
.0052 3.10399+14 1.10509+14 7.18031+14 1.32205+12 2.10482+14 1.35074+15 2.01759+12 1.73500+12 1.50787+12 3.43733+9 1.09451+12 6.35841+12
g Pi FRi/g FRi
. 0047l I
t
0
~.
il 1
'l
TABLE 15 BNL STANDARD PROBLEM DELAYED NEUTRON FRACTIONS
~Burnu (MWD/MTU) 40000 Isoto e i U235 U238 Pu239 Pu240 Pu241 TOTAL
.0065
.0157
.0021
.0026
.0052 Pission Rate i 1.77837+14 1.16663+14 7.79313+14 1.64580+12 2.69482+14 1.34494+15 Fission Rate i 1.15594+12 1.83161+12 1.63656+12 4.27908+9 1.40131+12 6.02970+12 P
=/Pi.
~ FRi/g FRi
=.00448
TABLE 16 BNL STANDARD PROBLEM THERMAL GROUP INVERSE NEUTRON VELOCITY*
~Buruu 150 500 5000+
10000 20000 30000 40000
'Ni ner/Wilkins 1/v ++
.564099
.563784
.563906
.564832
.567198
.569269
.57083 1/v (sec cm 1) 2.56409-6 2.56266-6 2.56321-6 2.56742-6 2.57818-6 2.58759-6 2.59468-6
- Calculated by:
N/N 1/v ~.454546-5 cm
+
Interpolated from 4
6 6K Values
++ CHEETAH Values
E, 4
. ~
P
'1 K
~
TABLE 17 BNL 15xl5 W LATTICE TWO-GROUP COLLAPSED ASSEMBLY AVERAGED XSECS* +++
~Burnu
~Grou 150 500 5000++
1 10000 20000 30000 40000 (cm 1)
(cm 1) 5.49472-3 1.85413-1 5.48826-3 1.87131-1 5.32781-3 1.97934-1 5.12030-3 1.98134-1 4.73447-3 (cm 1)
(cm 1)
(Watt/cm)
(cm) 7.07781-14 2.25684-3 2.53622-12 7.61545-2 7.06071-14 2.24444-3 2.55096-12 7.65279-2 6.67044-14 2.09739-3 2.61741-12 7.79203-2 6.41531-14 1.96107-3 2.56470-12 7.58851-2 5.81039-14 1.74656-3 8.86503-3 1.84526-2 1.37894 5.19697-1 1.37947 5.18838-1 1.38472 5.14464-1 1.39080 5.12633-1 1.38347 5.12285-1 1.37628 5.13251-1 1.37137 1.38900-1 8.88390-3 1.84622-2 1.40884-1 9.33700-3 1.82688-2 1.51924-1 9.85909-3 1.80721-1 1.56427-1 1.05605-2 1.79050-2 1.87337-1 2.35580-12 6.91092-2 1.57195-1 2.14142-12 6.24430-2 4.99914-14 1.47748-3 1.97763-12 5.74222-2 1.54961-1 1.73663-1 1-.14743-2 1.78430-2 4.18144-3 1.62512-1 5.14182-1 1.52523-1 1.10441-2 1.78793-2 4.41605-3 5.33640-14 1.58785-3
+
Calculated by dividing up+
by u In CHEETAH output
++
value interpolated from 4; 6K values
+++ Thermal MND CHEETAH/PDQ values
I I
TABLE 18 BNL STANDARD PROBLEM REACTXVTTY DEFECT CALCULATIONS+
Reactivity Defect Fuel Temp Mod.
Temp*
Mod.
+ Fuel*
8 68 F
Mod.
+ Fuel*
8 300 F
%zK/K
.8899
.0546
.6693
.6240 8.0948 2.6233 30000 MWD/MTU
%~K/K 1.3533
.3954
-3.7450
-1.3990 9.4095 2.7788 Kperturbed-Kbase
+
% ~ K/K x 100 Kperturbed*Kbase
- Calculation maintains 700 ppm 6
HFP equilibrium xenon.
yr
~
g' I
p h
October 20, 1986 DISTRIBUTION
~/
~ PADP2 Rdg w/o encl.
D, HcDonald w/encl.
D. Miller w/encl.
DOCKET NO(S) 50-250 and 50-251 (See attached list of addressees)
SUBJECT:
FLORIDA POl<ER AND LIGHT COftPANY TURKEY POINT PLANT UNITS 3 AND 4 The following documents concerning our review of the subject facility are transmitted for your information.
D Notice of Receipt of Application, dated D Draft/Final Environmental Statment, dated D Notice of Availabilityof Draft/Final Environmental Statement, dated D Safety Evaluation Report, or Supplement No.
, dated D Notice of Hearing on Application for Construction Permit, dated D Notice of Consideration of Issuance of Facility Operating License, dated D Monthly Notice; Applications and Amendments to Operating Licenses Involving no Significant Hazards Considerations, dated D Application and Safety Analysis Report, Volume D Amendment No.
to Application/SAR dated D Construction Permit No. CPPR-
, Amendment No.
dated D Facility Operating License No.
, Amendment No.
, dated D Order Extending Construction Completion Date, dated Ql Other (Specify) 5 h 1986
Enclosures:
As stated Division of PWR Licensing-A Office of Nuclear Reactor Regulation CC:
OFFICE+
SURNAME%
DATE~
D57 8...:ab......
!.O P/86.....
NRC FORM 318 {1/84) NRCM 0240
h
~ t l
4
~
~
~
I t
"r I
Turkey Point 3 and 4
cc:
Chief Division of Ecological Services Bureau of Sport Fisheries 8 Wildlife U.S.
Department of the Interior Washington, DC 20240 Chief (NOAA/BF/ECD/H6814)
Ecology and Conservation Division National Oceanic 5 Atmospheric Administration 14th and Constitution Ave.,
NW Washington, DC 20230 Dr. William B. Stroube, Jr.
FDA Research Chemist National Bureau of Standards Reactor Building 235, Room B-108 Gaithersburg, MD 20899 U.S.
Environmental Protection Agency Region IV Office ATTN:
Regional Radiation Representative 345 Courtland Street, NE
- Atlanta, GA 30365
0 le&