ML17346A242
| ML17346A242 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/02/1984 |
| From: | Williams J FLORIDA POWER & LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR L-84-91, NUDOCS 8404050137 | |
| Download: ML17346A242 (32) | |
Text
REGULATORY IFORHATION DISTRIBUTIONH (RIDS) f ACCESSION NBR:8400050137 DOC ~ DATE: 84/04/02 NOTARIZEDj NO "DOCKET FACIL:50-250 Turkey Point Plantg Unit 3i Florida Power and Light C
05000250
'50-251 Turkey Point Planti Unit 4E Florida Power and l.ight C
05000251 AUTH'AME AUTHOR AFFILIATION lvILLIAHSiJ~ '8 ~
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RECIP ~ NAME RECIPIENT AFFILIATION VARGAES,AD Operating Reactors Br anch 1
SUBJECT:
Forwards data re Cycle 9 core octant time averaged relative
.power densityitime averaged peripheral assembly axial power 8 peripheral assembly radial pin power per 8311 17 request for info on pressurized thermal shook issue, DISTRIBUTION CODE:
AOOIS COPIES RECEIVED:LTR l.:ENCI.
SIZE:
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OR Submittal:
General Distribution NOTES:
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~yOIAg Jl'vs w~Wi FLORIDA POWER & LIGHTCOMPANY April 2, 1984 L-84-9l Office of Nuclear Reactor Regulation Attention:
Mr. Steven A. Varga, Chief Operating Reactors Branch ¹1 Division 'of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 RE:
Turkey Point Units 3'r. 4 Docket Nos..
50-250 8I; 50-251 Pressurized Thermal Shock Flux Reduction Pro ram
Reference:
"Turkey Point Unit 3 and 4 Neutron Source Data Schedule",
Letter from Mr. J.
W. Williams to Mr. S.
A. Varga, December 21,
- 1983, L-83-597
Dear Mr. Varga:
Your letter dated November 17,
- 1983, requested integral neutron source data for the purpose of evaluating and verifying flux reduction.
The data in Attachment A to this letter is submitted for Turkey Point Unit 3, Cycle 9 in accordance with our schedule in the Reference and consists of:
1.
Cycle 9 core octant time averaged relative power density.
2.
Time averaged peripheral assembly axial power.
3.
Peripheral assembly radial pin power.
The time averaged core octant relative power densities provided are based on predicted assembly powers from the FPL PDQ-7 model, assuming an expected core average burnup of 12,700 MWD/MTU.
The peripheral assembly axial powers are based on predicted data from the FPL EPRI-NODE model.
Comparisons of measured and predicted axial power data show good correlation and make the predicted value applicable for the purpose of the flux reduction evaluation.
I'404050137 '840402.
PDR. ADOCK 05000250, p,
PEOPLE... SERVING PEOPLE
The peripheral assembly radial pin powers provided are based on predicted values from the FPL PDQ-7 model and are representative of the cycle average..
These pin powers form the basis 'of the azimuthal flux variation to be used at the core periphery.
The pin powers of all other assemblies are assumed to be flat.
Additional data, as requested by Mr. Lambros Lois of your office by telephone on March 20,
- 1984, has been provided in Attachment B.
This data consists of the location of the critical weld for Turkey Point Units 3 and 4 and the time averaged peripheral assembly axial powers for Unit 4 Cycle 9.
Should you have any questions, please contact Dr. Finis Southworth at 305-552-3468.
Very truly yours, J.
W. Williams, Jr.
Vice President Nuclear Energy WRrC'WW/ERK/daj cc:
J.
P. O'Reilly, Region II Harold F. Reis, Esquire
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TURKEY POINT REACTOR VESSEL ASSEMBLY PIN POWER LOCATOR FOR ATTACHED PIN POWER 1tAPS NORTH 0
0 AIR CAVITY INSULATION REACTOR VESSEL VESSEL CLADDING 6
7 Qa Qs oQ BAFFLE THERMAL SHIELD CORE BARREL 0 - EX-VESSEL DOSIMETER LOCATIONS
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TURKEY POINT UNIT 3 CYCLE 9 Normalized Assembly Axial Power Normalized to Unit Prol.'iles Assembly No.
0.92 1.18 1.22 1.24 1.20 1.16 0.84 0.80 0.78 0.81 1.03 0.82 0.27 0.83 1.12 1.19 1.23
".20 1.17 0.88 0.86 0.84 0.87 1.03 0.78 0.25 0.61 0.92 1.03 1.07 1.09 1.11 1.11 1.12 1.12 1.12 1.02 0.69 0.88 0.70 0.96 1.05 1.08 1.08 1.09 1.08 1.09 1.08 1.07 0.99 0.71 0.41 0.74 0.99 1.05 1.08 1.07 1.08 1.07 1.08 1
1;06 0.98 0.73 0.48 Top critical weld Bottom Assembly Average (RPD)
Assembly No.
6 0.73 1.00 1.06 1.10 1.09 1.09 1.05 1.06 1.04 1.05 1.00 0.73 0.82 0.63 0.93 1.03 1.08 1.09 1.10 1.09 1.10 1.11 1.10 1.03 0.71 1.04 0.63 0.91 1.01 1.06 1.07 1.10 1.10 1.13 1.13 1.12 1.03 0.72 1.08 0.63 0.90 1.01 1.05 1.07 1.09 1.10 1.12 1.13 1.12 1.04 0.73 1.31 10 0.66 0.93 1.02 1.06 1.07 1.09 1.09 1.11 1.11 1.10 1.02 0.73 1.03 Top critical weld Bottom Assembly Average (RPD)
Note:
To obtain assembly axial relative power density (RPD), multiply normalized assembly axial power by assembly average relative power density.
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ATTACHXKNT B
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0 TURKEY POINT REACTOR VESSEL ASSEMBLY PIN POWER LOCATOR FOR ATTACHED PIN POWER MAPS NORTH 0
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EX-VESSEL DOSINETER LOCATIONS
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TURKEY POINT UNIT 4 CYCLE 9 Normalized Assembly Axial Power Normalized to Unit Profiles Assembly No.
Assembly No.
0.82 1.02 1.04 1.07 1.05 1.08 1.05 1.07 1.04 1.04 0.97 0.77 0.31 0.72 0.96 1.02 1.06 1.06 1.09 1.08 1.10 1.08 1.08 1.00 0.74 0.73 0.76 0.99 1.03 1.07 1.06 1.09 1.07 1.09 1.06 1.06 0.97 0.73 0.29 0.58 0.88 0.99 1.05 1.08 1.11 1.13 1.15 1.16 1.15 1.04 0.69 1.12 0.56 0.87 0.99 1.06 1.09 1.12 1.14 1.16 1.17 1.15 1.03 0.66 1.02 0.57 0.87 1.00 1.06 1.09 1.12 1.13 1.16 1.16 1.14 1.03 0.68 1.
16'.66 0.93 1.02 1.08 1.08 1.11 1.11 1.13 1.11 1.09 0.98 0.69 0.44 0.64 0.91 1.01 1.06 1.08 1.10 1.10 1.13 1.12 1.11 1.02 0.72
'1.19 0.68 0.95 1.03 1.08 1.08 1..11 1.10 1.11 1.08 0.98 0.70 0.47 10 0.59 0.89 1.01 1.06 1.09 1.11 1.13 1.15 1.15 1.13 1.02 0.68 1.13 Top critical weld Bottom Assembly Average (RPD)
Top critical weld Bottom Assembly Average (RPD)
Note:
To obtain assembly axial relative power density (RPD),
multiply normalized assembly axial power by assembly average relative power density.
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