ML17346A222
| ML17346A222 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/01/1984 |
| 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-84-54, NUDOCS 8403080020 | |
| Download: ML17346A222 (22) | |
Text
REGULATOR NFORMATION DISTRIBUTION S EM (RIDS)
AccEssIoN NBR:e4030s0020 DOC.DATE: s4/03/01 NoTARIzEDs No
,DOCKET FACIL:50 250 Turkey Point Planti Uni:t 3r Fl,orida Power -and Light C
05000250 50 251 Turkey Point Planti Unit 4i Florida Power and Light C
05000251 AUTH'YNAME AUTHOR AFFILIATION NILLLIAMSiJ.W.
F l.orida Power 8 Light Co.
'RECIP ~NAME'ECIPIENT AFFILIATION VARGAiS ~ AD Operating Reactors Branch 1
SUBJECT:
Forwards integral neutron source data for evaluating 8
verifying flux reduction per 84117 requests Data for Cycle 9
core octant time averaged relative power densityicritical weld peaking factor 8 peripheral assembly pin.power encl'1STR'IBUTION
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FLORIDAPOWER & LIGHTCOMPANY March 1, 1984 L.-84-54 Office of Nuclear Reactor Regulation Attention:
hIr. Steven A. Varga, Chief Operating Reactors Branch g1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 RE:
Turkey Point Units 3 5 4 Docket Nos.
50-250 8r. 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 hir.
S.
A. Varga, December 21,
- 1983, L-83-597
Dear hir. 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 4, Cycle 9 in accordance with our schedule in Reference 1;
and consists of:
1.
Cycle 9 core octant time averaged relative power density.
2.
Critical weld axial peaking factor.
3.
Peripheral assembly 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 8000 h1WD/MTU.
Comparisons of. predicted and measured assembly relative power densities from available measured incore data are in good agreement, thus making the use of predicted values appropriate.
The peripheral assembly axial peaking factor at the critical weld location is 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 purpo'se of the flux reduction evaluation.
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Page Two The peripheral assembly 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.
The format of'his data is based on. information provided by her.
Lambros Lois of your office by telephone on December 9,
1983.
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 JWW/ERK/daj cc:
J.
P. O'Reilly, Region II Harold F. Reis, Esquire
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ATTACHhKNT A
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226.66-TURKEY POINT UNIT 4 CYCLE 9
CYCLE AVERAGE RELATIVE POWER DENSITY 0
NORTH
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197.88 197.49 Cl8 A
187.91-181.13-cf 175.11-170.03-164.14 161.28 0
31 0.29 AIR CAVITY INSULATION REACTOR VESSEL VESSEL CLADDING 73 1.12 1.02 0.44 THERMAL 'SHIELD CORE BARREL 1.05 1.01 I.16 1.16 0.47 BAFFLE 0
91 1.22 1.21 1.19
.13 1.20 1.19 1.24 1.23 1.24 1 05 PERIPHERAL ASSENBLY AXIAL PEAKING FACTOR
= 1.07 AT CRITICAL WELD ELEVATION 1.26 1
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