ML19308A960
| ML19308A960 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/06/1970 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Hendrie J Advisory Committee on Reactor Safeguards |
| References | |
| NUDOCS 7912120730 | |
| Download: ML19308A960 (2) | |
Text
OFFICIAL USE ONLY
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Docket Hos. 50-269 Distribution:
50-270 Docket w/enci and 50-2B7 PWR-2 Reading RCDeYoung gg8-WD FWKaras (2)
ASchwencer Dr. Joseph !!. Hendrie Chaircan, Advisory Corrittee on Ecactor Safeguards U.S. Atomic Energy Cor::nission Washington, D.C.
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Dear Dr. liendrie:
Eighteen copies of a replacer.cnt page 17 to the report to the ACRS by the Division of Icactor Licensing dated July 24 1970 e
are enclosed for your distribution to the recipients of the original report concerning the Duke Power Con:pany's Oconee Nucicar Station Units 1, 2, and 3.
Sincerely, Peter A. l' orris, Director Elvision of Teactor 1.icensing
Enclosure:
Report to ACRS When separated from enclosuies, handle tisis docurnent a s _____ _ ___ __ __,[g (In: art prcper classificaticIn)~~~~~~~~~~
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OFFliCHAL USE OhY 17 3.2.2 Reactivity Calc _olations The applicant has deceribed the computer programs and calculational techniques used by B&W to predict the nuclear charac,teristics of the reactor.
designs, and has provided exampics to denonstrate the ability of thesc tacthodn to predict UO and P 0 - UO critical assemblics.
We concur that 2
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these examples demonstrate the validity of tiie rnethods used to pradict
'edf for the large power reactor corcs.
Detailed three-dimensional power distribution measurements have been perfortned by B&W at the Babcock & Wilcox Critical Experiments Laboratory.
Results of the applicant's calculations using PDQ07, a three-dimensional i
program, agree quite voll with the rneasured power distributions.
The B&W version of PDQ07 used for the calculations incorporates a thermal feedback option, permitting accurate descriptions to be made of the radial and axlal pouer distributions in analyses of control rod haneuvering, icnon stnhility neatus and control, and reactivity coef ficients.- These distributions are e
needed to evaluate core thermal' margins.
t-The applicant has also performed analyses, using a two-dimensional PDQ program in. conjunction with fuel cycle calculations obtained with the use
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of the HM010NY program, to provide estimates of core fue burnups and first and second cycle and eq:tilibrium core enrichments.
We have concluded that the material presented adequately demonstrates B&W's ability to predict the physics characteristics of the reactors.
3.2.3 Jteactivity control Requirements The applicant has provided substantial information supporting his ability to control the excess reactivity provided in the reactors and main-
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tain a shutdoun margin to hot critical of 'at least 1% Ak/k throughout core life Vith the most rear.tive control rod stuck out of the core.
Sixty-one full-length control, rods are provided. This is greater than the number provided in othel PWR designst The predicted worth of 12.1% Ak/k for Oconce 1, is also greater than'the worth usually provided.
For 90% of the fuel cycle in Oconee 1,1.0 to 1.3% of the control rod worth will be used for partial j
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