ML19345A279
| ML19345A279 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/06/1962 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Coe R YANKEE ATOMIC ELECTRIC CO. |
| References | |
| NUDOCS 8011180514 | |
| Download: ML19345A279 (3) | |
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Docket 11o. 50-29 Yankee Atomic Electric Company 441 Stuert Street Boston 16, Messachusetts Attention:
Mr. Roger J. Coe Vice President Gentlemen:
As has been discussed with representatives of the Yankee Atomic Electric Company, certain additional information is required in support of your application for authorization to incrc.ase the maximum operating power of the Yankea reactor from 485 to $40 Mw thermal. This edditional information is outlined in the list attached es an enclosure to this letter.
In view of the scheduled dates for the Augurt ACRS neeting, we request t wt you provide this inforaction prior to August 8.
Tarec copies signed under ccth or affirmctivn end 53 co.tformed copies should be provided.
"**YI DISTRIBUTION OGC (1) cy E. G. Case (1) cy Doc. Rm.
Formal Suppl.
L&R Reading Adar Director R&PRSB Reading Division of Licensing cud Regulation Enclosare:
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LIST OF EEQUIPID ADDITIONAL It?PO'NTION REGARDIt!C h
TPI YAS/IE El'd.CTOR f
1.
In addition to the items discussed in your amendment application, discuss components or features of the facility whose capacities
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could be approached or exceeded as a result of 540 Mw thermal
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operation. In particular, discuss the adequacy of the turbo-f:
generator and the increase in probability, if any, of a thrown turbine blade.
2.
Explain how the safety injection pump flow can be adjusted to replace the water boiled off into the vcpor container in the
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event of a rupture, as described in the fif th parcgraph on page 212:1 of your amendsent application,.nd the basis for and the
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meaning of the 5 gpa value stated in the first paragraph on page 212:3.
3.
Present an analysis of fuel element bowing and its possible effect on reactivity and interference with control rod motion during
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normal operation and ie the event of overpower transiente.
l 4.
Analyze the consequences of the sequentini loss of main coolant 7._.
pump flow type of accidents.
st 5.
Describe the tests and step-wise approcch which will be performed during the escalation of the opercting power of the reactor from 485 to 540 Lv thermal. Indiente how often flun wire recdings vill be taken end hot channel factorc calculated during operction of the reactor et 540 IN thermal eith Core II.
6.
With regard to the fuel elements from Core I which will be irradicted to 19.000 Mwd /t burnup in Core II:
a.
State the percentage of fiscion product gas release which was assumed and reasons therefor.
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i-b.
Give the resulting maximan internal gas pressure.
i c.
Indiccte the resultant preesure and theroni and combined stresses which will exist in the cladding at end of core life:
C) During full power operation (2) In the event of a loco of flow accident d.
State the expected yield end ultimate strengths of cicdding as a function of tenperature for purpoces of cenperison uith ctrecrco given under (c).
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7.
State the magnitude of the thermal stress referred to in the lart paragraph on page 202:2 of your amendmerit application. Indicate how the pressure stress plus the thermal streco co:npares to the yield and ultimate strengths of the Type 316 materials
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8.
Explain what was used for a film boiling heat transfer coefficient in the leas of flow accident analyses and state on what basis it was selected.
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