ML20151A589
| ML20151A589 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/20/1976 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151A587 | List: |
| References | |
| NUDOCS 8011030798 | |
| Download: ML20151A589 (5) | |
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I UNITED STATE'S
'y S NUCLEAR REGULATORY COMMISSION
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.1 DOCKET NO. 50-29 YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)
AMENDMENT TO FACILITY.0PERATING LICENSE t
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Amendment No. 2 2 License No. DPR-3 1
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1.
The Nuclear Regulatory Commission (the Commission) has found that:
b A.
The, application for amendment by Yankee Atomic Electric Company'_
(the licensee) dated December 29, 1975, complies with the standards and requirements of[ the Atomic Energy Act of 1954, as amended (the Act)' and the Commission's rules and regula-
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tions set forth in 10 CFR Chapter I; N:
B.
The facility'will operate in conformity with the application, the provisioons of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; A
D.
The issuance of this amendment will not be inimical to the common 1
defense and security or to the health and safety of the public; and E.
An environmental statement or negative declaration need not be prepared in connection with the issuance of this amendment..
n 2.
Accordingly, the license is amended by a change to the Technidal
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Specifica.tions as indicated in the attachment to this. license amendment and Paragraph 3. A. (2) of Facility License No. DPR-3 is hereby
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amended to read as follows:
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" 3.A. (2) Technical Specifications lifk i:=:u..
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The Technical Specifications contained in' Appendix A, 5@.]@j]
as revised, are hereby incorporated in the license.
s=e The licensee shall operate the facility in accordance
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with the Technical Specifications."
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This license amendment is effective as of the date of its issuance.
...::.=5 FOR THE NUCLEAR REGULATORY COWIISSION.
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Or!ginal r;ignedb[
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R. A. Purple -
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...;.iiuiii; Robert-A. Purple, Chief
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Operating Reactors Branch #1 vise., _
Division of Operating Reactors
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Attachment:
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Changes to the
.1 Technical Specifications E!:
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Date of Issuance:. JAN 2 01976
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- ATTACBENT 'ID LICENSE AMENDMENT NO. 2 2
.. "5 FACILITY OPERATING LICENSE NO.~ DPR-3 DOCKET NO. 50-29 5:
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h:j;_ ' l:::.b b.:i Revise Appendix A as follows:
Remove pages Sa, Sb; and'5e and insert revised pages 5a ji~~
and 5b.
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a) lleat flux power peaking factor, F, measured.using
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b)' Effoct of inserting the control bank from its position
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at the time of measurement to its insertion limit -(F l F
i as shown in Figure 8-2.
The rod insertion limit is Th shown in Figure 8-3; y.-
c) Effeet of xenon redistribution (1.10);
p t:5 d) Shortened stack height factor (1.009);
5 LE e) Measurement uncertainty (1.05);
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f) Fower level uncertainty (1.03);
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g) Heat flux engineering factor, F{F-,(1.04);
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h) Core ~ average linear heat generation rate at full power it=i=d i
- (4.34 kW/ft).
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These factors. are multiplicative.
When operating'at constant E.....
power, all rods out, with equilibrium xenon, power peaking t a
- EZT the Yankee-Rowe core decreases monotonically as.a function of cycle burnup.
This has.been verified by both calculation and measurement on Yankee-Rowe cores and is in accord with tho expected behavior in a core that does not contain burnable poison. The all-rods-out power peaking measured at any time in core life thus provides an upper bound on ARO power peaking for the renaindor of that cycle. Thereforo, the measured power peaking shall be chocked every 1000 equivalent full-power hours and the latest measured value shall be used in the computation. The only effects which can increaso peaking beyond this value would be control rod insertion and xenon transients and theso are accounted for in itens (b) and (c).
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