ML19340A920
| ML19340A920 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/01/1963 |
| From: | Lowenstein R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Bower D COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML19340A921 | List: |
| References | |
| NUDOCS 8009080619 | |
| Download: ML19340A920 (2) | |
Text
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UNITED SIATES Ih [%
ATOMIC ENERGY COMMISSION
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I WASHINGTON 25. D.C.
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,, e FEB1 1963 Docket No. 50-10 Change No. 2
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0 Commonwealth Edison Company j
72 West Adams Street
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Chicago 90, Illinois F
Attention:
Mr. D. Robert Bower P
Treasurer Gentlemen:
Commonwealth Edison Company has requested, by letter dated November 15, 1962, a relaxation of the requirements in the technical specifi-cations appended to Facility License No. DPR-2, as amended, which
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pertain to a " cocked rod criterion" as applied to the removal of irradiated fuel from the reactor to the fuel storage pool and to the 1
temporary removal and subsequent replacement of a single bundle of irradiated fuel in the reactor for testing purposes.
This request, designated as Proposed Change No. 2, was considered
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pursuant to the provisions of Section 50.59, 10 CFR 50.
On the basis of the information submitted in support thereof, it was concluded j
that Change No. 2 does not present significant hazards censiderations not.fescribed or implicit in the hazards sununary report and that there is reasonable assurance that the health and safety of the public will not be endangered. The related hazards analysis is attached.
Accordingly, purusant to the provisions of 50.59(e) of 10 CFR 50, paragraph D.S.b of the Technical Specifications (Appendix "A" to j
l License No. DPR-2) is amended to read as follows:
r "With the reactor in any condition, the following shutdown criterion chall be met:
' Stuck Rod' Criterion: At every stage during loading and in the fully loaded configuration, the control rods must provide a shutdown con-trol margin of at least 0.01 Jk with any rod wholly out of the core and completely unavailable."
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A FEB ~'
1963 Commonwealth Edison Company ;
"During core alterations after the first fuel cell is loaded, the following ' cocked rod' criterion shall be met:
Cocked Rod' Criterion: The reactor must be sub-critical by at least 0.01 A k with at least one control rod fully withdrawn in the region of the l
alteration and available for rapid scram inser-tion. Exceptions to this requirement may be taken for removal of irradiated fuel to the fuel storage pool during refueling and for temporary removal and subsequent re-placement in the core location from which it came of a single bundle of irradiated fuei for testing purposes; provided that, while such a fuel element is out of the core, no manipulation or movement of other components or equipment in or near the core, hall be made, nor shall the state of the reactor be otherwise changed in such a way that reactivity would be increased."
Distribution Sincerely yours, H. J. McAlduff G. Page E. G. Case Doc. Room
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H. Shapar Formal g
P. A. Morris-2 Suppl.
1 E. E. Hall LB-LGR readings D. C. Clark R. Lowenstein, Director E. Tre=mel Division of Licensing and H. Steele Regulation R. Huard
Enclosure:
Hazards Analysis t
DLSR g*
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<j s.J NDMason/dk Q67 RHB,un Director 4
YIk /MY63 1/21/63
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