ML20037B161
| ML20037B161 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/17/1968 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Reder R COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20037B162 | List: |
| References | |
| NUDOCS 8009050629 | |
| Download: ML20037B161 (2) | |
Text
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DISTRI JTION Suppl DRL Reading REG Reading May 17, 1968 Branch Reading ACRS (3)
Form 1 W. Dooly, REG Ir. Reply Refer To:
R. Engelken, CO (2)
Docket No. 50-10 H. K. Shapar, CC-C N. Dube, DRL ( 5)
J. R. Buchanan, ORNL D. Thompson, DEL Public Docurent Roca Comomealth Fdison Company D. J. Skovholt, DEL 72 West Adams Street S. Levine., DRL Chicago, T11 %ois 60690 D. L. Zierann, DRL S. McManus, DRL Attention:
ft. R. E. Reder R. Diggs, DRL Nuclear Licensing / & inistm tor Cnange No. 16 License No. DPR-2 Gentlemen:
In accoadance with the provisions of Section 50.59 of 10 CFR Part 50, we
- l have reviewed your Proposed Change No.16, dated liay 9,1968, to the Technical Specifications of Facility Operating License No. DPR-2, as amended. 'Ihe proposed change would authorize replacerent of one of the gadolinia-urania poison fuel rods in each of two irradiated Type V high gadolinia fuel assemblies with an unirmdiated gadolinia-alumina poison rod identical to those used in Type III-F fuel asserblies in onder that y% the gadolinia-urania rods may be reroved for examination and burnup
, reasurements.
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~ 4 We have concluded that the proposed cMnge, designated as Cunge No.16, h
does not present significant hamds considemtions not described or Q
inplicit in the Hazands Suzary Report (hereafter called the safety analysis y
report) and that there is reasonable assurance that the health and safety of the public will rot be erdangered by the change. A copy of our related Safety Evaluation is enclosed.
Accordingly, the fourth line of the footnote on Table II entitled Dresden I Fuel Ele ent Data for Cycle 6, revised Dece-ber 28, 1967, of the ~'echnical Specificatiens of Facility Operating License :o. DPR-2, as a~ ended, is hereby changed to read:
l "of cne of the follcwing Pu enrich ents:
1.2 w/o; 1.7 w/o; 1.2 and 1.4 'do; 1.2 w/o; in natuml uranium.
(f) Selected rods contain small arounti of Gd 0 remainder of rod 100% UO, except that the remainder of two rods wi$1contain100%A10."
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UNITED STATES
!N ATOMIC ' ENERGY COMMISSION
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~WASWNGTON. D.C.
20545 I
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May 17, 1968
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In Reply Refer To:
Docket No. 50 *=
Cc=cnwealth Edison Cor::pany 72 West Adars Street Chicago, Illinois 60690 Attention:
Mr. R. E. Reder Nuclear Licensing Administrator Change No. 16 License No. DPR-2 Gentlemen:
In accordance with the provisions of Section 50.59 of 10 CFR Part 50, we have reviewed your Proposed Change No.16, dated May 9,1968, to' the Technical Specifications of Facility Operating License No. DPR-2, as arended. The proposed change would authorize replacem nt of one of the
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gadolinia-urania poison fuel rods in each of two irradiated Type V high
~~
gadolinia fuel assemblies with an unirradiated gadolinia-alurina poison
.i rod identical.to those used in Type III-F fuel asserblies in ender that the gadolinia-urania rods ray be re: roved for examination and burnup measumwnts.
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We have concluded that the proposed change, designated as Change Ib.16, does not present significant b m rds considerations not described or implicit in the Hazanis Sur:rary Report (hereafter called the safety analysis report) and that there is reasonable assurance that the health-and safety of the public will not be endangered by the change. A copy of our related Safety Evaluation is enclosed.
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Accordingly, the fourth line of the footnote on Table II entitled Dresden I' Fuel Element Data for Cycle 6, revised Decerber 28, 1967, of the Technical Specifications of Facility Operating License No. DFR-2, as a~ ended, is hereby changed to read:
"cf one of the following Pu enrichments:
1.2 w/o; 1.7 s/o; 1.2 and 1.4 w/o; 1.2 a/o; in natural uranium.
(1) Selected rods contain srall a. cunts of-Gd 0; remainder of red 100% UO ' except that the re ainder of two rods -
2 wi_l~contain 100% A1 0
- 23
.;.x Sincerely yours, n
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MM M i ib k Peter A. Ferris, Directcr 11 Division of Reactor Licensing E.:les re:
Safety Evaluatien