ML19340A896
| ML19340A896 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/23/1966 |
| From: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Bower D COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8009050623 | |
| Download: ML19340A896 (2) | |
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SUPPLEMENIEL 0,,,,, (9 UNITED STATES 3
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e ATOMIC ENERGY COMMISSION a s X*i WASHINGTON. D.C. 20545
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DV 2 31955 IN REF.Y R."7IM TO:
Docket No. 50-10 Coenonwealth Edison Company 72 West Adams Street Chicago, Illinois 60690 Attention:
Mr. D. Robert Bower Change No. 12 Treasurer Centlemen:
Commonwealth Edison Company, by letter dated August 9, 1966, has requested authorization to change Section F.4 of the Technical Specifications to License No. DPR '2 for the Dresden Unit No. 1 reactor. The request has been designated Proposed Change No. 12.
Section F.4 presently requires that a minicum of tuo control rod drive mechanises be removed, disassembled and inspected at least every 16 months.
This length of time appeared sufficient to accommodate the
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anticipated operating cycle at the time Section F.4 was adopted. However, as it now appears that operating cycles between refueling will exceed 16 months, Commonwealth has proposed that the inspection interval be based on the frequency of major refueling outages in order to eliminate any requirement for an extended reactor outage prior to such refueling.
Based on discussion with representatives of Commonwealth, it was agreed that it would be preferable to extend the inspection interval to a maximum of 24 months, to acco==edate a longer refueling cycle, rather than base the maximu= interval for inspection on an indefinite period.
Such an extension will not impair safe reactor operation.
Proposed Change No. 12 has been considered pursuant to the provisions of Section 50.59, 10 CFR 50.
We have concluded that Proposed Change No. 12 does not presert significant 8009Oppo M
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Commonwealth Edison Co. (Docket No. 50-10) l hazards considerations not described or implicit in the hazards summary report and that there is reasonable assurance that the health and safety of the public will not be endan-gered.
In view of the foregoing, the Tc.chnical Specifications to License No DPR-2 are hereby amended as set forth below.
4 In Section F.4, " Tests and Inspection of Control Rod Drives," the phrase "not to exceed 16 months" is hereby changed to "not to exceed 24 months" so that the paragraph will read as follows:
" Routine inspections during major outages:
Not less than two control rod drive mechanisms shall be removed, disassembled, and thoroughly inspected at intervals not-to exceed 24 conths.
It is anticipated that such inspections will be made during outages
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involving the removal of the reactor head for refuel-ing or other purposes."
Sincerely yours, i
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Peter S. Morris, Dirbetor i
Division of Reactor Licensing Distribution:
AEC Public Document Room Formal Docket Copy Supplemental DRL Reading R&PRSB Reading
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C. L. Henderson, REG E. G. Case, DRL H. !;. Shapar, GC-L. Rornblith, CO (2)
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