ML19340A951
| ML19340A951 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/12/1973 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Butterfield L COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8009100793 | |
| Download: ML19340A951 (2) | |
Text
l i
i MAP.12 33 Docket No. 50-10 Commonwealth Edison Company ATTN:
Mr. L. D. Butterfield, Jr.
Nuclear Licensing Administrator Post Office Box 767 Chicago, Illinois 60690 O. g 7
Change No. R Centlemen:
License No. DPR-2 Your letter of February 7,1973, requested changes to the Technical Specifications of License No. DPR-2 to authorize a higher==vimum water temperature in the isolation condenser. We understand the change is requested because high anbient air temperature in the containment done where the isolation condenser is located often raises condenser water temperature above 100*F.
The letter also requests deletion of i
a procedure covering the probable maximum flood since you do not consider such a procedure to be necessary.
- our letter states that the analysis performed in response to the AEC's Interim Acceptance Criteria for Emergency Core Cooling Systems was performed assuming an initial water temperature of 212'F.
In addition, in discussiens with your staff, -e were informed that cal-culated fuel clad temperatures using the assumptions of the Interim Acceptance Criteria are relatively insensitive to the initial tempera-ture of the isolation condenser water. On this basis we have con-cluded that raising the technical specification limit on isolation condenser water temperature frca 100'F to 212'P has no significant effect on safety.
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.ased on the preceding considerations, ve have concluded that the
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~i proposed change for a higher mmwimum water tapperature in the isolation j
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. condenser does not present significant hazards considerations not described or implicit in the Dresden 1 Safety Analysis Report (Ha::crds
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Summary Report) and that there is reasonable assurance that the health
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reactor in the manner proposed.
and safety of the public will not be endangered by operation of the mozoo 773 p
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j Co==onwealth Edison Company E, Accordingly, pursuant to Section 50.59 of 10 CFR Part 50, Section B.15.b(1) of the Technical Specif1 cations of Facility License 2;o.
DPR-2 is hereby changed to read as follows:
3.15..(1)
The shell side water level and temperature shall be checked daily to assure that it con-tains a minimum of 30,000 gallons and that the temperature of the water does not exceed 212'F when not in operation.
Our review of your request to delete the requirement for a procedure for the probable maximum flood indicates that your request does not contain adequate basis and therefore cannot be granted. You have not demonstrated that the level of the probable maximum flood is not above grade level of the Dresden site. Unless such demonstration can be made, appropriate planning for coping with emergencies should include development of a procedure to ensure reactor safety in the event of floods with levels up to that of the probable marinum flood.
Sincerely, cd#d S*'d 'd p, y, : -- -Mt Donald J. Skovholt Assistant Director for Operating Reactors Directorate of Licensing Distribution cc:
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