ML17238A799
| ML17238A799 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 03/18/1975 |
| From: | Commonwealth Edison Co |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| Download: ML17238A799 (2) | |
Text
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Commonwe. Edison One First Natiqna1 laza, Chicago, Illinois Address Reply fo: Post Office Box 767 Chicago, Illinois 60690
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March 18, 1975 REGULATORY DOCKET FILE COPY Mr *. Edson G. Case Acting Director Off ice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Wa.sh".!ngt0n, D.C.
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Dear Mr. Case:
Dresden Station Units 2 and 3, Quad-Cities Station Units 1 and 2, Dresden Station Special ReportNo. 39, Quad-Cities Special Report No. 14, Analysis of Hydrogen Generation and Control in Pr irnary Containment Foliowing Postulated Loss of Coolant Accident,,
NRC Dkts. 50-237, 50-249, 50-254 and 50-265.
Attached is a copy of the subject report which present*s an analysis of generation and control of combustible gas in the containment.
The purpose, the scope and the results of this review are thoroughly discussed in.the report.
Your review of the subject report is requested.
If you concur with the report's conclusion that the requirement for inerting the containment should be eliminated, the appro-priate proposed amendments to Facility Operating Licenses DPR-19, DPR-25, DPR-29, and DPR-30 will be prepared and sub-mitted* for NRC approval.
The proposed license amendments are not included in this submittal, because the amount of me*tal-water reaction generated hydrogen calculated in this report u'sing 10CFR50.46 criteria must be confirmed by the results of documented and approved.analysis.
Established techniques which are more precise than those used in Dresden Special Report No. 40 and Quad-Cities Special Report No. 15 (ECCS Analyses per 10CFR50.46) will be submitted to confirm the hydrogen generation calculated in the attached report.
These conf irme'd calculations will not be
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. NOV 2 6 19.74 Although the numerical guidelines of proposed Appendix I t6 Part 50 of Title 10 of the Code of Federal Regulations are not yet effective, the Regulatory staff is applying these guidelines for current light
. water reactor licensing acttons.
In general, the operations of a
. plant are controlled by the Technical Specifications appended to the.*
operating.license s.o*that annual total body doses to.individuals living near the plant should not exceed 5 millirem due to radioactive mate.rials in liqu]d or gaseous effluents, and annual doses to any*
organ should not exceed 15 millirem due to radioiodine and particulate material in gaseous effluents. The potential doses are controlled by restrictions on the rate of liq~id and gaseous radiological effluent releases and are further monitored through radiological environmental
~onitoring programs.
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