ML19329D801: Difference between revisions

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SAFETY EVALUATION FOR RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (FCR      79-114)
SAFETY EVALUATION FOR RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (FCR      79-114)
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   /        an unreviewed safety questions such that:                                    .
   /        an unreviewed safety questions such that:                                    .
a) the probability of occurrence or the consequences of an accident or f
a) the probability of occurrence or the consequences of an accident or f
malfunction of equipment important to safety previously evaluated in the
malfunction of equipment important to safety previously evaluated in the sr.fety analysis report may be increased.
-
sr.fety analysis report may be increased.
b) the possibility for an accident or malfunction of a different type than any l
b) the possibility for an accident or malfunction of a different type than any l
evaluated previously in the safety analysis report may be created c) the margin of safety as defined in the basis for any technical specification is reduced.
evaluated previously in the safety analysis report may be created c) the margin of safety as defined in the basis for any technical specification is reduced.

Latest revision as of 21:29, 31 January 2020

Safety Evaluation for Radiological Effluent Tech Specs. Supports Changes
ML19329D801
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/16/1979
From: Myers C
TOLEDO EDISON CO.
To:
Shared Package
ML19282C207 List:
References
FCR-79-114, NUDOCS 8003180312
Download: ML19329D801 (1)


Text

_ , . . . . _ . . . . . .

  • O -

SAFETY EVALUATION FOR RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS (FCR 79-114)

The Radiological Effluent Technical Specifications (RETS) have been developed at ,

the request of the US Nuclear Regulatory Commission. The requested form represented the addition of new requirements to insure compliance with portions .

of 10CFR50, 10CFR20 and 40CFR190 as well as reorganizing some of the present ,

technical specifications.

The attached technical specification changes address portions of 10CFR50, 10CFR20 and reorganize current portions of sections A and B of the Davis-Besse Nucicar Power Station Unit 1 Technical Specifications. None of these represent

/ an unreviewed safety questions such that: .

a) the probability of occurrence or the consequences of an accident or f

malfunction of equipment important to safety previously evaluated in the sr.fety analysis report may be increased.

b) the possibility for an accident or malfunction of a different type than any l

evaluated previously in the safety analysis report may be created c) the margin of safety as defined in the basis for any technical specification is reduced.

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