ML18024A358: Difference between revisions

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| number = ML18024A358
| number = ML18024A358
| issue date = 10/05/2017
| issue date = 10/05/2017
| title = Browns Ferry Nuclear Plant Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.3 Unacceptable Safety Results for Accidents
| title = Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.3 Unacceptable Safety Results for Accidents
| author name =  
| author name =  
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
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=Text=
=Text=
{{#Wiki_filter:BFN-21 14.3-1 14.3  UNACCEPTABLE SAFETY RESULTS FOR ACCIDENTS 1. Radioactive material release to such an extent that the guideline values of 10 CFR 50.67 would be exceeded. 2. Fuel Cladding temperature in excess of 2200°F for pipe breaks.
{{#Wiki_filter:BFN-21 14.3 UNACCEPTABLE SAFETY RESULTS FOR ACCIDENTS
: 3. Nuclear system stresses in excess of that allowed for accidents by applicable industry codes.
: 1. Radioactive material release to such an extent that the guideline values of 10 CFR 50.67 would be exceeded.
: 4. Containment stresses in excess of that allowed for accidents by applicable industry codes when containment is required.
: 2. Fuel Cladding temperature in excess of 2200°F for pipe breaks.
: 5. Overexposure to radiation of plant operation personnel in the control room. 6. Peak enthalpy of the fuel in excess of 280 cal/gm for the control rod drop accident.  
: 3. Nuclear system stresses in excess of that allowed for accidents by applicable industry codes.
}}
: 4. Containment stresses in excess of that allowed for accidents by applicable industry codes when containment is required.
: 5. Overexposure to radiation of plant operation personnel in the control room.
: 6. Peak enthalpy of the fuel in excess of 280 cal/gm for the control rod drop accident.
14.3-1}}

Latest revision as of 03:10, 22 October 2019

Updated Final Safety Analysis Report (Ufsar), Amendment 27, 14.3 Unacceptable Safety Results for Accidents
ML18024A358
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/05/2017
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
Shared Package
ML18018A778 List: ... further results
References
Download: ML18024A358 (1)
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Text

BFN-21 14.3 UNACCEPTABLE SAFETY RESULTS FOR ACCIDENTS

1. Radioactive material release to such an extent that the guideline values of 10 CFR 50.67 would be exceeded.
2. Fuel Cladding temperature in excess of 2200°F for pipe breaks.
3. Nuclear system stresses in excess of that allowed for accidents by applicable industry codes.
4. Containment stresses in excess of that allowed for accidents by applicable industry codes when containment is required.
5. Overexposure to radiation of plant operation personnel in the control room.
6. Peak enthalpy of the fuel in excess of 280 cal/gm for the control rod drop accident.

14.3-1

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