ML18024A358: Difference between revisions
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 16: | Line 16: | ||
=Text= | =Text= | ||
{{#Wiki_filter:BFN-21 14.3 | {{#Wiki_filter: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. | : 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 | : 2. Fuel Cladding temperature in excess of 2200°F for pipe breaks. | ||
°F for pipe breaks. | |||
: 3. Nuclear system stresses in excess of that allowed for accidents by applicable industry codes. | : 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. | : 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. | : 5. Overexposure to radiation of plant operation personnel in the control room. | ||
: 6. Peak enthalpy of the fuel in | : 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
ML18024A358 | |
Person / Time | |
---|---|
Site: | Browns Ferry |
Issue date: | 10/05/2017 |
From: | Tennessee Valley Authority |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML18018A778 | List:
|
References | |
Download: ML18024A358 (1) | |
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