ML18024A358: Difference between revisions
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| number = ML18024A358 | | number = ML18024A358 | ||
| issue date = 10/05/2017 | | issue date = 10/05/2017 | ||
| title = | | 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 | ||
Line 14: | Line 14: | ||
| page count = 1 | | page count = 1 | ||
}} | }} | ||
=Text= | |||
{{#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. | |||
: 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}} |
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