ML18024A358: Difference between revisions
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{{#Wiki_filter:BFN-21 14.3-1 14.3 UNACCEPTABLE SAFETY RESULTS FOR ACCIDENTS | {{#Wiki_filter:BFN-21 14.3-1 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 | ||
: 5. Overexposure to radiation of plant operation personnel in the control room. 6. Peak enthalpy of the fuel in | °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 exce ss of 280 cal/gm for the control rod drop accident.}} |
Revision as of 05:13, 29 June 2018
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 14.3-1 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.
- 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 exce ss of 280 cal/gm for the control rod drop accident.