ML18024A358: Difference between revisions
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: 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. 6. Peak enthalpy of the fuel in excess of 280 cal/gm for the control rod drop accident. | : 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.}} | ||
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Revision as of 02:30, 18 May 2018
ML18024A358 | |
Person / Time | |
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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 excess of 280 cal/gm for the control rod drop accident.