ML14246A201
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| ML14246A201 | |
| Person / Time | |
|---|---|
| Site: | Perry  (NPF-058) |
| Issue date: | 09/03/2014 |
| From: | Ellen Brown Plant Licensing Branch III |
| To: | |
| Brown E, NRR/DORL/LPL3-1, 301-415-2315 | |
| References | |
| Download: ML14246A201 (1) | |
Text
DISCUSSION TOPICS FORTHCOMING NUCLEAR REGULATORY COMMISSION (NRC) MEETING WITH FIRSTENERGY NUCLEAR OPERATING COMPANY REGARDING FULL IMPLEMENTATION OF ALTERNATIVE SOURCE TERM PERRY NUCLEAR POWER PLANT THURSDAY, SEPTEMBER 18, 2014 The staff is looking for a discussion:
- 1. Describing how the direct shine dose from the control room emergency recirculation filter system was evaluated as a contributor to the control room loss of coolant accident (LOCA) dose consequence analysis;
- 2. Describing the calculation of the dispersion factors used in the technical support center (TSC) dose consequence analysis; and,
- 3. Describing the basis for the use of one set of control room dispersion factors for all release points evaluated in the alternative source term accident dose consequence evaluations including the contributions to the LOCA dose as well as the control rod drop accident and the main steam line break outside of containment.