ML15279A499
| ML15279A499 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/08/2015 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Chereskin A | |
| References | |
| Download: ML15279A499 (7) | |
Text
NRC Meeting October 8, 2015 CCNPP NFPA 805 License Amendment Application
2 Agenda
Current Licensing Status:
PRA-3:
Using NRC template for confirmation of RAI status
Adding Fire Modeling RAIs to the listing
No questions regarding input provided by the NRC.
RG 1.174 limit margin
Delta CDF
Delta LERF
Margins and delta LERF Small margins Significance of the limit
Compliant Plant Definition for Cable Spreading Room
3 CCNPP Team Members:
Exelon/CCNPP Representatives
Jeff Stone - Exelon Senior FPRA Manager
Jim McQuighan - Exelon Manager, NFPA 805
Ron Reynolds/Pat Furio - Exelon Principal Regulatory Engineer
Rob Cavedo - Exelon Senior Staff FPRA Engineer
Pat Pringle - Exelon Senior PRA analyst
Paul Darby - Exelon NFPA 805 Electrical Engineer
Usama Farradj - FPRA consultant
Tom Daniels - FPRA consultant
Mark Graham - FPRA consultant
Mark Schairer - Fire modeling consultant
Jeff Quinn - NFPA 805 consultant
4 Current Licensing Status
CCNPP NFPA 805 Transition Request Submittal 09/24/2013
NRC On-Site Audit and Draft RAIs 12/12/2014
CCNPP Submittal of last follow-up RAIs responses 08/13/2015
Public Meeting to Discuss FPRA Results 10/08/2015
Submission of Final Results (Attachments C, G, S & W) to be discussed.
NRC Issues Safety Evaluation to be discussed.
5 Fire PRA Status: PRA-03
Necessary Fire Modeling is complete.
Total risk quantification results are in.
Total Delta Risk, Risk of Recovery Actions will be evaluated IAW RG 1.174 criteria.
Final Quantification/documentation has begun.
The final results will accompany the response to RAI PRA 3, 19a and 19d.
Attachment C, G, S and W updates will be transmitted with the PRA RAI-3 response.
Methodology for PRA 03 will be the same as post transition, no outstanding items with respect to Fire PRA methodology are expected at the time of issue of the final RAI 03 response.
6 RG 1.174 Delta Risk Criteria.
Discussion of Results:
Total CDF
Total LERF
delta CDF
delta LERF
Significance of delta LERF.
Discussion of margin.
Conservatisms in the analysis Defense in depth measures/discussions.
Impact on NRC review
Impact if limited to delta LERF
7 ML15049A100: Delta Risk for Cable Spreading Room
Potential use of approach in the ML15049A100 (public meeting with NextEra/St. Lucie) for the Calvert Cliffs Cable Spreading Rooms
For Control Room abandonment scenarios
Address VFDRs associated with Primary Control Station (Aux Shutdown Panel) only
For non-abandonment scenarios
delta risk would only be applicable to operator actions credited outside the control room (including actions at Primary Control Station)
no train separation VFDRs (unless they result in operator actions outside the control room)