ML111570296: Difference between revisions
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| author name = | | author name = | ||
| author affiliation = Omaha Public Power District | | author affiliation = Omaha Public Power District | ||
| addressee name = Wilkins L | | addressee name = Wilkins L | ||
| addressee affiliation = NRC/NRR/DORL/LPLIV | | addressee affiliation = NRC/NRR/DORL/LPLIV | ||
| docket = 05000285 | | docket = 05000285 | ||
Revision as of 15:46, 10 July 2019
| ML111570296 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun |
| Issue date: | 05/26/2011 |
| From: | Omaha Public Power District |
| To: | Lynnea Wilkins Plant Licensing Branch IV |
| Wilkins, L E, NRR/DORL/LPL4, 415-1377 | |
| References | |
| Download: ML111570296 (18) | |
Text
Nuclear Regulatory Commission NFPA 805 Fire Protection Transition Pre-Submittal Briefin g gOmaha Public Power DistrictFort Calhoun Nuclear Station 5/26/11
Introductions
- Omaha Public Power District
-Joe McManis-Manager Projects
-Tom Shudak -Sr. Engineer Programs
-Gaston Riva -Sr. Engineer Systems Analysis
-Bill Hansher -Supervisor Nuclear Licensing
-Donna Lippy
-Sr. Nuclear Licensing Engineer
- Engineering Planning and Management
-Francesco Pellizzari -Project Manager
- Westinghouse Electric Company
-Gerhard Samide -Project Manager
-Clarence Worrell -WEC Fire Risk Services Team 2 2 Agenda*Current Fire Protection Licensing Basis
- NFPA 805 Transition Project Overview
- Fire Protection Program Transition
- Compliance with NFPA 805
- Summary 3 3 Current Fire Protection Licensing Basis
- Fort Calhoun Station
-Single Unit PWR 1500 MWt Combustion Engineering
-Licensed to operate August 9, 1973
- CurrentLicensingBasis(CLB):
- Current Licensing Basis (CLB): -10 CFR 50 Section 50.48 (a) and (b)
-10 CFR 50 Appendix A General Design Criteria (GDC) 3
-10 CFR 50 Appendix R Sections III.G, III.J and III.O
-Appendix A to Nuclear Regulatory Commission (NRC) Branch Technical Position (BTP) APCSB 9.5-1
-Renewed Facility Operating License (OL) No. DPR-40 4 4 NFPA 805 Transition Project Overview*Date committed to transition -June 9, 2008
- Submittal date
-June 9, 2011
- License Amendment Request (LAR) -In final stages of assembly
- Plan a complete submittal 5 5 Fire Protection Program Transition
- License Condition being revised
- Technical Specification(s) being revised
- Reviewed regulatory orders and exemptions
- Transition majority of exemptions with clarifications 6 6 Fire Protection Program Transition
- Determined no significant hazards
- Implement 18 months after receipt of safety evaluation report
- Modifications completed within two refueling outages after receipt of safety evaluation report 7 7 Compliance with NFPA 805
- NFPA 805 Chapter 3 compliance
-Performance-based methods applied
-NoHemycorMT-No Hemyc or MT-Request approval of pyrocrete barrier
- Non-Power Operations per FAQ 07-0040
- Nuclear Safety Capability Assessment
-Fire Area b y Fire Area review y-Multiple Spurious Operations review for impact on deterministic requirements 9 9 Compliance with NFPA 805
- Nuclear Safety Capability Assessment
-Result:Result:*54 Fire Areas
- 42 Assessed Deterministic
- 12 Assessed Performance-based 10 10 Compliance with NFPA 805
- Recovery Action (RA) Feasibility Assessment
-Control Room RAs credited for Risk Reduction
-Remainin g RAs are Defense-in-De p th g p*Sustain Mode 3, Hot Shutdown, per FCS Technical Specifications
- Defines Safe and Stable
- 24 hours 11 11 Compliance with NFPA 805
- Modifications
-Recover or ensure the availability of Offsite Power
-Minimize or eliminate Variances from Deterministic Requirements (VFDR)
- Typical Modification
-Electrical Isolation
-Cable re-routing 12 12 Compliance with NFPA 805
- Monitoring
-Following Draft FAQ 10-0059
-Phased a pproach for p ro grampppg-Screening criteria to determine risk significant fire compartments using:
- Risk Achievement Worth and either
- Core Damage Frequency or
- Large Early Release Frequency 13 13 Fire Probabilistic Risk Assessment
- Fire PRA built using NUREG/CR-6850 & Supp 1
- Peer review complete
- No major technical issues
-Documentation
-Modeling enhancements
-Facts & Observations (F&O)
- 50% Suggestions
- F&Os resolved 14 14 Fire Probabilistic Risk Assessment
- NUREG/CR-6850 alternative treatments:
-Severity factor / non-suppression probability for electrical cabinets
-Pump fire frequency
-Diesel Generator severity factor / non-suppression probability
- Realism and focus on risk significant attributes
- Aligns with operating experience 15 15 Fire Probabilistic Risk Assessment
- Severity factor / non-suppression probability for electrical cabinets
-In review by Industry New Methods Peer Review Panel
- Pumpfirefrequency Pump fire frequency-To be superseded by pump fire frequency method currently in review by Panel *Diesel Generator severity factor / non-suppression probability
- To be submitted to Panel by June 9, 2011.
16 16 Fire Probabilistic Risk Assessment
- Draft FAQ 08-0050 Non-Suppression Probability
-Available version when FPRA task being performed-Current version does not impact conclusions
- Low frequency of fire events where FCS Fire PRA credits manual suppression 17 17 Summary*Fire Risk Evaluations
-Recovery Actions have no adverse impact
- Net change in riskMRlGid1174Rii1
-M eets R egu latory G u id e 1.174 , R ev i s i on 1*Modifications and Implementation Actions
-Compliance with NFPA 805 18 18