ML111570296: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 5: Line 5:
| author name =  
| author name =  
| author affiliation = Omaha Public Power District
| author affiliation = Omaha Public Power District
| addressee name = Wilkins L E
| 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

Licensee Slides from 5/26/11 Pre-Submittal Meeting to Discuss NFPA 805 Fire Protections
ML111570296
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
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
  • 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
  • License Condition being revised
  • Technical Specification(s) being revised
  • Reviewed regulatory orders and exemptions
  • 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
  • Radioactive release per FAQ 09-0056 8 8 Compliance with NFPA 805
  • 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
  • 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
  • Peer review complete
  • No major technical issues

-Documentation

-Modeling enhancements

-Facts & Observations (F&O)

  • 50% Suggestions
  • 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
  • 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