ML13066A740

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Licensee Slides from 3/7/13 Pre-Application Meeting with Pacific Gas and Electric Company(Tac MF0687 & MF0688)
ML13066A740
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 03/07/2013
From:
Pacific Gas & Electric Co
To:
Plant Licensing Branch IV
Polickoski J
References
TAC MF0687, TAC MF0688
Download: ML13066A740 (24)


Text

Diablo Canyon Power Plant NFPA 805 Transition Project Pre-Submittal Meeting with NRC 03/07/2013

2

Introductions

PG&E Representatives Steve BakerManager, Design Engineering Rasool BaradaranSupervisor, Probabilistic Risk Assessment (PRA)

Michael RichardsonRegulatory Services Paul Bemis....Strategic Projects Oversight (SPO)

John PyoFPRA / FREs Lead (by phone)

Brent Waggener...Independent Verifier (by phone)

Project Consultants - EPM Ted StantonSite Modifications Technical Coordinator Paul Ouellette....Division Manager, Safety & Systems Analysis (by phone)

Mark Crompton.Project Manager (by phone)

Jim Gregerson......Site Project Coordinator (by phone)

Ray Dyer..Site Technical Lead (by phone)

Meeting Objectives 3

  • Last Presentation before submittal in June
  • Present / Discuss LAR
  • Receive feedback from Staff on LAR acceptability and information

Meeting Agenda 4

  • Overview of NFPA 805 Transition Background
  • Discuss Preliminary Results
  • Internal Events/Internal Flooding, Fire, Seismic PRAs Peer Reviewed to RG 1.200 rev. 2; Turbine Building Fragilities included
  • Post-Transition Plant Risk-Includes IE/IF, Seismic and Fire PRAs in CDF
  • Discuss Post-Submittal Implementation
  • Proposed Modifications
  • Other Implementation Items
  • Questions / Discussion / Feedback

Diablo Canyon Power Plant 5

  • 4-Loop Westinghouse NSSS
  • 1150 MWe / Unit
  • Initial Operating License:
  • Unit 1: 1984
  • Unit 2: 1985 Owned and Operated by Pacific Gas & Electric Company (PG&E)

6 Current Fire Protection Licensing Basis

  • License Conditions 2.C.(5) (Unit 1) and 2.C.(4) (Unit 2)
  • Branch Technical Position APCSB 9.5-1 Appendix A
  • Current Deviations
  • 39 Current Deviations
  • Current Plan: Transition 11 Deviations

7 NFPA 805 Transition Overview

  • License Amendment Request (LAR) submittal date: June 28, 2013
  • Program Improvements Realized:
  • Development and Peer Review of IE /IF, Seismic PRAs as well as Fire PRA per RG 1.200 revision 2
  • Multiple Fire Risk Evaluation Iterations
  • Seismic Fragilities complete in Turbine Building; remainder in progress
  • DCPPs reported Total CDF/LERF represent true overall risk
  • Additional 3rd party reviews by Industry/Legal/Academic Experts of:
  • Fire Models (complete & planned)
  • Circuit Analysis (complete)
  • NUREG CR6850 compliance (complete)
  • LAR Package (planned)
  • LAR Transition Report draft complete
  • Preparation and Internal Review in Progress

8 NFPA 805 Transition Guidance

  • Regulatory Guides:
  • 1.205 revision 1
  • 1.200 revision 2
  • 1.174 revision 1
  • Industry Guidance (FAQs, LAR Template Revision 1P, etc.)

9 NFPA 805 TRANSITION PROJECT ORGANIZATION CHART DIABLO CANYON POWER PLANT

10 Fundamental FP Program & Design Elements (LAR Attachment A)

  • 135 Total Sections
  • Note: Several Sections Require Two Responses (e.g., Complies with use of Existing Engineering Equivalency Evaluation (EEEE) and Required Action)
  • Complies: 84
  • Complies with Clarification: 6
  • Complies by previous NRC Approval: 10
  • Complies with use of EEEE: 13
  • Submit for NRC Approval: 6
  • Complies with Required Action: 19

11 Non-Power Operations Review (LAR Attachment D)

  • High Risk Evolutions
  • Consistent with Existing Procedure
  • AD8.DC50, Outage Safety Management
  • Mid-Loop (Plant Operating State (POS) 2)
  • Consistent with FAQ 07-0040
  • Pinch Points Identified:
  • Unit 1: 45 areas containing pinch points
  • Unit 2: 47 areas containing pinch points

12 Radioactive Release Review (LAR Attachment E)

  • Performed per NEI 04-02, revision 2 (4.3.4 and Attachment G) supplemented by FAQ 09-0056
  • Evaluated by Fire Area / Fire Zone
  • Pre-Fire Plans Revisions & Training Updates Scheduled
  • Tracked as Implementation Item (IMP-038)

13 Nuclear Safety Capability Assessment

  • 110 Fire Areas in Power Block (LAR Attachment C)
  • 44 Deterministic (4.2.3) Fire Areas
  • 66 Performance-Based (4.2.4) Fire Areas
  • Safe and Stable (LAR Section 4.2.1.2)
  • Hot Standby (Mode 3)
  • Qualitative Discussion of Long-Term Safe and Stable

14 Recovery Action Transition (LAR Attachment G)

  • As of current LAR draft:
  • Unit 1:
  • 9 Credited Recovery Actions
  • Unit 2:
  • 9 Credited Recovery Actions
  • Additional Defense-in-Depth Actions
  • Not Credited in PRA

15 Monitoring Program (LAR Section 4.6)

  • FAQ 10-0059 Guidance
  • High Safety Significance / FPRA Components:
  • Low Safety Significant / NPO, Rad Release, FP Program:
  • System and Program Health Monitoring

16 Fire PRA (LAR Section 4.5)

  • Based on Peer Reviewed Internal Events PRA
  • Fire PRA Peer Review (2010)
  • Facts and Observations:
  • 80% Addressed / Closed
  • Remainder scheduled to complete by time of submittal
  • No Unreviewed Methods Used
  • Peer Reviewed

Overall Plant Risk 17

  • Based on Peer Reviewed Models with Additional Refinements
  • Includes proposed modifications
  • Updates still in progress; will complete by time of submittal
  • SSHAC Level 3 to be complete by March 12, 2015 (consistent with 50.54(f) letter)
  • Fire CDF: ~5 x 10-5 / unit (still in refinement)
  • Overall Plant CDF: ~8.5 x 10-5 / unit (still in refinement)
  • Includes Fire, IE/IF, and Seismic

Fire Risk 18

  • Based on Fire Risk Evaluations, revision 0
  • Includes proposed modifications
  • Revision 1 in progress based on self-assessment of Fire PRA and modeling
  • Will be complete by time of LAR Submittal
  • Fire CDF:
  • Unit 1: Goal ~5 x 10-6 (still in refinement)
  • Unit 2: Goal ~5 x 10-6 (still in refinement)
  • Fire LERF:
  • Unit 1: Goal ~5 x 10-7 (still in refinement)
  • Unit 2: Goal ~5 x 10-7 (still in refinement)

19 Regulatory Guide 1.174 Risk Assessment

  • Planned (post transition, post modification) Risk in Region II

Plant Risk due to VFDR(s) ~5x10-6

~8.5x10-5 Overall Plant Risk

20 Implementation (1/2)

(LAR Attachment S)

  • Four Proposed Modifications (each applicable to both units)
  • Incipient Fire Detection Installation
  • SSPS and Cable Spreading Room Cabinets
  • RCP Seal Upgrade
  • ERFBS Installation and Circuit Re-Route
  • Hot Shutdown Panel Upgrades

21 Implementation (2/2)

(LAR Attachment S)

  • 32 Implementation Items
  • Significant Implementation items include:
  • Finalization of Configuration Control process revisions (in progress)
  • Review of PRA model following implementation of modifications
  • Incorporation of Code Conformance Review (including Codes of Record) into Engineering Equivalency Evaluation (EEE) program
  • Revise Pre-Fire Plans and Training Materials to address Radioactive Release Requirements
  • Implementation Items to be Complete prior to Implementation

22 Post-Implementation Program Maintenance

  • Change Management Plan
  • Per Plant Procedure
  • Includes Detailed Plan of Actions and Milestones, Tracked in SAP
  • Transition Plan
  • Maintain close Fire Protection Engineering group liaison with NFPA 805 Transition Project throughout RAI and Implementation phase

23 Summary

  • Complete LAR to be submitted by June 28, 2013
  • In-process reviews along with planned reviews by Industry/Legal/Academic experts
  • In-house PRA staff intimately involved with PRA development and upgrade; Presented/Responded to Peer Review Teams
  • Four Proposed Modifications to improve plant fire risk
  • Transition:
  • Developing procedure changes and training programs
  • Complete modifications not later than 2R20, spring 2018

Comments? 24 Questions?

Feedback?