ML13239A340

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Presentation for NRC Projects
ML13239A340
Person / Time
Site: Oconee Duke energy icon.png
Issue date: 08/27/2013
From:
Duke Energy Carolinas, Duke Energy Corp
To:
NRC/RGN-II
References
Download: ML13239A340 (48)
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Text

Oconee Nuclear Station Major Projects Update, August 28, 2013

Duke Participants Preston Gillespie, Senior VP, Nuclear Operations Scott Batson, Site VP, Oconee Nuclear Station Dave Baxter, VP, Regulatory Project Completion Ed Burchfield, Engineering Manager, Oconee Nuclear Station Jim Fuller, General Manager, Oconee PSW Project Bob Guy, Manager, Oconee Organizational Effectiveness Dean Hubbard, Licensing Manager, Oconee Nuclear Station Chris Nolan, Director, Fleet Regulatory Affairs For Information Only 2

Agenda Opening Remarks Scott Batson Protected Service Water (PSW) Jim Fuller PSW Licensing Update Dave Baxter Digital Reactor Protective System/Engineered Safeguards Ed Burchfield (RPS/ES)

National Fire Protection Association (NFPA) 805 Ed Burchfield Main Steam Isolation Valves (MSIVs) Ed Burchfield Fukushima Ed Burchfield External Flooding Dean Hubbard Closing Comments Preston Gillespie For Information Only 3

Opening Remarks Scott Batson Site Vice President, Oconee Nuclear Station For Information Only 4

Projects Update Jim Fuller General Manager, Oconee PSW Project For Information Only 5

PSW PSW Project - Current Overall Status Milestone One required items completed and turned over to Operations on August 2nd Remaining five milestones on track For Information Only 6

PSW Milestone 1 - Commercial Power Path to the Standby Shutdown Facility -

October 1, 2013 Completed Items Milestone One required items completed and turned over to Operations on August 2nd Selected Licensee Commitment 16.9.22 implemented July 31, 2013 to track unavailability of PSW power via Maintenance Rule 13% Estimated Fire Core Damage Frequency improvement For Information Only 7

PSW Milestone 1 - PSW Building For Information Only 8

PSW Milestone 1 - PSW Building 13.8KV, 4160VAC and 600VAC Switchgear Equipment and Transformers For Information Only 9

PSW Milestone 1 - PSW Building 125VDC System Equipment For Information Only 10

PSW Milestone 1 - PSW Building HVAC Equipment For Information Only 11

PSW Milestone 2 - Power Path From Keowee Hydro - July 18, 2014 Completed Items Keowee Unit 2 outage implementation of Keowee AC Power Tie-ins and Keowee Control Cable Re-route Completed 6 of 14 discrete online control cable blocks of work Scheduled Activities Keowee Unit 1 outage Keowee Unit 2 bus tie-in outage Completion of remaining online Keowee Control Cable Re-route work scopes PSW Building outage for Keowee power cable tie-in Completion of integrated load test For Information Only 12

PSW Milestone 2 - PSW Project Keowee Unit 2 13.8KV Switchgear Control Switches For Information Only 13

PSW Milestone 2 - Keowee Unit 2 Transition Junction Box External For Information Only 14

PSW Milestone 2 - PSW Project Keowee 13.8KV Switchgear Cabinet For Information Only 15

PSW Milestone 3 - Power Path From PSW to HPI System - October 1, 2014 In Progress Items Unit 2 pre-outage work Termination of 4160VAC power cable and control circuit installation and testing Testing on PSW Power AC and DC panel boards A PSW engineered equipment qualification issue has been recently identified Action plan to resolve issue is being developed to ensure the milestone date is not impacted Scheduled Activities Unit 2 (Fall 2013) Testing Work Scope Continuity verification of 4160V Switchgear B6T-4 Control Circuit Rotational checks 2A and 2B HPI pumps from PSW and Normal power Functional verification of valves using PSW and Normal power Units 1 and 3 Overlap Testing Work Scope Rotational checks A and B HPI pumps from PSW power for each unit Phase rotation checks on 600VAC MCCs on PSW power for each unit For Information Only 16

PSW Milestone 4 - Align PSW Pump to Steam Generators - June 3, 2015 Completed Items Installation of pre-outage piping and pipe supports Scheduled Activities Completion of 48 Auxiliary Building / Reactor Building Engineering Change Packages (ECPs) to support Phase I cooling Pre-outage Station ASW system demolition and installation of PSW system Integrated PSW System testing For Information Only 17

PSW Milestone 4 - PSW Pump Room For Information Only 18

PSW Milestone 4 - 2000 HP Pump/Motor For Information Only 19

PSW Milestone 5 - PSW System Complete - February 4, 2016 Remaining PSW Project Work Scope

  • Units 1, 2, and 3 Pressurizer Heater and Vital I&C Battery Charger Repowering from PSW
  • Six 600VAC Automatic Transfer Switches (Two per unit)
  • Eight 600VAC Manual Transfer Switches (Two for Unit 1 and Three each for Units 2 and 3)
  • 18 cables left to pull from PSW Building to Auxiliary Building through TSB Cable Vault and Manhole 7
  • Cable infrastructure installation in the Auxiliary Building
  • Units 1, 2, and 3 Vital I&C Cable Re-routes
  • Installation and termination of twenty-four 1000MCM single conductor cables
  • 16 cables have been pulled, 8 remain
  • Installation of cable infrastructure
  • Tie-ins to new Automatic Transfer Switches
  • Phase II of Auxiliary Building and Reactor Building Cooling Project For Information Only 20

PSW Milestone 6 - Satisfy the Requirements of NFPA 805 - November 25, 2016 Transition License Conditions The Transition License Conditions will be discussed by Ed Burchfield in the NFPA 805 presentation For Information Only 21

Projects Update Dave Baxter VP, Regulatory Project Completion For Information Only 22

PSW Licensing Update Overall Approach: PSW TS and UFSAR revision, HELB Mitigation Strategy, then Tornado Mitigation Strategy PSW TS and UFSAR revision completion plan PSW Design Basis - Define design basis for initial installation - Complete Thermal-Hydraulic Analysis - Perform analysis for NFPA 805 case - Complete RB/AB Cooling - RAI response addressing Alternate Cooling System design criteria -

Complete PSW TS and UFSAR - Finalize TS, TS bases, and UFSAR - Complete Expect NRC SER 90 to 180 days after submittal For Information Only 23

Projects Update Ed Burchfield Engineering Manager For Information Only 24

RPS/ES Upgrade Reactor Protective System/Engineered Safeguards Unit 1 RPS/ES Installation Complete (Spring 2011)

Unit 3 RPS/ES Installation Complete (Spring 2012)

Unit 2 RPS/ES Installation Scheduled for Fall 2013 For Information Only 25

NFPA 805 Project Status NRC Safety Evaluation issued December 29, 2010 Program Implemented January 1, 2013 All items not related to PSW are complete or on schedule Turbine Building / Auxiliary Building wall penetrations modifications completed Triennial fire inspection performed in August For Information Only 26

NFPA 805 Remaining Items to Complete:

PSW modifications Once the PSW modifications are complete Incorporate the PSW modifications into site documents Confirm that the risk decrease from installation of PSW bounds the transition risk Complete the analysis of non-power operation fire impacts Complete remaining modifications Fire detection modifications Purge Room wall modifications For Information Only 27

NFPA 805 Ongoing actions until modifications are complete:

Appendix R required fire watches continue to be performed New NFPA 805 fire watch program has been established Additional compensatory actions remain in place until PSW is completed Oconees fire safety has benefited from the implementation of NFPA 805, and will continue to improve upon PSW completion For Information Only 28

Main Steam Isolation Valves Project Status MSIV schedule re-prioritized based on higher safety significance projects PSW NFPA 805 Fukushima Modifications For Information Only 29

Fukushima Modifications FLEX Modifications Based on use of SSF for Phase 1 Coping Duke Project Approval Process complete; Kickoff meeting conducted Implementation Schedule: U2 (Fall 2015), U3 (Spring 2016), U1 (Fall 2016)

S/G Make-up Capability RC Make-up Capability CCW Embedded Water Transfer Capability Primary Repower Alternate Repower SFP Makeup FLEX Equipment Storage Building For Information Only 30

Fukushima Modifications Spent Fuel Pool Level Instrumentation (SFPLI) Modifications Duke Project Approval Process complete; Kickoff meeting conducted Implementation Schedule: U1 & U2 (Fall 2015), U3 (Spring 2016)

Primary and backup channel for each spent fuel pool Both channels will use wave guided radar technology For Information Only 31

Fukushima Modifications Flood Modifications (50.54(f) Request Letter)

Fukushima Response includes External Flood for Oconee Flood Modifications will be discussed in more detail later in the presentation For Information Only 32

Projects Update Dean Hubbard Licensing Manager, Oconee Nuclear Station For Information Only 33

Fukushima Flooding Response Fukushima Flooding Response - Overview Oconees flooding evaluation has been updated to meet Fukushima response requirements All extreme external flooding events have been evaluated Interim actions have been put in place for postulated flooding events The interim actions for the postulated dam failure have been inspected by the NRC Permanent integrated flooding responses are in development Flooding modifications for a postulated dam failure are being designed to support 2016 implementation For Information Only 34

External Flooding Flooding Hazard Reevaluation Status Hazard Reevaluation Report (HRR) - Completed March 12, 2013 Includes all external flooding events per NUREG 7046 Dam failure analysis using Xu & Zhang 2009 (with alternate breach sensitivity reviews)

Dam seismic fragility gap analysis using 2007 fragility analysis with 1989 Electric Power Research Institute (EPRI) Uniform Hazard Spectrum (UHS) inputs Probable Maximum Precipitation (PMP) analysis using HMR-51, 52 with no change based on review of updated U.S. Bureau of Reclamation (USBR), December 2011 PMP Study for the Southeast Breach methodology question response (parallel paths):

Alternate Breach Method Development - Targeted November 2013 Von Thun and Gillette McDonald & Langridge-Monopolis Froehlich Xu & Zhang Independent Review for Jocassee - Targeted November 2013 For Information Only 35

External Flooding - Compressed Schedule Integrated Assessment & Modification Development Integrated Assessment (IA) started January 2013 Conducted in parallel with Hazard Reevaluation Report (HRR completed)

Targeted to complete by December 2013 using current HRR (due March 12, 2015)

Contractor involved with NEI flooding taskforce on IA development Modification design firm mobilized and working on detailed design Dam failure protection & mitigation modifications Local Intense Precipitation updated hazard design study Objective to maintain a free flowing site For Information Only 36

External Flooding High Level Timeline 2013 January - Integrated Assessment Team kickoff February - Peer Review team lead in place March - Hazard Reevaluation completed & controlling flood parameters identified May - Completed Integrated Assessment (IA) evaluation of existing flood protection o June - Target date for NRC approval of HRR (moved based on Xu & Zhang review)

July - Completed IA evaluation of protection/mitigation o September - Determine IA protection/mitigation strategy & mod scope o October - Complete first draft of IA o December - Target for submittal of the IA to the NRC 2014 o Target date for NRC approval of the IA For Information Only 37

External Flooding Flooding Modification Options - Postulated Dam Failure Major modifications will be required regardless of the breach method applied Modification options (depending on the final dam failure assumptions)

1. Discharge Diversion Wall
2. Power block east bank armoring
3. Intake dike armoring
4. Turbine Building drain isolation
5. L-wall on the Intake Dike
6. Hardening of the Keowee and West Saddle dam with roller compacted concrete For Information Only 38

Dam Failure Modifications Options 6

Jocassee Dam

1. Discharge Diversion Wall
2. Power block east bank armoring
3. Intake dike armoring
4. Turbine Building drain isolation
5. L-wall on the Intake Dike
6. Hardening of the Keowee and West Saddle dam with roller compacted concrete For Information Only 39

HRR Flooding Modification Options - Postulated Dam Failure Modifications selected based on the Fukushima Hazard Reevaluation Report to respond to a postulated upstream dam failure:

1. Discharge Diversion Wall
2. Power block east bank armoring
3. Intake dike armoring
4. Turbine Building drain isolation For Information Only 40

Discharge Diversion Wall T WALL TOP EL SCALABLE BASED ON MAX WATER LEVEL SHEET PILE OR L WALL TOP OF TOP EL 822 DEADMAN EL 816 TOP EL 815 TOP OF DEADMAN VARIES STEP TO MEET WALL HEIGHT AND GRADE CONDITIONS MAIN ACCESS ROAD For Information Only 41

East Bank Armoring Discharge Canal 230 KV Switchyard 525 KV Switchyard Site grade, east yard Intake Dike 42 For Information Only For Information Only Site grade, east yard

East Bank Armoring INTERLOCKING BLOCKS w/ CABLE ANCHORS CABLE CABLE SLEEVE LENGTH AS DESIRED WASHER For Information Only 43

Intake Dike Armoring For Information Only 44

Turbine Building Drain Isolation For Information Only 45

In Summary Hazard Reevaluation Report (HRR) Submitted on March 12, 2013 Parallel paths to address breach method questions Alternate Breach Method Development - Targeted November 2013 Independent Review of the HRR breach method - Targeted November 2013 Integrated Assessment (IA) started January 2013 Targeted to complete by December 2013 using current HRR (due March 12, 2015)

Modification design firm mobilized and working on detailed design Major modifications will be required regardless of the breach method applied Dam failure flood mitigation modifications must be completed by June 2016 For Information Only 46

Closing Comments Preston Gillespie Senior Vice President, Nuclear Operations For Information Only 47

Acronyms AB - Auxiliary Building PSW - Protected Service Water ASW - Auxiliary Service Water RAI - Request for Additional Information CCW - Condenser Circulating Water RB - Reactor Building ECP - Engineering Change Package RC - Reactor Coolant EOC - End of Cycle RPS/ES - Reactor Protective System/Engineered Safeguards HELB - High Energy Line Break S/G - Steam Generator HPI - High Pressure Injection SER - Safety Evaluation Report HRR - Hazard Reevaluation Report SLC - Selected Licensee Commitment I&C - Instrumentation and Control SFP - Spent Fuel Pool IA - Integrated Assessment SSF - Standby Shutdown Facility KV - Kilovolt TS - Technical Specifications MCC - Motor Control Center UFSAR - Updated Final Safety Analysis Report NEI - Nuclear Energy Institute VAC - Volts Alternating Current NFPA - National Fire Protection Association VDC - Volts Direct Current For Information Only 48

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