ML12158A344
| ML12158A344 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/06/2012 |
| From: | Progress Energy Co |
| To: | Farideh Saba Plant Licensing Branch II |
| Saba, Farideh | |
| References | |
| Download: ML12158A344 (19) | |
Text
Brunswick Nuclear Plant Brunswick Nuclear Plant Units 1 and 2 TS 3.8.1 Diesel Generator Completion Time Extension Completion Time Extension License Amendment Request Pre-Submittal Meeting June 7, 2012
Agenda Agenda
Introductions / Opening Remarks
License Amendment Request (LAR) Overview
Project Overview
Probabilistic Risk Assessment (PRA) Overview 2
Introduction/Opening Remarks Nuclear Safety - Emergency AC Power
EDG Collector Rings Nuclear Safety Emergency AC Power
Switchyard Breaker/Panel/Relay Replacements
27SX-1 Relay UV/DUV Relays
UV/DUV Relays
Switchyard Insulator Coatings
Air Start Modification
14 Day LCO EDG y
3
LAR Overview - Proposed Change
Extend Technical Specification Diesel Generator (DG) Completion Time (CT) from 7 days to 14 days LAR Overview Proposed Change
Branch Technical Position (BTP) 8-8 LAR supported by PRA LAR supported by PRA BNP installing a 4MW non-safety Supplemental DG (SUPP-DG)
Capacity to bring affected unit to Cold Shutdown Capable of powering E bus within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of SBO event Capable of powering E-bus within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of SBO event Technical Specifications include:
Verify availability of SUPP-DG before entering extended CT A
il bili f SUPP DG h k d hif Availability of SUPP-DG checked once per shift Action should SUPP-DG become unavailable during extended CT Monthly Test 4
Emergency Diesel Generator Improvement Actions p
Action 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 EDG #2 Exhaust Bellows Allen Bradley Relays EDG Actions Completed Working Allen Bradley Relays Jacket Water TCV's SAMG DG's Capacitor Leakage EDG PM Evaluations Ultra Low Sulfur Fuel Latent Design Issues Scheduled Working Human Performance Issues High Quality Potentiometers GEMCO Control Switches Clean Fuel Tanks Refurbish JW Coolers Voltage Reg Replacement Eng/Procure Planning Install Install Install Install Air Start Configuration Eng/Plan/Install Install Collector Ring Replacement Governor Replacement Eng/Planning Eng/Planning Install Install Install 14 Day EDG LCO Eng/Planning Install EDG PM Optimization Rebuild Turbo Critical Spare Parts (Identif )
Critical Spare Parts (Identify)
Spare Generator Procure Fab Receive Generator Inspection Eng/Planning Eng/Planning Inspect Inspect Data Acquisition Eng/Planning Eng/Planning Install Digital Relays Study Eng/Planning Install Install Replace FO Buried Piping Eng/Planning Install New Safety Maintenance DG Spec Dvpmt Hold. Pending Fukishima recommendation resolution.
5 New Safety Maintenance DG p
p Loadbank to Support Online LOOP/LOCA Equivalent Eng/Planning Install Hold. Pending Fukishima recommendation resolution.
Project Overview Project Overview Project Status & Schedule 6
Note: Automatic Voltage Regulator (AVR)
PRA Includes: Internal Events, Internal Flooding, E t l E t
Hi h Wi d E t l Fl di Fi External Events, High Winds, External Flooding, Fire
All Completed Peer Reviews against ANS/ASME PRA Standard and RG 1 200 R2 Standard and RG 1.200 R2
Seismic has qualitative assessment 7
Results of Emergency Diesel Generator (EDG)
Risk Metric Results
Results of Emergency Diesel Generator (EDG)
Allowed Outage Time (AOT) Risk Evaluation Risk Metric Risk Metric Results Unit 1 Unit 2 Total CDF 4.2E-05 4.1E-05 Total CDF 8.5E-07 8.3E-07 Total LERF 3.7E-06 2.5E-06 Total LERF 4 8E-09 6 2E-09 Total LERF 4.8E-09 6.2E-09 Total ICCDP 4.3E-07 4.1E-07 Total ICLERP 2.0E-09 3.5E-09 8
Brunswick Nuclear Plant (BNP) Internal Events Peer Review June 2010 All Supporting Requirements (SR) Reviewed Resolved to Capability Category (CC) II except for 7 Findings and Observations (F&Os) 4 D t ti i
4 Documentation issues 3 LERF SRs at CCI 9
PRA Overview PRA Overview BNP External Events High Winds/External Flooding Peer Review January 2012 Peer Review January 2012 All Supporting Requirements Reviewed High Winds High Winds 3 F&Os remain on documentation External Flooding External Flooding All F&Os resolved 10
PRA Overview PRA Overview Significant External Events Conservatisms High Winds/ External Flooding Some Operator Actions could be Credited Some Operator Actions could be Credited 11
Fire PRA Fire PRA Fire PRA Overview Important Fire Areas and Scenarios Fire PRA Peer Review Fire PRA Peer Review Current Status 12
Fire PRA Overview Fire PRA Overview Methods Similar to Harris Nuclear Plant (HNP)
Application Application
Used Accepted Alternatives (e.g., FAQ 08-0046) p
(
g,
)
RG 1.200 Peer Review Process Methods Beyond NUREG/CR-6850
The BNP Fire PRA calculates using:
A Severity Factor 0.1, Where 90% of the Fires are Contained Within the Motor Control Centers (MCC)
Heat Release Rate (HRR) Severity Factors are Treated Independently, Similar to Other Cabinets
Method was Used to Address RAI 5-32 for the HNP NFPA-805 Application 13
Fire PRA Overview Fire PRA Overview Significant Efforts Bus Ducts and Below Ground Cable Ducts Electrical Coordination of PRA Components p
Walkdowns and Related Documentation Significant Conservatism No Credit taken for Flame Retardant Coating Installed on Thermoset Cable Cable Spread Room (CSR)
Diesel Generator Building Basement 14
Fire PRA Overview Fire PRA Overview Incipient Detection Main Control Boards - Credit per FAQ 08-0046 CSR Area Wide - Normal Detection Credit Crediting Existing Solid Bottom Trays to Delay Damage Delay Damage Per NUREG/CR-6850 15
Important Fire Areas and Scenarios Important Fire Areas and Scenarios Cable Spread Room Control Room Abandonment Detailed Human Reliability Analysis (HRA)
Control Room Turbine Building Battery Rooms Switchgear Rooms Switchgear Rooms 16
Fire PRA Peer Review Fire PRA Peer Review Fire PRA Peer Review
Peer Review December 2011
Performed by Boiling Water Reactor Owners G
NEI 07 12 P Group per NEI 07-12 Process Incorporated Findings Resulted in Improved Core Damage Frequency Core Damage Frequency Greater than 50% improvement 17
Fire PRA Status Fire PRA Status One Modification Credited Additional Fire Modeling Diesel Generator Building Basement Main Control Room Cable Spread Room 18
Questions 19