ML12158A344

Meeting Slides for Pre-Application Meeting with Carolina Power and Light Company Regarding Emergency Diesel Generator Completion Time Extension for Brunswick Steam Electric Plant, Units 1 and 2

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 Units 1 and 2 TS 3.8.1 Diesel Generator Completion Time Extension License Amendment Request Pre-Submittal Meeting June 7, 2012

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 Switchyard Breaker/Panel/Relay Replacements 27SX-1 Relay UV/DUV Relays Switchyard Insulator Coatings Air Start Modification 14 Dayy LCO EDG 3

LAR Overview - Proposed Change Extend Technical Specification Diesel Generator (DG) Completion Time (CT) from 7 days to 14 days Branch Technical Position (BTP) 8-8 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 E-bus 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 off SUPP Availability SUPP-DG DG checked h k d once per shift hif Action should SUPP-DG become unavailable during extended CT Monthly Test 4

Emergency Diesel Generator Improvement p Actions EDG Actions Action 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 EDG #2 Exhaust Bellows Completed Allen Bradley Relays Working Jacket Water TCV's Scheduled SAMG DG's Capacitor Leakage EDG PM Evaluations Ultra Low Sulfur Fuel Latent Design Issues 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 (Identify)

(Identif )

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 p Dvpmt p Hold. Pending Fukishima recommendation resolution.

Loadbank to Support Online LOOP/LOCA Equivalent Eng/Planning Install 5

Project Overview Project Status & Schedule Note: Automatic Voltage Regulator (AVR) 6

PRA Overview PRA Includes: Internal Events, Internal Flooding, E t External l Events, E t High Hi h Wi Winds, d E External t l Fl Flooding, di Fi Fire All Completed Peer Reviews against ANS/ASME PRA Standard and RG 1 1.200 200 R2 Seismic has qualitative assessment 7

PRA Overview Results of Emergency Diesel Generator (EDG)

Allowed Outage Time (AOT) Risk Evaluation Risk Metric Results Risk Metric 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 4.8E-09 6 2E-09 6.2E-09 Total ICCDP 4.3E-07 4.1E-07 Total ICLERP 2.0E-09 3.5E-09 8

PRA Overview 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) 4D Documentation t ti iissues 3 LERF SRs at CCI 9

PRA Overview BNP External Events High Winds/External Flooding Peer Review January 2012 All Supporting Requirements Reviewed High Winds 3 F&Os remain on documentation External Flooding All F&Os resolved 10

PRA Overview Significant External Events Conservatisms High Winds/ External Flooding Some Operator Actions could be Credited 11

Fire PRA Fire PRA Overview Important Fire Areas and Scenarios Fire PRA Peer Review Current Status 12

Fire PRA Overview Methods Similar to Harris Nuclear Plant (HNP)

Application NUREG 6850 p

Used Accepted Alternatives ((e.g.,

g , FAQ 08-0046))

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 Significant Efforts Bus Ducts and Below Ground Cable Ducts p

Electrical Coordination of PRA Components 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 Incipient Detection Main Control Boards - Credit per FAQ 08-0046 CSR Area Wide - Normal Detection Credit Crediting Existing Solid Bottom Trays to Delay Damage Per NUREG/CR-6850 15

Important Fire Areas and Scenarios Cable Spread Room Control Room Abandonment Detailed Human Reliability Analysis (HRA)

Control Room g

Turbine Building Battery Rooms Switchgear Rooms 16

Fire PRA Peer Review Fire PRA Peer Review Peer Review December 2011 Performed by Boiling Water Reactor Owners G

Group per NEI 07-12 07 12 PProcess Incorporated Findings Resulted in Improved Core Damage Frequency Greater than 50% improvement 17

Fire PRA Status One Modification Credited Additional Fire Modeling Diesel Generator Building Basement Main Control Room Cable Spread Room 18

Questions 19