ML111610558
| ML111610558 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 06/14/2011 |
| From: | Exelon Nuclear |
| To: | Division of Operating Reactor Licensing |
| Hughey J, NRR/DORL, 301-415-3204 | |
| Shared Package | |
| ML111610551 | List: |
| References | |
| Download: ML111610558 (31) | |
Text
NRC Public Meeting Pre-Application Meeting for Peach Bottom Extended Power Uprate (EPU) 06/14/11
Exelon Confidential and Proprietary 2
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Introductions
John Rommel - Power Uprate Engineering Director
Kevin Borton - Power Uprate Licensing Manager
Todd Wickel - Power Uprate Senior Engineering Manager
Jenna Lichtenwalner -
Power Uprate Regulatory Engineer
Andy Olson - Senior Staff Engineer
Exelon Confidential and Proprietary 3
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Agenda
Meeting Purpose
=
Background===
Schedule & Approach
Major Modifications
Essential Analyses
ATWS/ASME overpressure
Steam Dryer Analysis
Future EPU Project Meetings Topics and Schedule
Exelon Confidential and Proprietary 4
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Meeting Purpose
Introduce PBAPS EPU Schedule and Approach
Describe Key EPU Analyses &
Obtain NRC Feedback
Exelon Confidential and Proprietary 5
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5 Background
Initial License
Unit 2 and Unit 3 began operation 1974
3293 MWt Original Licensed Thermal Power (OLTP)
3458 MWt licensed power level (105% of OLTP)
Unit 2 approved 1994, Unit 3 approved 1995
Measurement Uncertainty Recapture (MUR) Uprate
3514 MWt licensed power level (106.62% of OLTP)
Unit 2 and Unit 3 approved November 2002
Proposed Extended Power Uprate
3951 MWt licensed power level (120% of OLTP)
4030 MWt analyzed power level
Exelon Confidential and Proprietary 6
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EPU Schedule
NRC Communication Schedule
Additional Pre-Submittal Meeting - target August 2011
Final Pre-Submittal Meeting - target October 2011
EPU Implementation Schedule
Submit LAR - target December 2011
LAR Approval - target August 2013
Unit 2 fully implemented in 2014 (P2R20 Outage)
Unit 3 fully implemented in 2015 (P3R20 Outage)
Exelon Confidential and Proprietary 7
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Approach
RS-001, Review Standard for Extended Power Uprates
Specific Peach Bottom licensing bases sections provided (Peach Bottom is not a GDC plant)
Constant Pressure Power Uprate Licensing Topical Report (NEDC-33004P-A)
No Beyond Scope issues
No linked submittals
Exelon Confidential and Proprietary 8
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Exelon to provide:
Cover Letter Amendment Request -
Description/Evaluation of Proposed Changes including No Significant Hazards Consideration -
Markup of Operating License and Technical Specifications -
Markup of Tech Spec Bases and TRM Power Uprate Safety Analysis Report (PUSAR) (non-proprietary, proprietary, and affidavit) -
Supplemental Environmental Report -
Modifications List 0 -
EPU Startup Test Plan 1 -
Grid Stability Study 2 -
PRA Report 3 -
Flow Induced Vibration (FIV) Piping and Component Evaluation 4 -
Instrument Setpoint Calculations 5 Steam Dryer Evaluation for PBAPS Unit 2 & 3 (High Cycle Fatigue Report) (non-proprietary, proprietary, and affidavit)
Exelon Confidential and Proprietary 9
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Modifications
Major Modifications
RHR Cross-tie
Boron 10 Enrichment
CST Modifications
Addition of Main Steam Spring Safety Valve
Reactor Recirc Pump ATWS Trip
Main Generator Upgrades
HP/LP Turbine Upgrades
Isophase Bus Duct Modifications
Reactor Feedwater Pump Turbine Upgrades
Feedwater Heater Replacements
Condensate Demin System Upgrades
Condensate Pumps/Motors Upgrades
Main Steam and Feedwater Flow Induced Vibration monitoring
Exelon Confidential and Proprietary 10 10 10 EPU Key Analyses
ATWS/ASME Overpressure
Steam Dryer
Exelon Confidential and Proprietary 11 11 11 ECCS Pump NPSH Analysis Methodology
In accordance with Reg. Guide 1.82
Event-specific analyses determine containment response
Suppression Pool Temperature
Suppression Pool Inventory (level)
Event Type Event Description Mitigating Pumps RHR Core Spray HPCI RCIC DBA-LOCA Short-term (first 10 minutes)
Yes Yes No No Long-term (beyond 10 minutes)
Yes Yes No No Special Events Appendix R Yes Yes Yes Yes ATWS Yes No Yes Yes SBO Yes No Yes Yes
Event-specific NPSHA time history developed for each pump
NPSHA compared to NPSHR for each pump
Exelon Confidential and Proprietary 12 12 12 ECCS Pump NPSH Analysis Key Assumptions
- No Containment Accident Pressure required
- Cross-tie modification included (required for DBA-LOCA only)
- Deterministic analysis with conservative inputs used for DBA-LOCA
- Nominal inputs used for non-LOCA analysis
- Used vendor supplied NPSHR curves
- 21% uncertainty for DBA-LOCA (0% non-LOCA)
- Results will be verified prior to submittal
Exelon Confidential and Proprietary 13 13 13 Preliminary Results Event / Pump NPSHa (ft)
NPSHr Effective (ft)
Margin (ft)
DBA-LOCA Short-Term /
RHR 33.9 31.5 2.4 DBA-LOCA Short-Term /
Core Spray 35.4 33.3 2.1 DBA-LOCA Long-Term /
RHR 24.2 19.4 4.8 DBA-LOCA Long-Term /
Core Spray 26.7 25.8 0.9 SBO / RHR 22.6 16.0 6.6 ATWS / RHR 32.2 16.0 16.2 App R / RHR 17.4 16.0 1.4 App R / Core Spray 21.7 21.3 0.4 SBO, ATWS, App R / HPCI 21.1 17.1 4.0 SBO, ATWS, App R / RCIC 23.1 20.0 3.1 ECCS Pump NPSH Analysis Note: NPSHr Effective values consistent with draft guidance (NPSHr effective = NPSHr3% +
uncertainties). This includes a 21% uncertainty adder for DBA-LOCA Cases and a 0% adder for Special Events.
Exelon Confidential and Proprietary 14 14 14 ECCS Pump NPSH Analysis Regulatory Alignment
Follows CPPU LTR and RS-001 (Section 2.6.5) Guidance
Current Licensing Basis
Peach Bottom Current Licensing Basis credits CAP
GL, other applicable guidance
NRC DRAFT Guidance on CAP
NRC staff communication to non-CAP plants that 21% uncertainty margin is acceptable for DBA-LOCA
Exelon Confidential and Proprietary 15 15 15 ECCS Pump NPSH Analysis ECCS Pump NPSH - Events Proposed Key Changes/Modifications DBA-LOCA Short-Term (first 10 minutes)
Reduce RHR runout flow rate by adding hydraulic resistance
NPSHR 3% curves + uncertainty DBA-LOCA (LAR)
Long-Term (beyond 10 minutes)
Increase RHR HX performance (reduce fouling)
Decrease RHR flow rate
NPSHR 3% curves + uncertainty Station Blackout (SBO)
Increase RHR HX performance (reduce fouling)
Decrease RHR flow rate
NPSHR 3% curves
Credit CST as suction source for RCIC pump ATWS (Peak Pool Temperature)
Increase SBLC Boron Enrichment
Increase RHR HX performance (reduce fouling)
Decrease RHR flow rate
NPSHR 3% curves Appendix R
Increase RHR HX performance (reduce fouling)
Decrease RHR flow rate
NPSHR 3% curves
Increase/Supplement CST Inventory
Exelon Confidential and Proprietary 16 16 16 ECCS Pump NPSH Analysis ECCS Pump NPSH Analysis Discussion & Feedback
Exelon Confidential and Proprietary 17 17 17 ATWS/ASME Overpressure Analysis Methodology
Event-specific analyses to determine reactor vessel & containment response
Peak Reactor Vessel Pressure
Peak Suppression Pool Temperature (ATWS only)
Peak Containment Pressure (ATWS only)
Peak Cladding Temperature (ATWS only)
ASME overpressure results compared to ASME Class B pressure limit (1375 psig) and TS Reactor Steam Dome Safety Limit (1325 psig)
ATWS overpressure results acceptance criteria:
ASME Class C pressure limit (1500 psig)
Suppression Pool Temperature limit (180 °F)
Containment Pressure Limit (56.0 psig)
Peak Clad Temperature limit (2200 °F)
Analysis performed utilizing current licensing basis methodology
NEDC-24154P-A (ASME Overpressure - ODYN)
Exelon Confidential and Proprietary 18 18 18 ATWS/ASME Overpressure Analysis Key Assumptions
SRV/SSV capacity at ASME minimum certified values
SRV/SSV opening setpoints at upper limit (nominal +3%)
1 SRV assumed out-of-service (OOS)
Limiting cycle conditions (e.g., exposure, power distribution)
Bounding TS MSIV closure time for ASME overpressure
Bounding TS scram speed for ASME overpressure
Conservative May-Witt decay heat for ATWS
Nominal parameters for ATWS based on actual plant performance if not otherwise required by methodology
Exelon Confidential and Proprietary 19 19 19 ATWS/ASME Overpressure Analysis How ATWS/ASME Overpressure Analyses Align with Current Regulatory Framework
Performed in accordance with CPPU LTR
Follows EPU RS-001 Guidance - Section 2.8.5.7 (ATWS) and Section 2.8.4.2 (ASME Overpressure)
Current Licensing Basis
ASME Overpressure - NUREG-0800 (SRP) Sec. 5.2.2
Exelon Confidential and Proprietary 20 20 20 ATWS/ASME Overpressure Analysis Resulting Modifications
Need additional reactor vessel pressure relief/reduction capability for EPU conditions
Addition of 1 SSV
Transfer of ATWS RPT trip from M-G set drive motor breaker to recirculation pump drive motor breaker (or alternatively installation of Adjustable Speed Drives)
Need reduction of suppression pool temperature for EPU conditions
Increase in SLCS B-10 enrichment to 92%
Exelon Confidential and Proprietary 21 21 21 ATWS/ASME Overpressure Analysis ATWS/ASME Overpressure Analysis Discussion & Feedback
Exelon Confidential and Proprietary 22 22 22 Steam Dryer Analysis Methodology
- The approach provided by BWRVIP-182-A is followed.
Guidance for Demonstration of Steam Dryer Integrity for Power Uprate
- Analytical acoustic screening
- Sub-scale model testing
- Strain gage installations to obtain in-plant data at CLTP.
CLTP data is bumped-up via scale-model tests to predict EPU conditions.
Exelon Confidential and Proprietary 23 23 23 Steam Dryer Analysis Methodology (continued)
- Acoustic Circuit Model (ACM) analysis
Models the interaction of the (4) four MSLs and the dryer
Determines the acoustic pressure loads acting on the dryer at EPU conditions.
- High Cycle Fatigue assessment to address the effects of acoustic pressure loads.
Exelon Confidential and Proprietary 24 24 24 Steam Dryer Analysis Key Assumption/Inputs
- BWRVIP documents followed for analysis methodology.
BWRVIP-182-A: Guidance for Demonstration of Steam Dryer Integrity for Power Uprate
BWRVIP-181: Steam Dryer Repair Design Criteria
- Acoustic Circuit Model (ACM) version 4.1 used
This latest version of ACM is being reviewed by NRC Staff for another licensee Regulatory Alignment
- Analysis is in accordance with Reg. Guide 1.20: Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing
Strain gages are used to measure hoop strain, which is correlated to pipe internal pressure
Exelon Confidential and Proprietary 25 25 25 Steam Dryer Analysis Modifications
- The need for modifications to the steam dryers has not yet been determined.
Exelon Confidential and Proprietary 26 26 26 Steam Dryer Analysis Steam Dryer Analysis Discussion & Feedback
Exelon Confidential and Proprietary 27 27 27 Future EPU Meeting Topics and Schedule
Follow-up EPU Meetings
- Potential Topics
Vibration Assessment (FIV)
Spent Fuel Pool Criticality
Project Status Next meeting target in August 2011
Exelon Confidential and Proprietary 28 28 28 Supplementary Information
Exelon Confidential and Proprietary 29 29 29 RHR HX Cross-tie Modification Concept Suppression Pool 24" Pipe 24" Pipe RHR Pump A
RHR Pump C
A C
B New pipe U2 HPSW Pumps 039A 034A To LPCI D
Div I Div II FE Proposed Additions M
New MOV 2344 M
M M
Existing Wall 00B062 To 3344 20A015 20B010 20B036 20A017 20B012 20B038 M
M M
154A 089C M
089A M
A From 20B011 Existing Wall U3 HPSW Pump Room 00B061 FE FE New MOV Remove Orifice
Exelon Confidential and Proprietary 30 30 30 ECCS Pump NPSH
Core Spray - no modifications
RHR Pump (LPCI) - Runout Flow Rate: Current analysis requires CAP (from 7.5 to 10 minutes)
- Current:
12,000 gpm
- Post Mod:
10,600 gpm (adjust limit stops to increase HX inlet MOV hydraulic resistance)
DBA-LOCA Short-Term (1st 10 minutes)
Exelon Confidential and Proprietary 31 31 31 ECCS Pump NPSH
Core Spray - no modifications, no new operator actions
RHR Pump (LPCI) - Core and Containment Cooling Analysis Flow Rate:
- Current:
10,000 gpm
- Post Mod:
8,600 gpm (analysis value - operators maintain flow within 8,600 -
10,600 gpm range in accordance with EOP NPSH curves)
DBA-LOCA Long-Term (beyond 10 minutes)