ML092240298

From kanterella
Jump to navigation Jump to search

Extended Power Uprate and Alternate Source Term Review Planning Meeting Presentation (Handout 2)
ML092240298
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 08/06/2009
From:
Nextera Energy
To:
Office of Nuclear Reactor Regulation
Poole Justin/DORL/LPL3-1/ 301-415-2048
References
Download: ML092240298 (11)
v • d • e


Text

AST/EPU Potential Relationship Table Potential AST Category Relationship AST LAR EPU LAR Area Dose Consequence Analysis Loss of Coolant Accident EPU Power Level assumed Used conservative input assumptions that bound current and EPU conditions consistent with RG 1.183 (no tie to EPLI LAR)

Reference to AST for radiological consequences Steam Generator Tube Rupture EPU Power Level assumed Used conservative input assumptions that bound current and EPU conditions consistent with RG 1.183 (no tie to EPU LAR)

Supplemental analysis presented in response to RAI to confirm no SG overfill and conservatism of 30 minute isolation assumption Reference to AST for radiological consequences Detailed overfill analysis performed Locked Rotor EPU Power Level assumed Used conservative input assumptions that bound current and EPU conditions consistent with RG 1.183 (no tie to EPU LAR)

Exception was assumption of rods in DNB which was changed from 100% to 30% based on RAVE analysis)

Reference to AST for radiological consequences EPU Power Level assumed Main Steam Line Break Used conservative input assumptions that bound current and EPU conditions consistent with RG 1.183 (no tie to EPLI LAR)

Reference to AST for radiological consequences EPU Power Level assumed Control Rod Drive Ejection Used conservative input assumptions that bound current and EPU conditions consistent with RG 1.183 (no tie to EPU LAR)

Reference to AST for radiological consequences Reactor Vessel Head Drop EPU Power Level assumed Reference to AST for radiological consequences Fuel Handling Accident EPU Power Level assumed Conservative gap fractions assumed Reference to AST for radiological consequences Systems Residual Heat Removal EPU Power Level assumed Decay removal based on throttled flow evaluated using existing methodology EPU doesn't impact EPU evaluations assume AST modifications are implemented Page 1 of 3

AST/EPU Potential Relationship Table I

Potential AST Category ASTLAR Area Relationship Systems

  • Throttled flow evaluated for acceptability using existing methodology
  • Does not affect AST analyses Auxiliary
  • New operating mode developed
  • To address LOOP for LOCA, fans now auto loaded vs. manually loaded on EDGs
  • Modifications being implemented to address single active failures
  • System upgraded to Augmented Quality
  • EPU Power Level assumed
  • Modifications being implemented to address single active failures
  • System upgraded to Augmented Quality
  • New Technical Specifications Proposed
  • Impact of auto loading of Control Room Ventilation fans addressed by removing an existing non-essential load which is larger
  • No impact of Auxiliary Building ventilation fans because they will be integrated into the load management program
  • No impact on Fuel Consumption because analysis based on EDGs operating at the 200 hour0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> rating Page 2 of 3 EPU LAR
  • EPU doesn't impact
  • EPU evaluations assume AST modifications are implemented
  • EPU evaluates AFW modifications and supports Technical Specifications
  • EPU evaluations assume AFW modifications are implemented
  • EPU doesn't impact
  • EPU evaluations assume AST modifications are implemented
  • EPU doesn't impact
  • EPU evaluations assume AST modifications are implemented EPU evaluations assume AST and EPU modifications are implemented Overall onsite electrical system evaluated utilizing ETAP model

AST/EPU Potential Relationship Table Potential AST Category Relationship Area Other Environmental Qualification GSI191 ASTlAR

  • EQ still based on TID and not part of AST
  • Newly credited equipment (ventilation fans) will be included in EQ program as applicable
  • No change in containment chemical environment as a result of AST modifications
  • No impact
  • Modifications will stay within current assumptions and analyses (Le., sump recirculation flow rate not changed)

EPU lAR

  • EPU doesn't impact
  • Modifications will stay within current assumptions and analyses (Le., sump recirculation flow rate not changed)

Page 3 of 3

AFW Review Matrix Licensing/Tech Associated LR Reason LR Section Title Spec Change Sections Systems and Components Subject LR Section controls Discusses AFW interface changes.

Discusses impact of AFW modifications on electrical system.

2.5.4.5 2.4.1 2.11.1 2.2.4 2.5.4.2 2.3.2 2.3.3 2.5.7.1 2.3.4 TS 3.3.2-1, ESFAS 2.7.6 Item 6.e, AFW Pump Suction Transfer on Suction 2.7.5 Pressure Low TS 3.7.5, AFW TS 3.7.6, CST 2.6.3.2 2.6.1 2.8.5 2.8.5.2.2 2.8.5.2.3 2.8.5.6.2 2.8.5.6.3.3 2.3.5 2.8.5.7 2.5.1.2.1 Auxiliary Feedwater Reactor Protection, Safety Features Actuation, and Control Systems Human Factors Safety-Related Valves and Pumps Station Service Water System Offsite Power System Discusses AFW associated setpoints and Discusses control room changes for AFW.

Discusses safety-related pumps and valves.

Discusses impact of AFW modifications on AC Onsite Power System electrical system.

Emergency Diesel Fuel Oil Storage and Transfer DC Onsite Power System Engineered Safety Feature Ventilation System Auxiliary and Radwaste Area and Turbine Areas Ventilation Systems Safety Analyses Mass and Energy Release Discusses transients that credit new AFW Analysis for Secondary system.

System Pipe Ruptures Primary Containment New AFW configuration used in analysis.

Functional Design Accident and Transient Discusses AFW input to accident analyses.

Analysis Loss of Non-Emergency AC Power to the Station Auxiliaries Loss of Normal Feedwater Flow Steam Generator Tube Rupture Technical Evaluation SBLOCA Station Blackout Does not specifically discuss AFW, however does discuss increase on fuel consumption due to increase in EDG load Discusses impact of AFW modifications on electrical svstern.

Discusses AFW room ventilation.

Discusses PAB ventilation - location of new AFW pumps.

Discusses transients that credit new AFW system.

Discusses transients that credit new AFW system.

Discusses transients that credit new AFW svstem.

Discusses transients that credit new AFW system.

Discusses transients that credit new AFW system.

Anticipated Transients Without Discusses transients that credit new AFW Scram svstern.

Addresses internally generated missiles for Internally Generated Missiles SR equipment.

Page 1 of 2

AFW Review Matrix Licensing/Tech Spec Change Associated LR Sections LR Section Title Reason TS 3.3.2-1, ESFAS Item 6.e, AFW Pump Suction Transfer on Suction Pressure Low TS 3.7.5, AFW TS 3.7.6, CST Programs/Other 2.3.1 Environmental Qualification of Electrical Equipment Discusses EQ requirements.

2.5.1.4 Fire Protection Discusses conditions that credit new AFW system.

2.13.1 Risk Evaluation Discusses AFW modifications to enhance PRA Page 2 of 2

RPS/ESFAS Review Matrix Cat Licensing/Tech Spec Change Associated LR Sections LR Section Title Reason A

TS 3.3.1, Reactor Protection System (RPS)

Instrumentation:

Function 2b, Power Range Neutron Flux Low Function 3, Intermediate Range Neutron Flux Function 7.b, Pressurizer Pressure High Function 8, Pressurizer Water Level High Function 14, SG Water Level Low Function 17a, Intermediate Range Neutron Flux, P-6 Function 17b(1), Low Power Reactor Trip Block P-7, Power Range Neutron Flux Function 17b(2), Low Power Reactor Trip Block P-7, Turbine Impulse Pressure Function 17e, Power Range Neutron Flux P-10 2.4.1 Appendix E Reactor Protection, Engineered Safety Features and Control Systems Supplement to LR Section 2.4.1 Associated with all setpoints.

Provides methodology for setpoints.

TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation:

Function 1c, Safety Injection Containment Pressure High Function 1d, Safety Injection Pressurizer Pressure Low Function 2c, Containment Spray-Containment Pressure High High Function 4c, Steam Line Isolation Containment Pressure High High Function 5.b, Feedwater Isolation - SG Water Level High Function 8, SI Block - Pressurizer Pressure 2.4.1 Appendix E Reactor Protection, Engineered Safety Features and Control Systems Supplement to LR Section 2.4.1 Associated with all setpoints.

Provides methodology for setpoints.

Page 1 of 3

RPS/ESFAS Review Matrix Cat Licensing/Tech Spec Change Associated LR Sections LR Section Title Reason All 2.4.1 Reactor Protection, Engineered Safety Features and Control Systems Associated with all setpoints.

Appendix E Supplement to LR Section 2.4.1 Provides methodology for setpoints.

TS 3.3.1, Reactor Protection System (RPS)

Instrumentation, Function 2a, Power Range Neutron Flux High 2.8.5.4.2 Uncontrolled Rod Cluster Control Assembly Withdrawal at Power New value used in analysis.

TS 3.3.1, Reactor Protection System (RPS)

Instrumentation, Function 13, Steam Generator Water Level Low Low 2.8.5.2.3 Loss of Normal Feedwater Flow Loss of AC Related to TS 3.3.1 Function 13.

New value used in the analysis.

TS 3.3.1, Reactor Protection System (RPS)

Instrumentation, Function 17c, Power Range Neutron Flux P-8 2.8.5.3 Decrease in Reactor Coolant System Flow LR section discusses change of P-8 setpoint.

B TS 3.3.1, Reactor Protection System (RPS)

Instrumentation, Function 17d, Power Range Neutron Flux P-9 2.4.2.1 Plant Operability (Margin to Trip)

LR discusses analysis using P-9 input.

TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Function 4d, Steam Line Isolation - High Steam Flow Coincident with Safety Injection and Tavg Low 2.5.1.3 Steam Line Break Outside Containment LR section describes analysis results for steam line failures outside containment.

TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Function 4e, Steam Line Isolation - High High Steam Flow Coincident with Safety Injection 2.8.5.1.2 2.5.1.3 Steam System Piping Failures Inside and Outside Containment Steam Line Break Outside Containment Related to TS 3.3.2 Function 4.e.

TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Function 6b, Auxiliary Feedwater on SG Water Level Low Low 2.8.5.2.2 2.8.5.2.3 2.2.2.5 Loss of Non-Emergency AC Power to Station Auxiliaries Loss of Normal Feedwater Flow Steam Generators and Supports Related to TS 3.3.2 Function 6.b.

Related to TS 3.3.2 Function 6.b SG Modifications affect level setpoints (AFW on SG Water Level-Low Low) Function 6b Page 2 of 3

RPS/ESFAS Review Matrix Cat Licensing/Tech Spec Change Associated LR Sections LR Section Title Reason All 2.4.1 Appendix E Reactor Protection, Engineered Safety Features and Control Systems Supplement to LR Section 2.4.1 Associated with all setpoints.

Provides methodology for setpoints.

TS 3.3.1, Reactor Protection System (RPS)

Instrumentation, Function 5, Overtemperature 2.8.5 Accident and Transient Analysis Associated with Functions 5 and 6 non-LOCA analysis related.

~T 2.8.5.6.2 Steam Generator Tube Rupture Supplemental margin to overfill and supplemental input to dose analyses model Function 5 and la, but reactor trips on OTDT.

TS 3.3.1, Reactor Protection System (RPS)

Instrumentation, Function 6, Overpower ~T 2.8.5 Accident and Transient Analysis Associated with Functions 5 and 6 non-LOCA analysis related.

C TS 3.3.1, Reactor Protection System (RPS)

Instrumentation, Function la, Pressurizer Pressure Low 2.8.5.6.2 Steam Generator Tube Rupture Supplemental margin to overfill and supplemental input to dose analyses model Function 5 and la, but reactor trips on OTDT.

2.4.2.1 Plant Operability (Margin to Trip)

Associated with TS 3.3.1, Functions t>> and l.b.

2.4.2.2 Pressurizer Control Component Sizing Associated with TS 3.3.1, Functions r>> and l.b.

TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Function 1e, Safety Injection - Steam Line Pressure Low 2.8.5.1.2 Steam System Piping Failures Inside and Outside Containment Associated with TS 3.3.2, Function 1.e.

2.4.2.1 Plant Operability (Margin to Trip)

Associated with TS 3.3.2, Function 1.e.

2.4.2.2 Pressurizer Control Component Sizing Associated with TS 3.3.2, Function 1.e.

TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation, Function 6e, AFW Pump Suction Transfer on Suction Pressure Low 2.5.4.5 Auxiliary Feedwater Associated with TS 3.3.2, Function 6.e.

Page 3 of 3

Unit 1 2010 Spring Outage Modifications Review Matrix LicensinglTech Spec Change Associated lR Sections lR Section Title Reason TS 3.3.2, Engineered Safety 2.8.5.2.2 Loss of Non-Emergency AC Power to Station Auxiliaries Related to TS 3.3.2 Function 6.b.

Feature Actuation System (ESFAS)

Instrumentation, 2.8.5.2.3 Loss of Normal Feedwater Flow Related to TS 3.3.2 Function 6.b Function 6b, Auxiliary Feedwater on SG Water Level Low Low 2.2.2.5 Steam Generators and Supports SG Modifications affect level setpoints (AFW on SG Water Level-Low Low) Function 6b 2.5.5.4 Condensate and Feedwater Discusses new MFIVs.

2.6.1 Primary Containment Functional Design MFIV closure is credited in containment integrity analysis.

2.5.4.2 Station Component Service Water System Discusses impact of increased Containment accident temperature on GL 96-06 2.6.3.2 Mass and Energy Release Analysis for Secondary System Pipe Rupture MFIV closure is credited in analysis.

2.6.5 Containment Heat Removal Discuss heat removal capability for revised containment analysis TS 3.7.3, Main Feedwater Isolation 2.7.7 Other Ventilation Systems (Containment)

Discuss heat removal capability for revised containment analysis 2.1.7 Protective Coating Systems Discusses impact of change in Containment PIT 2.3.1 Environmental Qualification of Electrical Equipment Discusses impact of change in Containment PIT 2.2.4 Safety-Related Valves and Pumps Discusses 1ST changes due to addition of MFIV and closure time change for FRV 2.11.1 Human Factors Discusses changes to Control Room for addition of MFIV 2.13.1 Risk Evaluation Discusses addition of MFIV 2.8.5.6.3.3 Technical Evaluation SBLOCA Models addition of MFIV 2.8.4.2 Overpressure Protection During Power Operation Discusses setpoint changes needed for analysis.

2.8.5.2.1 Loss of External Electrical Load, Turbine Trip and Loss of Condenser Vacuum Discusses setpoint changes needed for analysis.

TS 3.7.1, Main Steam Safety Valves 2.8.5 Accident and Transient Analysis Discusses RETRAN code used for LR 2.8.5.2.1 analysis.

2.2.4 Safety-Related Valves and Pumps Discusses 1ST changes due to change in MSSV setpoints 2.5.5.1 Main Steam Discuss need for MSSV setpoint change 2.8.5.6.3.3 Technical Evaluation-SBLOCA Models new MSSV setpoints Page 1 of 3

Unit 1 2010 Spring Outage Modifications Review Matrix LicensinglTech Spec Change Associated LR Sections LR Section Title Reason TS 3.4.9, 2.8.5.2.2 Loss of Non-Emergency AC Power to the Station Auxiliaries EPU analysis supporting AFW changes requires revised initial pressurizer level Pressurizer 2.8.5.2.3 Loss of Normal Feedwater Flow EPU analysis supporting AFW changes requires revised initial pressurizer level 2.8.5.2.1 Loss of External Electrical Load, Turbine Trip and Loss of Condenser Vacuum EPU analysis supporting MSSV TS 3.7.1 changes includes revised +2.5% PSV tolerance TS 3.4.10, Pressurizer Safety 2.8.5.2.2 Loss of Non-Emergency AC Power to Station Auxiliaries EPU analysis supporting AFW changes includes revised +2.5% PSV tolerance Valves 2.8.5.2.3 Loss of Normal Feedwater Flow EPU analysis supporting AFW changes includes revised +2.5% PSV tolerance 2.8.5 Accident and Transient Analysis Discusses RETRAN code used for LR 2.8.5.2.1 thru 2.8.5.2.3 analyses.

2.8.4.2 Overpressure Protection During Power Operation Methodology used in analysis for TS 3.7.1, Main Steam Safety Valves (MSSVs).

2.8.5.1.2 Steam System Piping Failures Inside and Outside Containment Methodology used in analysis for TS 3.3.2 Function 4e, Engineered Safety Featur Actuation System (ESFAS) Instrumentation -

High High Steam Flow.

2.8.5.2.1 Loss of External Electrical Load, Turbine Trip, and Loss of Condenser Vacuum Methodology used in analysis for TS 3.7.1, Main Steam Safety Valves (MSSVs) and TS 3.4.10, Pressurizer Safety Valves.

RETRAN 2.8.5.2.2 Loss of Non-Emergency AC Power to the Station Auxiliaries Methodology used in analysis for:

TS 3.7.5, Auxiliary Feedwater TS 3.4.9, Pressurizer TS 3.4.10, Pressurizer Safety Valves TS 3.3.1 Function 13, Reactor Protection System (RPS) Instrumentation - Steam Generator (SG) Water Level Low Low TS 3.3.2 Function 6b, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation - SG Water Level Low Low Methodology used in analysis for:

TS 3.7.5, Auxiliary Feedwater TS 3.4.9, Pressurizer TS 3.4.10, Pressurizer Safety Valves TS 3.3.1 Function 13, Reactor Protection System (RPS) Instrumentation - Steam Generator (SG) Water Level Low Low TS 3.3.2 Function 6b, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation - SG Water Level Low Low 2.8.5.2.3 Loss of Normal Feedwater Flow Page 2 of 3

Unit 1 2010 Spring Outage Modi'fications Review Matrix Licensi nglTech Spec Change Associated LR Sections LR Section Title Reason RETRAN 2.8.5.4.2 Rod Withdrawal at Power Methodology used in analysis for:

TS 3.3.1 Function 2a, Power Range Neutron Flux High Methodology used in analysis for (LOCA, MSLB, &Containment Response):

TS 3.3.2 Function 1c, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation Containment Pressure High TS 3.3.2 Function 2c, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation - Containment Pressure High High TS 3.3.2 Function 1d, Engineered Safety Feature Actuation System (ESFAS)

Instrumentation - Pressurizer Pressure Low TS 3.7.5, Auxiliary Feedwater Methodology used in analysis section 2.8.3.2.3.5 SLB Accident GOTHIC 2.6.1 Primary Containment Functional Design 2.8.3 Thermal and Hydraulic Design VIPRE 2.8.5.1.2 Steam System Piping Failures Inside and Outside Containment Methodology used in analysis for TS 3.3.2 Function 4e, Engineered Safety Feature Actuation System (ESFAS) Instrumentation -

High High Steam Flow.

2.8.5.4.2 Uncontrolled Rod Cluster Control Assembly Withdrawal at Power Methodology used in analysis for:

TS 3.3.1 Function 2a, Power Range Neutron Flux High Page 3 of 3

Retrieved from "https://kanterella.com/w/index.php?title=ML092240298&oldid=5311945"