ML050960117

3/15/05 Hope Creek Generating Station, Slide Presentation for Category 1 Meeting with PSEG Nuclear LLC, Regarding Future Application for Extended Power Uprate

ML050960117
Person / Time
Site:	Salem, Hope Creek
Issue date:	03/15/2005
From:	Public Service Enterprise Group
To:	Office of Nuclear Reactor Regulation
Collins D S, NRR/DLPM, 415-1427
References
Download: ML050960117 (25)

Text

Hope Creek Extended Power Uprate NRC/PSEG NRC/PSEG Nuclear Nuclear Pre-Application Pre-Application Meeting Meeting Rockville, Rockville, Maryland Maryland March March 15, 15, 2005 2005

Introduction Hope Creek Generating Station GE BWR 4 Operating License in 1986 - 3293 MWt 2000 - Uprated to 3339 MWt Requested Uprate to 3840 MWt Project Submittal Technical Rigor Industry Lessons Learned Addressed Current Issues Understood Thorough and Encompassing 2

Introduction/Meeting Objectives Objectives Inform NRC staff of PSEGs plans for EPU LCR (115% of CLTP)

Discuss the NRC staff's expectations regarding the content of the EPU application 3

Agenda Licensing Approach Project Status Reactor Systems Containment Mechanical & Materials Engineering Probabilistic Safety Assessment Environmental 4

Licensing Approach Constant Reactor Pressure Based on CPPU LTR ELTR1 & ELTR2 for Fuel Dependent Topics Supplemented with Mixed Core Evaluations 5

Hope Creek EPU Project Status Alternative Source Term - approved Amendments 134 & 146 P/T Limits - approved Amendment 157 GE14 Fuel Transition - approved Amendment 158 ARTS/MELLLA - submitted Plant Modifications 6

Hope Creek EPU Project Status MELLLA/MELLLA+

MELLLA

• Prerequisite for EPU per CPPU LTR

• Submitted 06/07/04

• Mixed Core Evaluations Submitted 02/18/05

• Implementation during Current Cycle 13 (on-line)

MELLLA+

• Not a Prerequisite for EPU (115% CLTP)

• Not Currently Being Pursued 7

Hope Creek EPU Project Status Plant Modifications Designed to Maintain Plant Design and Operational Margin in Selected Areas:

• Main Turbine Replacement

- Includes new DEHC and TSI system

• Main Transformer Replacements

• Moisture Separator Internals Upgrade

• Generator Stator Cooling System Upgrade

• GE-14 Fuel Design

• Switchyard Upgrades

• Cooling Tower Upgrades

• Iso-Phase Bus Cooling Upgrade

• MELLLA Implementation

• Moisture Separator Relief Valve Upgrades

• Steam Jet Air Ejector Modification

• FWH 2/3 Dump Valve Replacements

• EPU Implementation 8

Reactor Systems Topics Mixed Core Analyses Fuel Transition: Cycle 13 CLTP ELLLA ARTS/MELLLA Implementation: Cycle 13 CLTP EPU Implementation: 115% CLTP NSSS Codes & Methods Large Transient Testing 9

Reactor Systems Topics Mixed Core Analyses GE14 Fuel Transition: Cycle 13, ELLLA, GNF Methods

• Mixed Core Analysis Report

• Stability

- Backup Stability Protection Report - report provided

- DIVOM Report

- Option III Setpoint Report

• ECCS/LOCA - report provided

• Fuel Transition Report Fuel dependent evaluations applicable to CLTP condition Forms solid basis for change assessment of EPU impact on fuel & core 10

Reactor Systems Topics Mixed Core Analyses ARTS/MELLLA: Cycle 13, CLTP

• ARTS/MELLLA Safety Analysis Report, Rev. 2

- Submitted 02/18/05

- Addresses Plant and Fuel Requirements

- Documents Bases and Changes Due to Introduction of ARTS/MELLLA at CLTP

>> Mixed Core (GE14 / SVEA-96+) through Full Core of GE14

- Tied to Reactor Systems EPU Technical Review 11

Reactor Systems Topics Mixed Core Analyses EPU Implementation: 115% CLTP

• Power Uprate Safety Analysis Report

- Addresses plant and fuel requirements

- Documents bases and changes due to EPU with equilibrium core of GE14 fuel

• Fuel Supplemental Reports

- Mixed Core (GE14 / SVEA-96+)

>> Fuel dependent evaluations applicable to EPU condition

>> Based on Assumed Energy Plan

>> GNF Reload Methodology/Process Controls

- Mixed Core Analysis Report

- Stability Reports

>> Backup Stability Protection (BSP)

>> DIVOM

>> OPRM Option III Setpoint

- ECCS/LOCA

- Fuel Transition Report 12

Reactor Systems Topics NSSS Codes & Methods SRXB - Applicability of Codes & Methods in EPU Condition GE Proposed Methods Interim Process NRC Requested GE to Docket Process PSEG to Review Resolution LCR to Refer to Methods Interim Process 13

Reactor Systems Topics Large Transient Testing CLTR is the Basis for Hope Creek CPPU Power Ascension and Test Program CLTR Test Program Accepted by NRC Staff, Except for the Recommendation to Eliminate Large Transient Testing of ELTR1 (i.e. MSIV Closure/Generator Load Reject)

Guidance for Justification of Large Transient Test Program Provided in Draft SRP 14.2.1 14

Reactor Systems Topics Large Transient Testing Evaluation in Progress Using Guidance in Draft SRP 14.2.1

• Operating Experience and Documented Events/Transients

• Transient Evaluations for CPPU

• Event/Evaluation Comparisons (Margins &

Conservatisms)

• Simulator Capabilities/Operator Preparation

• Safety Significance of Potential Testing Benefits (latent defects) versus Undesirable Transient Cycle 15

Reactor Systems Topics Large Transient Testing LCR Attachment Will Be Submitted to Supplement PUSAR Testing Information

• Focuses on MSIV Closure and Generator Load Rejection Events

• Addresses Aggregate Impact of Post-modification Testing 16

Containment Topics Containment Overpressure Not Required for EPU ECCS NPSH Still Meets RG 1.1 17

Mechanical & Materials Topics B Reactor Recirculation Pump Vibration Monitoring - Cycle 13 Drywell - Main Steam, Reactor Recirculation, Feedwater, Branch Lines

• 30 Channels of Data From Accelerometers Installed on the Main Steam (18 Accelerometers) and Feedwater (12 Accelerometers) Piping Inside the Drywell

• 58 Accelerometers Installed on the Recirculation Piping, RHR Piping, Pump Motor, and 3 Proximity Probes Installed on 3 Valves Turbine Building - Main Steam, Feedwater, Extraction Steam

• 34 Channels of Data from Sensors Installed on the Main Steam Piping (10 Accelerometers and 10 Strain Gage Channels),

Feedwater Piping (4 Accelerometers), and Extraction Steam Piping (10 Accelerometers) 18

Mechanical & Materials Topics Vibration Monitoring - Cycle 13 Data Taken at 10 Power Levels from 23% to 100% RTP Main Steam Line Vibration

• Below the Stress Criteria of 7,692 PSI Feedwater Piping Vibration

• Below the Stress Criteria of 7,692 PSI Recirculation System Vibration

• Maximum Stresses for the Reactor Recirculation System Are Less Than 7,692 PSI for the Carbon Steel Portions and Less Than 10,880 PSI for the Stainless Steel Portions

• Piping Vibrations an Order of Magnitude Higher Than FW or MS

• Highest Vibration Levels on Branch and Instrument Lines 19

Mechanical & Materials Topics HCGS Steam Dryer Condition Curved Hood Design Regular Inspections to BWRVIP Standards

• Minimal Indications Observed - IGSCC Fall 2004 Inspections - Performed IAW SIL 644 Supp 1

• Observed One Additional Indication

- Center Support Ring - IGSCC

• No Indications Observed on Most Susceptible Locations (Hoods, Cover Plates or End Plates)

• No Vibration Induced Flaws Have Been Identified 20

Mechanical & Materials Topics Analytical Methods for Determining Loads Computational Fluid Dynamics

• To Determine Loads Caused by Flow Exiting the Dryer Circulating Within the Steam Dome up to the Point Where It Exits the Main Steam Nozzles

• May Also Be Applied to Steam Lines Acoustic Loads Model

• To Determine Loads Caused by Acoustic Phenomena in the Main Steam Lines Finite Element Analysis of Steam Dryer

• OEM to develop acceptance criteria for dryer loads CFD and Acoustic Models Will Make Use of Data Collected from Main Steam Strain/Vibration Instrumentation 21

Mechanical & Materials Topics Confirmation of Dryer Loads Validation of Analytical Methods

• Data From an Instrumented Dryer Will be Utilized to Validate the Loads Models Instrumentation of Hope Creek Dryer

• Contingency Will Be in Place Before Implementation

• Will Identify Abnormal Vibration Levels if They Occur

• Finite Element Analysis Used to Generate Acceptance Criteria for Dryer Stress 22

Mechanical & Materials Topics RCPB Structural Evaluations Augmented Inspection Program

• IGSCC Category A

- Risk Informed ISI

• Categories C & E

- Continue IAW GL 88-01 and BWRVIP-75 Flow Accelerated Corrosion 23

Probabilistic Safety Assessment Topics PRA Scope & Quality HC EPU Model Based on Updated (2003) PRA

• Generally Consistent with ASME Standard (Category II)

• Internal Flooding PRA Included

• Resolves 1999 Peer Review Level A and B F&Os

• HRA Uses EPRI HRA Calculator

• Robust CCF modeling based on ASME standard

• Self-Assessment to Compare to ASME Standard

• Suitable to Support PRA Applications that Require ASME PRA Capability Category II 24

Environmental Topics Environmental Assessment Updated Jan 2005 for EPU Scope

• Socioeconomic

• Non-Radiological Environmental

- Terrestrial

- Aquatic

- Air Quality

- Hydrology

• Radiological Environmental

• Alternatives 25

Environmental Topics Permit Status No Land Use Permits Required No Modifications to Groundwater, Surface Water, or NJPDES Permits Required Received Prevention of Significant Deterioration Non-Applicability from USEPA - March 2004 Submitted Application for Modification of Air Emission Permit to NJDEP - February 2004 Completed Required Emissions Modeling and Analyses for Increased Emissions Limitation - July 2004 NJDEP Proposed Regulatory Rulemaking to Address Emissions - Pending 26

Introduction/Meeting Objectives Summary Inform NRC Staff of PSEGs Plans for EPU LCR (115% of CLTP)

Discuss the NRC Staff's Expectations Regarding the Content of the EPU application 27