ML042180367

Fuel Transition Pseg/Nrc Meeting 06/02/2004

ML042180367
Person / Time
Site:	Hope Creek
Issue date:	06/02/2004
From:	Notigan D Global Nuclear Fuel, Public Service Enterprise Group
To:	Office of Nuclear Reactor Regulation
References
Download: ML042180367 (29)

Text

luarr G3bbai Nucebar Fuel Hope Creek Fuel Transition PSEG /NRC Meeting 6/2/2004 Don Notigan, PSEG Nuclear LLC EngineeringSupervisor Hope Creek Reactor&Safe ty Analysis Non-proprietary version 1

Global Nuclear Fuel Meeting Obj ectives

• Provide overview of Hope Creek fuel transition

• Discuss licensing approach

• Gain NRC insights from previous fuel transitions 2

GlNr Global Nuceasr Fuel

,_suw T.,I.~U Agenda

• GE14 Hope Creek Fuel Transition Overview

• Discuss LCR # H03-08 (Fuel Vendor Change)

• Discuss LCR # H04-03 (SLMCPR)

• Discuss Fuel Supplemental Reports

• Integrated GE14 fuel & EPU-MELLLA Program in Hope Creek reactor

• Future Communications Forum

• Questions & Answers 3

GE14 Transition Overview Global Nucelar Fuel

GE14 Transition using GESTAR G

Nru Global Nucleor Fuel Applied to GE14 and SVEA-96+ Fuel

• General Criteria

• Stability Licensing Acceptance Criteria

• Nuclear

• SLMCPR

• Thermal-Mechanical

• Refuel Accident

• Thermal-Hydraulic

• Rod Drop Accident

• OLMCPR

• Critical Power Correlation

• Overpressure Protection Analysis

• ATWS

• LOCA 5

GE14 Transition Complete GE14 Engineering reviews with G IJF Regulatory Approvals Obtained

- GEXL80

- SLMCPR

- Fuel Vendor Change NRC 6

VJtI GMea GE14 Transition Fuel Vendor Change RAI

• LCR submitted 12/24/03

• RAI conference call 5/10/04

• PSEG response 6/7/04 7

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.G~o~bal Nuceaer Fuel AJ__ts%1 if

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Hope Creek Cycle 13 Safety Limit Minimum Critical Power Ratio (SLMCPR)

NRC Items of Interest

• Cycle 9-

• Cycle 12 12 TIP Comparisons SLMCPR Comparison

• SVEA96+ MCPR Performance using GNF Methodology 8

II Standard Licensing Process Global Nuclear Fuel A... -

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SLMCPR.Repbort to Utility

..:.for:.Submittal".to' NR'C ;for....

..: approval..i.f:require iTS..

change..

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.Core Loading Pattern, C.'

on'trol Blade.Sequence's.

.and Core. Flow..Fracn,..

Transient Selection I Work Scope Review 9

SLMCPR Uncertainties GMF-Global Nuclear Fuel

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DESCRIPTION Non-power Distribution Uncertainties Core flow rate (derived from pressure drop)

Individual channel flow area Individual channel friction factor Friction factor multiplier Reactor pressure Core inlet temperature Feedwater temperature Feedwater flow rate Power Distribution Uncertainties GEXL R-factor Random effective TIP reading Systematic effective TIP reading Integrated effective TIP reading Hope Creek Cycle 12 and 13 Revised NEDC-32601P-A 2.5 Two Loop 6.0 SLO 5.0

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2.04 0.2 Reduced NEDC-32694P-A Hope Creek 1.2 Two Loopl I

12.Two Loo lUncertainties 2.85 SLO are consistent wih ove thapfue Bundle power 10

TIP Comparisons Global Nuclear Fuel ER 11 1]

SLMCPR Comparison Glob!al NuclearFuel

• SLMCPR analysis

- Simulates the limiting point during the transient

- Verifies that at least 99.9% of the rods in the core would be expected to avoid boiling transition

- Performed using NRC approved GNF methodology

• Cycle 13 evaluation submitted for NRC approval

• Cycle 12 being provided for comparison 12

F"MORMTO Aunt I~

C onmp ari son Results QUANTITY, DESCRIPTION Hope Creek Hope Creek.

Cycle 12 Cycle 13 Number of Bundles in Core 764 764 Limiting Cycle Exposure Point' EOR-1.1K EOR-1.1K Cycle Exposure at Limiting Point 12020 10704 r Fuel NMed/MTU)

Reload Fuel Type Latest Reload Batch Fraction, %

Latest Reload Average Batch Weight %

Enrichment SVEA 32.5 3.61 GE14 21.5 4.02 Core Fuel Fraction for GE14 (%)

Core Fuel Fraction for GE9B (%)

Core Fuel Fraction for SVEA (%)

Core Average Weight % Enrichment Core MCPR (for limiting rod pattern)

Calculated Safety Limit MCPR (Two Loop)

Calculated Safety Limit MCPR (SLO) 0.0 6.9 93.1 3.44 1.38 21.5 0.0 78.5 3.64 1.42 1.09 1.06 1.10 1.08 13

(CI Comparison Results Global Nuc ear Fu I

^ _

EOR Cycle 12 EOR Cycle 13 Expected Effect on Cycle 13 SLMCPR (per correlation)

Parameter rE

DLO change

...agrees with D]

expectation

/

~SLO change is less due to 1.06 approaching 1.08 minimum calc valueof 1.07 14 SLMCPR DLO SLO

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SLMCPR Historical Data Global Nuclear Fuel Ul Ii 15

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IPLUE MCPR using GNF Methods GNF Gtob"a8 Nuclear Fuel A..., V_

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SLMCPR Conclusions GtoblaNuclea. Fuel a

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• Reduced power uncertainties are applicable to Hope Creek mixed cores (GE14 & SVEA 96+)

• Differences between Cycle 12 and Cycle 13 SLMCPR results are fully understood

• Results agree with estimations and GNF historical database using NRC approved methodology 17

Cycle 13 Supplemental Reports CARL Global Nuclear Fuel AS r a

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Four Reports to be submitted "for information"

- Fuel Transition Report

- Mixed Core Analysis Report

- Stability

- LOCA Report Address the Cycle independent and Cycle dependent requirements for introducing GE14 at HCGS Address the mixed core performance of GE14 and SVEA-96+

Apply GENE/GNF Methods to SVEA-96+ for consistent design and licensing bases 18

Fuel Transition Report (FTR)

Global Nuclear Fuel

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• Decay Heat

• Neutron Fluence

• Reactor Internal Structural Integrity

• Reactor Recirculation Pump Seizure Event

• Radiation Source Term

• Reactor Internal Pressure Differences

• Seismic

• Combustible Gas Control (LOCA hydrogen generation)

• Mechanical Compatibility

• Fuel Handling Accident

• Anticipated Transient Without SCRAM

• Fuel Storage Requirements

• Banked Position Withdrawal Sequence Acceptability

• Appendix R

• Emergency Procedure Guidelines 19

Cycle 13 Mixed Core Analysis Report (MCAR)

GKlPr Global Nuclear fuel A

4i% 6 01-Qualification of Nuclear Methods for SVEA96+ Application

- TGBLA06 and MCNP Models

- 3D Simulator Accuracy

- Lattice Physics Results for (SVEA-96+ and GE14)

HCGS Core Follow Benchmark TIP Comparisons Thermal Mechanical Analysis Report SLMCPR Report Fuel Management Summary SRLR 20

GE14 Introduction and Thermal Hydraulic Stability

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• First cycle with GE14 Fuel will also be first cycle with OPRM system armed and operable

• Thermal hydraulic compatibility report concluded no adverse effect on relative performance of GE14 and SVEA-96+ fuel designs operating in the Hope Creek core 21

Thermal Hydraulic Stability - Mixed Core Analyses -iI-a

• ICA region confirmation or adjustment

-Reference Loading Pattern from cycle 13 core design input will be used to perform decay ratio calculations

-Either will confirm or adjust the existing ICA boundaries

• Plant-specific DIVOM curve generation

-Reference Loading Pattern from cycle 13 core design input will be used 22

LOCA Analysis Global Nuclear Fuel

• LOCA analysis using SAFER/GESTR

• Demonstrate acceptable performance of GE14 and SVEA-96+fuel

• Demonstrate plant's ability to operate safely and meet all safety and regulatory requirements 23

GNc LOCA Rep~ort Content

,.,~~aIlls~e

• Description of Models (GE14 core & SVEA 96+ core)

• Analysis approach (full break spectrum analysis)

-Large recirculation line breaks

-Small recirculation line breaks

-Non-recirculation line breaks

-Alternate operating modes

• Input to Analysis (CLTP - 3339 MWt)

• SER Compliance

-Licensing basis PCT evaluation

-Plant Specific upper bound PCT not required

• Conclusion 24

Global Nuclear Fuel ARTS/MELLLAA

• MSAR-Submittal - 06/04

- Non-fuel dependent evaluations

• New methods of evaluation

- Fuel dependent evaluations

• GE14 representative core of fuel

• Similar plants

• Updated MSAR - Submittal - 09/04

- Plant and fuel specific analyses

- Additional TS changes if required

• Permits additional time for NRC Reviews 25

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• Global Nuclear Fuel EPU Licensing Approach 4z -A-

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• Prerequisites

- Alternative source term - approved

• Amendments 134 & 146

- GEXL80 - submitted

- Fuel vendor change - submitted

- SLMCPR - submitted

- P/T Limits - submitted

- MELLLA - all required submittals by Sep 04 26

GHU EPU Licensing Approach Go~~t9.~

• EPU License Change Request - March 2005

- 3840 MWt

• Cycle 14 Fuel Supplemental Reports -

March 2005 27

Future Communications Global Nuclear Fuel AleVl.l

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• Establish periodic status communications with SRXB regarding progress of reviews

• Next Meeting

- Approximately July, following Fuel Transition Report transmittal 28

cvzti Olobat Nuclear Fuel I_.an _s

. c-Open Questions 29