ML042180367
| 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 G3bbaiNucebar Fuel Hope Creek Fuel Transition PSEG /NRC Meeting 6/2/2004 Don Notigan, PSEG Nuclear LLC EngineeringSupervisor Hope Creek Reactor & Safe ty Analysis Non-proprietaryversion 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 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
- Thermal-Hydraulic
- Stability Licensing Acceptance
- Rod Drop Accident Criteria
- Nuclear
- Critical Power Correlation
- Thermal-Mechanical
- Overpressure Protection Analysis
- Refuel Accident
- LOCA 5
GE14 Transition Complete GE14 Engineering reviews with G IJF Regulatory Approvals Obtained
- GEXL80
- SLMCPR
- Fuel Vendor Change NRC 6
GMea VJtI GE14 Transition Fuel Vendor Change RAI
- LCR submitted 12/24/03
- RAI conference call 5/10/04
- PSEG response 6/7/04 7
G lur
.G~o~bal Nuceaer Fuel AJ__ts%1 if _SO.
Hope Creek Cycle 13 Safety Limit Minimum C ritical Power Ratio (SLMCPR)
NRC Items of Interest
- Cycle 9- 12 TIP Comparisons
- Cycle 12 SLMCPR Comparison
II Standard Licensing Process Global Nuclear Fuel A...- .g.. .. $1-
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- SLMCPR.Repbort to Utility
..:.for:.Submittal".to' NR'C ;for....
..:approval..i.f:require iTS ..
change..
ig E
- . :;..:..,{ .;Pattern,
- . .g -.Core
.;..:..- Loading on'trol Blade .Sequence's.
C.'
- .and Core. Flow..Fracn, ..
Transient Selection I Work Scope Review 9
GMF-SLMCPR Uncertainties Global Nuclear Fuel
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_0* _4 Hope Creek Cycle 12 and 13 DESCRIPTION Non-power Distribution Revised NEDC-32601P-A Uncertainties Core flow rate (derived from 2.5 Two Loop pressure drop) 6.0 SLO Individual channel flow area Individual channel friction factor 5.0 Friction factor multiplier 1
Reactor pressure 2.04 Core inlet temperature 0.2 Feedwater temperature Feedwater flow rate Power Distribution Reduced NEDC-32694P-A Uncertainties GEXL R-factor Hope Creek Random effective TIP reading 1.2 Two Loopl I 12.Two 2.85 SLO Loo lUncertainties Systematic effective TIP reading are consistent wihthapfueove Integrated effective TIP reading 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~. Conmp ari son Results r Fuel 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 NMed/MTU)
Reload Fuel Type SVEA GE14 Latest Reload Batch Fraction, % 32.5 21.5 Latest Reload Average Batch Weight % 3.61 4.02 Enrichment Core Fuel Fraction for GE14 (%) 0.0 21.5 Core Fuel Fraction for GE9B (%) 6.9 0.0 Core Fuel Fraction for SVEA (%) 93.1 78.5 Core Average Weight % Enrichment 3.44 3.64 Core MCPR (for limiting rod pattern) 1.38 1.42 Calculated Safety Limit MCPR (Two 1.09 1.06 Loop)
Calculated Safety Limit MCPR 1.10 1.08 (SLO) 13
(CI Comparison Results ----
Global Nuc ear Fu I
^ _
EOR EOR Expected Effect on Cycle 13 Parameter Cycle 12 Cycle 13 SLMCPR (per correlation) rE
- DLO change
...agrees with D] expectation
/ ~SLO change is SLMCPR less due to DLO [[ 1] 1.06 approaching SLO [[ 1] 1.08 minimum calc valueof 1.07 14
SLMCPR Historical Data ii"_ Global Nuclear Fuel
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- Ul _
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2A IPLUE GNF MCPR using GNF Methods Gtob"a8 Nuclear Fuel A..., V_ Ni
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SLMCPR Conclusions GtoblaNuclea. Fuel
._.. a A, .
- 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 a r .^
- 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
- .u"-a 1I.. af_
- Decay Heat
- Neutron Fluence
- Reactor Internal Structural
- Reactor Recirculation Pump Integrity Seizure Event
- Radiation Source Term
- Fuel Handling Accident
- Reactor Internal Pressure
- Seismic
- Fuel Storage Requirements
- Combustible Gas Control (LOCA
- Banked Position Withdrawal hydrogen generation) Sequence Acceptability
- Mechanical Compatibility
- 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 _oa "N-
- 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
ARTS/MELLLAA Global Nuclear Fuel
- 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
i7#1 Gr Nuclear Fuel EPU Licensing Approach E E T *Global T **
4z -A- '-"AW."
- 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 _1
- Establish periodic status communications with SRXB regarding progress of reviews
- Next Meeting
- Approximately July, following Fuel Transition Report transmittal 28
cvzti OlobatNuclear Fuel I_.an . _s c- . ..
Open Questions 29