ML042180367
| ML042180367 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/02/2004 |
| From: | Notigan D Global Nuclear Fuel - Americas, 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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16
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