ML021070809
| ML021070809 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/16/2002 |
| From: | Stephen Monarque NRC/NRR/DLPM/LPD2 |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC MB4643, TAC MB4644 | |
| Download: ML021070809 (43) | |
Text
NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-1999)
TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed) by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed form, and the attached copy of meeting handout materials, will be sent to the Document Control Desk on the same day of the meeting; under no circumstances will this be done later than the working day after the meeting.
Do not include proprietary materials.
DATE OF MEETING The attached document(s), which was/were handed out in this meeting, is/are to be placed 04/16/2002 in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:
Docket Number(s) 50-338 and 50-339 Plant/Facility Name North Anna Power Station TAC Number(s) (if available)
MB4643 and MB4644 Reference Meeting Notice Accession No. ML020840200 Purpose of Meeting (copy from meeting notice)
Discussion of the Framatome fuel transition program at North Anna Power Station.
NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE Stephen R. Monarque Project Manager OFFICE Office of Nuclear Reactor Regulation DIVISION Division of Licensing Project Management BRANCH Project Directorate II Distribution of this form and attachments:
Docket File/Central File PUBLIC NRC FORM 658 (9-1999)
PRINTED ON RECYCLED PAPER This form was designed using InForms
A ominion-FRAMATOME ANP North Anna Fuel Transition Program Review Status Meeting NRC-One White Flint North April 16, 2002 April 16, 2002 - 1 A
tminin-Meeting Participants FRAMATOME ANP Dominion
"* G. L. Darden - Program Manager/Nuclear Safety Analysis
"* E. T. Shaub - Nuclear Licensing Framatome ANP
"* J. R. Biller-LOCA Analysis
" B. M. Dunn - LOCA Analysis
"* R. J. Lowe - LOCA Analysis
"* J. S. Holm - Manager, Product Licensing
"* C. K. Nithianandan (Nithian) - LOCA Analysis
"* R. D. Williamson - Project Manager
"* G. J. Wissinger - LOCA Analysis April 16, 2002 - 2 1
ý A
)DoWminion-Introductory Remarks FRAMATOME ANP Meeting Objectives Presentation Topics Status of Transition Program Activities G. L. Darden - Dominion April 16, 2002 - 3 A
.Ovfminln Presentation Topics FRAMATOME ANP Status of Transition Program Activities North Anna-Specific LOCA Licensing Needs
"* BEACH Submittal
"* North Anna Plant-Specific Items/EM Departures
- Integrated Transition Program Review Schedule Questions/Action Items April 16, 2002-4 2
Status of Transition A
'UDminkn Program Activities FRAMATOME ANP Summary Content of Dominion License Amendment Request Issued 3/28/02
" Design Features-Advanced Mark-BW Fuel Product
" Evaluations Performed
- Mechanical Design
- Structural Design (Normal Operation and Faulted Conditions)
- Thermal-Hydraulic Analysis
- Compatibility (Mechanical, Interface and Neutronic)
- Non-LOCA Accident Evaluations
- LOCA Analyses [Ongoing-Detailed Discussion to Follow]
- Spent Fuel Pool Criticality
- Impact on Radiological Consequences of Accidents April 16, 2002 - 5 Status of Transition A
Program Activities FRAMATOME ANP TS Changes Requested
"* Safety Limits (TS 2.1.1)-Define Separate Fuel Centedine Melt Relationship for W & Framatome ANP Fuel, as Follows:
"The peak fuel centerline temperature shall be maintained < 50800F, decreasing by 58OF per 10,000 MWT/MTU of burnup, for Westinghouse fuel and < 51730F, decreasing by 65OF per 10,000 MWD/MTU of burnup, for Framatome ANP fuel."
"* Design Features (TS 4.2.1)-Add Framatome ANP M5TM Alloy to List of Cladding Materials
"* Core Operating Limits Report (TS 5.6.5b)-Add References for Framatome ANP Methodologies April 16, 2002-6 3
Status of Transition A
IDaminion Program Activities FRAMATOME ANP Regulatory Exemptions for Use of M5Tm Clad Alloy
" Requested Since Existing Language Does Not Specifically Accommodate Use of M5Tm (Only Zircaloy and ZIRLOTM Cited)
" 10CFR50.44(a)-Addresses Post-LOCA Hydrogen Gas Control
- Baker-Just Model Conservative for M5TM
- Existing North Anna Hydrogen Analyses Not Impacted
"* 10CFR50.46(a)(1)(i)-Addresses ECCS Performance
- Acceptance Criteria of 1 OCFR50.46(b) Applicable to M5TM
- North Anna Analyses Will Conform to Acceptance Criteria
.- Intent of Each Regulation is Met for North Anna April 16, 2002-7 Status of Transition A
Program Activities FRAMATOME ANP Documentation of Framatome ANP Mixed-Core Analysis Methodology
"* General Approach
- Thermal-Hydraulic Analysis Performed for Various Core Configurations and Plant Operating Conditions
- Bounding Mixed-Core DNB Effect Explicitly Quantified
- Allows Separate Assessment of W and Framatome ANP Fuel Using CHF Correlations Applicable for Each Design
"* Analyses Support Key Operating Limits
- Core Power (Including Measurement Uncertainty Up-Rating)
FAH Limit: 1.538 (1sT Transition Cycle) and 1.587 (2 ND Cycle)
- Current Core Thermal Limits April 16, 2002-8 4
Status of Transition A
Dominion Program Activities FRAMATOME ANP "Dominion Topical Changes
" VEP-FRD-42, Revision 2-Submitted 1018/01
- Qualification of Reload Methodology for Framatome ANP Fuel
- Discussed in March 11 Teleconference with NRC Staff
- Draft RAI Responses Discussed with NRC Staff on April 15
"- VEP-NE-1, Revision 1-Relaxed Power Distribution Control
- Revisions to Address Use of Framatome ANP Fuel
- Scheduled Revision per 10CFR50.59 by 7131102 April 16, 2002-9 fh A
Domninlan Introductory LOCA Remarks FRAMATOME ANP LOCA Licensing Needs J. S. Holm - Framatome ANP April 16, 2002-10 5
6 A
SDominion LOCA Licensing Needs FRAMATOME ANP BEACH Topical Report
"* Initial Reflood Temperature
"* Reflood Rate
, North Anna Plant-Specific Items/EM Departures
" Core Peaking for LOCA Evaluation
"* Energy Deposition
"* Average Core Energy Representation
"* Minimum Containment Backpressure
"- REFLOD3B Carryout Rate Fraction
"* End of Transient Justification
"* Oxide Calculations
"* SBLOCA Noding April 16, 2002 - 11
A
_ODominion LOCA Topics FRAMATOME ANP North Anna-Specific LOCA Licensing Needs
"* LOCA Submittals--Status
- Fuel Temperature Uncertainty (Completed 4/9/02)
- BEACH Revision
"* The North Anna Analysis Challenge
"* Overview of North Anna-Specific Items
" Detailed Discussion of North Anna-Specific Items April 16, 2002-13 North Anna-Specific A
LOCA Licensing Needs FRAMATOME ANP LOCA Submittals RSG EM: BAW-10168PA-03 RELAPE BAW-1,0164PA-03 "Current Approved Evaluation Model REFLOD3B: GAVW-10171PA-03 BEACH: BAW-10166PA-04 EM Letter Fn-00-551, 2/29/00 i
"* Fuel Temperature Uncertainty RELAP5: BAW-10164P-04, 9/99 Completed: SER 4/9/02
"* BEACH Revision
[BEACH: BAW-1016O-05, 1 I
April 16, 2002 - 14 7
A
- 4fminin-BEACH Revision FRAMATOME ANP
>- BEACH Appendix H and I
"* BEACH Approved Applicability Ranges Limited
"* Appendix H Requests Increase of Initial Clad Temperature
- 1,640 F to 2,045 F
"* Appendix I Requests Change of Lower Flooding Rate
- 0.5 in/s to 0.3 in/s
"* BEACH is Mechanistic with Extensive Experimental Benchmarks
"* Extensive Benchmarks Provided for These Changes
"* Information Sufficient for Ready Approval April 16, 2002-15 North Anna-Specific A
SLOCA Licensing Needs FRAMATOME
>- The North Anna Analysis Challenge
" Reactor Vessel Upper Head Geometry
- Traps Water-Unavailable for Core Cooling
- Plugs Spray Nozzles
" THOT Plants with Sub-Atmospheric Containments
- Reduced Flooding Rates
"* Spray Nozzle Sizes Promotes Steam Binding
"* Low Containment Backpressure Promotes Added Steam Binding April 16, 2002 - 16 8
North Anna-Specific A
' Dominion LOCA Licensing Needs FRAMATOME ANP North Anna Plant-Specific Items/EM Departures
"* Core Peaking for LOCA Evaluation
"* Energy Deposition
"* Average Core Energy Representation
"* Minimum Containment Backpressure
"* REFLOD3B Carryout Rate Fraction
"* End of Transient Justification
"* Oxide Calculations
" SBLOCA Noding April 16, 2002-17 LOCA Overview A
~DominionFR ATMAN o
Concluding Remarks FRAMATOME
,- LOCA Submittals
"* All Been Issued
"* Are Under NRC Review
"* No Additional Topical Report Revisions Planned
.- North Anna Plant-Specific Items/EM Departures
"* Issued by LOCA LAR Supplement "OR"
"* Issued by Letter Prior to LOCA LAR Supplement
"* "NRC CHOICE"
"* NRC FEEDBACK AT MEETING END Transition Requires Both LOCA Submittals and North Anna-Specific Items April 16, 2002-18 9
31%
North Anna-Specific A
DOminion LOCA Licensing Needs FRAMATOME ANP North Anna Plant-Specific Items/EM Departures X
Core Peaking for LOCA Evaluation Bert Dunn April 16, 2002-19 Core Peaking for A
LOCA Evaluation FRAMATOME ANP LOCA Core Modeling
"* Hot Pin
"* Hot Assembly
"* Average Core Preserve North Anna Operational Flexibility
- LOCA Assumptions Should Follow and Support Existing Limiting Conditions of Operation (LCO) Control Methodology North Anna LCO Methodology Controls FQ FAH April 16, 2002 - 20 10
-aaih Core Peaking for A
SDominion LOCA Evaluation FRAMATOME ANP North Anna Power Distribution Determinants
" LCO Methodology
- Develop Set of "Normal" Power Distributions-Condition I Events
- Screen Set of Shapes to Those Allowed Axial Imbalances that Support Plant F. and FAH Limits with Peaking Uncertainty Applied
- Compliance with FQ and F.H is Surveyed During Operation
" Reload Check
- From Screened Power Distributions Determine Maximum Assembly Power (Including any Methods Bias)
- If Maximum Assembly Power is > LOCA Assumption
"* Further Reduce Imbalance, or
"* LOCA Calculations (Evaluation/Rerun)
April 16, 2002 - 21 Core Peaking for A
SLOCA Evaluation FRAMATOME ANP
>- Peaking Distribution Characteristics:
"* Hot Pin at Maximum Local Peaking (F.) Allowed by Tech Specs with Provision for Calculation and Measurement Uncertainties
"* Full Uncertainties Applied to Hot Pin Calculation Regardless of Elevation at Which Peak Cladding Temperatures Occurs
"* Fluid Conditions for Cooling Hot Pin are Most Severe Expected
"* Liquid Entrainment and Coolant Vapor Velocities Not Exaggerated April 16, 2002-22 11
I*Dominion Core Peaking for A
LOCA Evaluation FRAMATOME ANP Peaking for North Anna Reload LOCA Calculations
"- FQ, FaH, and Hot Assembly Radial Selected by Dominion "Peaking Results Value
- Hot Pin
"* Radial
= FaH (LCO) 1.60
"* Axial
= F0 (LCO) I FH 1.37 Hot Assembly
"* Radial
= DG-Supplied (Reload Check) 1.45
"* Axial
= Hot Pin Axial 1.37
- Average Core
"* Radial
= -1.0 0.997
"* Axial
= Hot Pin Axial 1.37 April 16, 2002-23 North Anna-Specific A
SDminion LOCA Licensing Needs FRAMATOME ANP North Anna Plant-Specific Items/EM Departures X
Energy Deposition Bert Dunn April 16, 2002 - 24 12
S~A
)D@minion Energy Deposition FRAMATOME ANI Energy Deposition Factor (EDF)
"* Approved EM: 0.95 Both Steady State and Transient
"* EDF Calculations for North Anna Resulted in Higher Values
"* North Anna LOCA Will Use the More Conservative Calculated Values:
- Steady State
= 0.974 for Hot Pin
= 0.974 for Hot Assembly
= 0.974 for Hot Pin
= 1.0 Hot Assembly April 16, 2002-25 North Anna-Specific A
Domfiann LOCA Licensing Needs FRAMATOME ANP North Anna Plant-Specific Items/EM Departures X
Average Core Energy Representation Bert Dunn April 16, 2002-26 13
rnnn Average Core A
O minion-Energy Representation FRAMATOME ANP Average Core Energy Representation
" Core Comprised of Categories of Fuel Assemblies
- Fresh Assemblies
- Once-Burned Assemblies
- Twice-Burned Assemblies
" Average Core Representation for Energy Content (Initial Fuel Temperature and Transient Actinide Power) Conservatively Evaluates and Combines the Differences for Each Category
- Category Radial Peaking
- Category Burnup Effect on Fuel Temperature
- Category Burnup Effect on Actinide Concentration April 16, 2002-27 North Anna-Specific A
nNeeds FRAMATOME ANP North Anna Plant-Specific items/EM Departures X
Minimum Containment Backpressure John Biller April 16, 2002 - 28 14
ft..
Minimum Containment A
-Dominin Backpressure FRAMATOME ANP Approved EM: Use FSAR Backpressure
"* UFSAR Backpressure Curves Stop at 240 sec
- Not Proper to Extrapolate
"* PCTs Occur in 200 sec Neighborhood Need Prediction Beyond 240 sec
"* Perform Backpressure Calculation
- EM Departure
" North Anna Containment-Normal Components
- Dry Containment
- Domed Cylinder w/Painted Steel Liner
- ECC Spray Safety Systems
- Typical Equipment and Materials Within Containment April 16, 2002 - 29 Minimum Containment A
aminion Backpressure FRAMATOME ANP Use B&WRELAP5 EM Method
"- NRC-Approved
- B&W EM: BAW-10192PA, Revision 0
- CONTEMPT: BAW-10095A, Revision 1
- Follows CSB 6-1
" North Anna Comparable to B&W Containments
- No Applicability Issues
- Same Backpressure Trends as Westinghouse Calculation
- FRA-ANP Backpressure Slightly Under-Predicts Westinghouse Conclusion
"* CONTEMPT Model Appropriate Method for North Anna Use
"* Appendix-K Compliant April 16, 2002 - 30 15
D mnk Minimum Containment A
SBackpressure FRAMATOME ANP FRA-ANP versus Westinghouse Prediction 5I 1
1 1
4
-- FRA-N DELC
.6, MU ECC
-- WDEMMG, CO-:OA, MýnECC NA LISAR 35 w DECLGD C-0.6, ME. ECC NA UFSAR (0
North Anna Minimum Containment BackprssUre I 0
5o 100 iso 200 250 3o0 350 400 450 5So Time, sec April 16, 2002-31 North Anna-Specific A
LOCA Licensing Needs FRAMATOME ANP North Anna Plant-Specific Items/EM Departures X
REFLOD3B Carryout Rate Fraction C. K. Nithianandan April 16, 2002-32 16
REFLOD3B A
Fraction FRAMATOME ANP REFLOD3B RV Plant Model REACTOR VESSEL MODEL
"°I I
Yo.r-3R April 16, 2002-33 REFLOD3B A
mn Carryout Rate Fraction FRAMATOME ANP REFLOD3B--Approved Methodology
- During Quasi-Steady Period Core Exit Flow Calculated Using FLECHT/FLECHT-SEASET-Based NRC-Approved Carryout Correlation-CRFCKN
- Upper Core Region (Volume 1R)-Thermal Equilibrium Fluid Condition Assumed
- Entraining Liquid in Superheated Steam Causes Numerical Oscillations
"* To Avoid Numerical Problem Entrain Enough Liquid to Keep Upper Core Region Two-Phase
- Conservative Artificiality Imposed for Numerical Purposes
"* Only Brief Departures from Carryout Correlation Expected April 16, 2002 - 34 17
REFLOD3B A
SD@minion Carryout Rate Fraction FRAMATOME ANP Illustration-Typical 4-Loop Case A-Developing Period; B-Transition Period; C-Quasi-Steady Period 4-LOOP PLANT CASE LBLOCA - 10.0-ft Peak CARRYOUT RATE FRACTION
- 1.
LEGEND
-USED IN THE CODE 1.0 CORRELATION S0.
"0 I
BASE CRFC.EN OPTION 0.4 0.2 A I
D 80 160 240 320 400 TIME I-Ro)
April 16, 2002-35 REFLOD3B A
SD~mli~itFRAMATOME ANP Dominion-Carryout Rate Fraction
,- North Anna-Base CRFCKN Option 3-LOOP PLANT CASE LBLOCA - 6.8556-ft Peak CARRYOUT RATE FRACTION W FLOODING RATE 1.0
- 0.6 RASE CRFCKN OPTION I-2 50.4 0
so 160 240 320 400 TIME IsRD April 16, 2002 - 36 18
moREFLOD3B A
Ominion Carryout Rate Fraction FRAMATOME ANP North Anna-Low Flooding Rate Plants
- Forces Excessive Core Carryout
- Well Above CRF Correlation o REFLOD3B Logic Maintains Upper Core Region Two-Phase Self-Perpetuates
"* Increased Steam Binding
"* Lower Flooding Rate
"* Increased Core Carryout
- Unintended Consequence of Two-Phase Logic
- Non-Physical April 16, 2002 - 37 SREFLOD3B A
Dpftminion-Carryout Rate Fraction FRAMATOME ANP REFLOD3B-North Anna-Specific CRF Option
"* Developing and Transition Periods
- No Change
"* Quasi-Steady Period
- Base Model:
- Maximum-CRFCKN Correlation OR Needed to Keep Upper Core Region Two-Phase North Anna-Specific Model:
"* Use CRFCKN Correlation-AS IT SHOULD
"* Numerical Issues Present Starting About 400 sec April 16, 2002-38 19
REFLOD3B A
_oDaminion-Carryout Rate Fraction FRAMATOME ANP North Anna-Specific CRFCKN Option 3-LOOP PLANT CASE LBLOCA - 6.8556-ft Peak CARRVOM RAT! FRACION
-e M -L00010 RAE 1.2 50.0 MO0IFIE-CRFCKN OPTION o
A
> o.4 0.2 0
00 1"0 240 320 400 TRME
(-I0)
April 16, 2002 - 39 REFLOD3B A
Carryout Rate Fraction FRAMATOME ANP North Anna-Flooding Rate Comparison 3-LOOP PLANT CASE LBLOCA - 6.8556-ft Peak CORE INLET FLOODING RATE IL-
-EGEND 8-BASE CRIF Optoi 5.-
3-MODIFIED CRRF Opviý 4
3 o
2 013 160 240 320 400 Ti.. 1,04)
April 16, 2002-40 20
REFLOD3B A
SDominikn CRAMATMouAN Carryout Rate Fraction FRAMATOME ANP North Anna-Hot Rod Clad Temperature Comparison 3-LOOP PLANT CASE LBLOCA - 6.8556-ft Peak 240 0 LEGEND BASE CRF Option 2000 13-MODIFIED CRF O
.1600
ý200 HOT ROD CLAODING TEMP2FERATJRE at 7.71 FT.
800 400 0
8o 160 T
40 320 400 April 16, 2002-41 REFLOD3B A
DO**IlIFRAMATOM E ANP Carryout Rate Fraction Frcto IRM OEIN
>- Impact on Benchmarks
"* Previous Benchmarks
- FLECHT-SEASET Test 33338
- Semi-Scale MOD-1 Test S-04-06
"* In Both Cases Core Exit Flow Calculated Using CRF Correlation Sufficient to Keep Upper Core Region Two-Phase
Conclusion:
CHANGE HAS NO IMPACT April 16, 2002 - 42 21
Dotk REFLOD3B A
Carryout Rate Fraction FRAMATOME ANP Appendix-K Compliance
"* CRF Calculated Using Approved Correlation
"* Option to Bypass Logic Added in Approved REFLOD3B to Avoid Potential Numerical Problem Conclusion
" Change Necessitated by Unique Nature of North Anna Plants
"* Change Does Not Alter Benchmarks
"- Change Consistent with Appendix-K Requirements April 16, 2002-43 North Anna-Specific A
' o~rnrn~n LOCA Licensing Needs FRAMATOME ANP North Anna Plant-Specific Items/EM Departures X
End of Transient Justification C. K. Nithianandan April 16, 2002 - 44 22
Mil A
Dominion End of Transient Justification FRAMATOME ANP REFLOD3B Calculation Terminates at 400 sec
"* Code Numerical Issues
"* Approaching Code Applicability Limit
" Prior to Calculated Core Quench
)- Justification to End Transient at 400 sec
"* After Calculated Peak Cladding Temperature
"* Average Core Temperature Below Oxidation Potential (<1,200 F)
"* Average Core Quench Height Near 9 Foot Level
"* Hot Assembly Quench Height Should Also be Near 9 Feet with Low Cladding Temperatures
"* Experiments Show Core Quench Before 400 sec
" Realistic Calculations Show Core Near Quench at 400 sec April 16, 2002-45 A
.Dominiion End of Transient justification FRAMATOME ANP
- North Anna-Modified CRF Case 3-LOOP PLANT CASE LBLOCA - 6.8656-ft Peak CLAD TEMPERATURE 7.71 a.d 11.7 FT 2400 0
AC-20 00 1p00
~1300 400 I
0 50 100to 150 200 250 300 350 400 TIME 0-~)
April 16, 2002 - 46 23
1 A
FRAMATOME ANP Demmninon End of Transient Justification
.-North Anna-Modified CRF Case 3-LOOP PLANT CASE LBLOCA - 6.8556-ft Peak 0f April 16,2002-47 A
O Dominion-End of Transient Justification FRAMATOME ANP Slab Core Test Facility (SCTF) CORE-Ill Test S3-15 Bundle #
1 2
3 4
5 a
7 8
Power Ratio 1.36 1.20 1.10 1.00 0.31 0.86 0.81 0.76 SCTF CORE-1ll Test 53-15 4
3.5 S1.5 o
10.5
--* =Averge Power Bndle 0
100 200 300 400 A rl1 (s)
April 16, 2002-48
)Dominion End of Transient Justification A
FRAMATOME ANP
.- BEACH Benchmark of SCTF Test S3-15 FIGURE G-72. HOT CHANNEL QUENCH FRONT SCTF TEST 3-15.
300 0
100 200 TIME, SEC 0
3.5 3.0 2.5 2.0 1.5 1.0 0.5 0.1 '
400 FIGURE G-73. AVERAGE CHANNEL QUENCH FRONT JAERI SCTF TEST 3-15.
0 100 200 TIME, SEC 300 400 April 16, 2002 - 49 1250 1000 750 2500 250 BEACH Benchmark of SCTF Test S3-15 FIGURE G-70. HOT CHANNEL CLAD TEMPERATURE FIGURE G-71. AVERAGE CHANNEL CLAD TEMPERATURE JAERI SCTF TEST S3-15.
JAERI SCTF TEST S3-15.
0 100 200 TIME SEC 300 400 i 1250 5; 1000 750 Soo 250 0
100 200 TIME, SEC 300 400 April 16, 2002 - 50 2
uF
.5
21
1
P =0.20 MPa TCo = 800 C Q = 7.12 MWt Tsub = 80 C Vi.
0.37 kgse r
,=1 JDominion A
End of Transient Justification FRAMATOME ANP 4-
3 A
FRAMATOME ANP
- Dominon End of Transient Justification
.-RLBLOCA Results for 3-Loop Plants E
150.0 200.0 rime, S April 16, 2002-51 f
A O f@rnt nion End of Transient Justification FRAMATOME ANP
.- Conclusion Ending Transient at 400 sec Justified
- After Calculated Peak Cladding Temperature
- Average Core Temperature Below Oxidation Potential (<1,200 F)
- Average Core Quench Height Near 9 Foot Level
- Hot Assembly Quench Height Should Also be Near 9 Feet with Low Cladding Temperatures
- Experiments Show Core Quench Before 400 sec
- Realistic Calculations Show Core Near Quench at 400 sec April 16, 2002-52
North Anna-Specific A
')`Dominion-LOCA Licensing Needs FRAMATOME ANP North Anna Plant-Specific Items/EM Departures X
Oxide Calculations Gordon Wissinger April 16, 2002 - 53 A
Dominon-Oxide Calculations FRAMATOME ANP Current RSG EM Oxide Calculation
- Amount of Metal-Water Reaction at Any Elevation in Core is Determined by Ratio of Adjusted Power Times Metal-Water Reaction at That Elevation in Hot Channel
- Calculation Based on REFLOD3B Quench Front Prediction
- Adjusted Power is Power in Excess of Minimum Power for Which Any Oxidation Increase Occurs
- 1,000 F Clad Temperature Metal-Water Cutoff Integration Over Core Then Gives Core-Wide Oxidation Increase or Amount of Hydrogen Generation
- Based on Assumed Core Radial Power Distribution
- Ten Subdivisions with Average Radial Power per Division April 16, 2002-54 4
A JODoamnion@
Oxide Calculations FRAMATOME ANP RSG Axially Dependent Local Oxidation Hot Pin Oxidation 0/
X Curve Used in Whole 0
Cr CoeEvalu tiorn
-0 Realistic Oxidation Curve Power April16, 2002-55 A
Spfminion Oxide Calculations FRAMATOME ANP Method Change "Transient is Finished at 400 sec
- Use Oxides at 400 sec
- Conservative Based on Highly Conservative Cladding Temperature Response
" Change Oxide Calculation to Mimic NRC-Approved OTSG Whole-Core Metal-Water Calculation Technique
- LOCA Simulation Uses 3 Heat Structures
- Extrapolation of Hot Pin to Whole-Core Excessively Conservative
- Close to Exceeding 1% Criterion April 16, 2002-56 5
Z41 A
Oxide Calculations FRAMATOME ANP Change Oxide Calculation to Mimic NRC-Approved OTSG Whole-Core Metal-Water Calculation Technique
"* Use Oxidation Increase from Three (3) Heat Structure Simulation with Typical Core Power Map
- Hot Pin, Hot Bundle, and Average Core
"* Hot Channel and Average Core Local Oxidation Increases are Used to Determine Oxidation Increase for Assemblies in Which Radial Power Factor Lies Between Them
"* Assemblies with Radial Power Factors Below Average Core Value Use Average Core Oxidation Increases
"* Integration of These Channels Over Entire Core Results in Core-Wide Oxidation Increase or Amount of Hydrogen Generation April 16, 2002-57 A
Dominion Oxide Calculations FRAMATOME ANP RSG Axially Dependent Local Oxidation w/3 HS Hot Pin Oxidation 0/
0X Curve Used in Whole Core Evaluation
/
Hot channel "0
Oxidation Average Channel
/
Realistc Oxidation SOxidation Curve Power April 16, 2002-58 6
A
- Dfminio@n Oxide Calculations FRAMATOME ANP RSG Core Power Distribution w/3 HS 0.6 0.5--------------------------------------------------------------------
Average Channel Power 2 0.4 - / ------------------
0 01 S0.3 o
I-k Pin Po*wer Hct Channel Power 0.0 0.997 1.047 1.098 1.148 1.198 1.249 1.299 1.349 1.400 1.450 1.600 Radial Power April 16, 2002-59 A
Dominion-Oxide Calculations FRAMATOME ANP SConservatism in Method Conservative Cladding Temperature Response Oxidation in Base Run Computed Using Baker-Just Correlation
- -50% Conservative
- Core Power Distribution
- Reasonable and Representative
- Pushed to Peak Powers Allowed by Plant Tech Specs
- Power Ratio Determining Degree of Oxidation for Lower Power Zones is Conservative
- 40% of Core at Average Core Power April 16, 2002 -
60 7
UL m
North Anna-Specific A
DZ min LOCA Licensing Needs FRAMATOME ANP North Anna Plant-Specific Items/EM Departures X
SBLOCA Noding C. K. Nithianandan April 16, 2002-61 SD@nini@ -
SBLOCA Noding FRAMATOME ANP North Anna 3-Loop Plant-EM Model
- When Intact Loop Clears
- Entrains Intact Loop ECC to Break
- Less Thwm Expected ECC Penetates Downcomer RELAP5 SBLOCA Upper Downcomer Noding Arrangement - Base Model 800 Iftact Loop Broken Loop 148 04 348 To Break 806 RV Downco*ner April 16, 2002-62 8
A ominion-SBLOCA Noding FRAMATOME ANP EM Intact Loop Bias 0 1-foot Bias to Promote Broken Loop Clearing-4-Loop Plant foot+ Bias Required-3-Loop Plant
- Bias Becoming Excessive
- UPTF Test 25
- Test to Evaluate ECC Entrainment During Reflood
- Wallis CCFL-Type Correlation-Calculate DC Liquid Level (NUREG/1A-0126, Figure 4.3-4)
- UPTF Correlation Predicts Higher Downcomer Level Than RELAP5 for SBLOCA Cases April 16, 2002-63 A
PD@m, Won-SBLOCA Noding FRAMATOME ANP Upper Downcomer Geometry-Revised Model
- Hot Leg Penetrations Block This Region
- Intact Cold Leg Flow to Break
- Must Go Up and Over or Down and Under Hot Leg Penetration RELAP5 SBLOCA Upper Downcomer Noding Arrangement-Revised Model Intc Lo Broken Loop To Break--
RV Downcomer April 16, 2002 - 64 9
A FRAMATOME ANP J'Dominion-SBLOCA NodingFRMTEAN North Anna-Downcomer Level Comparison 3-LOOP PLANT SBLOCA CASE: 3.0-INCH BREAK DOWNCOMER LEVEL 12
'[
4 I-EOEND
6 RELAPS 6-UPTF CORR.
o 0
2000 4000 6000 8000 TIME (s)
April 16, 2002-65 N
A Dominion-SBLOCA Noding FRAMATOME ANP SNorth Anna 3-Inch Break Case 3-LOOP PLANT SBLOCA CASE: 3.0-INCH BREAK 3-LOOP PLANT SSLOCA CASE: 3.0-INCH BREAK UPPER PLENUM PRESSURE HOT CHANNEL PCT.
2400 2400 20200 0
20 IGD0O
- 1600 TIME WS TIME MI April 16, 2002-66 10
A
-ODuminion-SBLOCA Noding FRAMATOME ANP Conclusion
"* Plant Noding Change Necessitated by Nature of North Anna Plants
"* DC Liquid Level Conservatively Calculated (Based on UPTF Correlation)
"* Change Consistent with Appendix-K Requirements April 16, 2002-67 A
Doainkon Concluding LOCA Remarks FRAMATOME ANP LOCA Licensing Needs J. S. Holm - Framatome ANP April 16, 2002-68 11
p A
DXomnion LOCA Licensing Needs FRAMATOME ANP BEACH Topical Report Initial Reflood Temperature
- Reflood Rate North Anna Plant-Specific Items/EM Departures
- Core Peaking for LOCA Evaluation
- Energy Deposition
- Average Core Energy Representation
- Minimum Containment Backpressure REFLOD3B Carryout Rate Fraction
- End of Transient Justification
- Oxide Calculations
- SBLOCA Noding April 16, 2002-69
,1 A
," Dominion LOCA Licensing Needs FRAMATOME ANP RLBLOCA Results for 3-Loop Plants 2200 1 O000 1000 1000 2000 2O.0 0000 0500 4000 lime, s April 16, 2002-70 12
Concluding Comments A
Dominion Integrated Review Schedule FRAMATOME ANP Integrated Transition Program Review Schedule G. L. Darden - Dominion April 16, 2002 - 71 Integrated A
i'Dominion Review Schedule FRAMATOME ANP Key Milestones-License Amendment Request for North Anna Transition Including Approval of North Anna-Only LOCA Changes
- Dominion Submits LAR-Completed 3/28102
- SER BAW-10164P, Revision 4-Fuel Temperature Uncertainty-Completed 4/9/02
- Target Date for First RAI---6115/02 ???
April 16, 2002 - 72 13
Integrated A
Dominkn Review Schedule FRAMATOME ANP Key Milestones-License Amendment Request for North Anna Transition Including Approval of North Anna-Only LOCA Changes, Continued
" SER BAW-10166, Revision 4, Appendices H and I-BEACH
- 711102
"* Dominion Issues LOCA Supplement to LAR-August 2002
"* Target Date SER on VEP-FRD-42, Revision 2-8131102
"* Target Date Last RAI-10131/02
"* NRC Draft SER for LAR-12115/02
"* Target Date to Issue SER-1131/03
"* Delivery First Framatome ANP Reload Batch-January 2003 April 16, 2002-73 Summary A
Questions, Action Items,_
FRAMATOME ANP Summary Questions Action Items G. L. Darden - Dominion April 16, 2002-74 14
A FRAMATOME ANP TO:
James F. Mallay 20553A-8 (1/2002)
FROM John R. Biller CUSTOMER OR FILE:
SUBJ.
BEACH Topical Report Revision-BAW-10166, Revision 5 DATE:
NRC Verbal Request for Information April 3, 2002
Reference:
Framatome ANP Letter, J. F. Mallay, to Document Control Desk, NRC, "Request for Review of Appendices H and I to BAW-10166," NRC:01:050, December 10, 2001.
On March 27, 2002, Messrs. Biller, Dunn, Klingenfus, Mallay and Nithian of Framatome ANP, Mr. Frank Orr of the NRC, and Mr. Len Ward, an NRC contractor, participated in a telephone call regarding the referenced submittal. During the call, Len Ward requested explanatory and reference materials relative to Framatome ANP's BEACH submittal. A partial response to Mr.
Ward's requests follows.
Enlarged copies of figures 1-15 and 1-17 were requested; they are attached hereto. These two figures are actual copies of the original digitized test benchmarks, rather than just enlargements of the Appendix I figures. For ease of reference, these figures are labeled with the same Appendix I figure numbers. The third and fourth figures attached hereto are two different versions of Figure 1-24. One with and one without shading within the envelope. The data points beneath the envelope should be visible in either figure.
Regarding the question on vapor temperature, void fraction, and droplet diameter, your attention is directed to the NRC-approved version of the BEACH topical Report-BAW 10166P-A, Revision 4, February 1996. Please note the materials responding to Question 14, page 5-43 and Figures 14-1 through 14-18 on pages 5-107 through 5-115. Chapter 5 of the report contains, in chronological order, all BEACH licensing materials or references thereto.
Relative to the quench front prediction for FLECHT Test 8037, Framatome ANP agrees that the benchmark of this test indicates an excessively quick decrease in cladding temperature.
However, this test appears to be outside the norm in this regard. In the BEACH topical report, Question 1, the subjects of quench time and metal-water reaction were discussed; please refer to pages 5-291 through 5-302. Also note the Revision 4 SER and TER on pages 5-340 and 5 341, and 5-354 and 5-355, respectively, where the effects of the earlier higher temperatures and the cladding gap are credited as trading off against the slightly earlier BEACH quench prediction.
FIGURE 1-24. TEMPERATURE RISE VRS. FLOODING RATE TO ROD PEAK POWER RATIO 2400.00 FLECHT-SE 2000.00 BEACH-FLE' pproximate Range FLECHT of BEACH Predictions BEACH-FLE' I
A FLECHT-SEj 1600.00 A BEACH-FLE' IL 0
0 800.00
. ]..
- 0)
-% ~~
- - -N 1200.00 0)0 0.00 1.00 2.00 3.00 4.00 5.00 6.00 Vin/Q {(inls)l(kWlft)}
ASET CHT-SEASET CHT ASET-L CHT-SEASET-L 7.00 8.00 9.00 10.00
FIGURE 1-24. TEMPERATURE RISE VRS. FLOODING RATE TO ROD PEAK POWER RATIO
-0 FLECHT-SEASET m BEACH-FLECHT-SEASET O FLECHT
- BEACH-FLECHT A FLECHT-SEASET-L A BEACH-FLECHT-SEASET-L 2400.00 2000.00 1600.00
- c. 1200.00 E
800.00 400 00 01 0
0.00 0
0.00 1.00 2.00 3.00 4.00 5.00 Vin/Q {(in/s)/(kW/f 6.00 7.00 8.00 9.00 10.00 0-
FIGUREJ' /.5
_FLECHT 3215B (15x15) BENCHMARK f3215v25.in 32-5014735-00 PC =20.O psia,TCO= I1100,Q =0.84,TI ~var TSUB =var,VIN =var PUP = var TuOct 11 10:12:54 2001 XVGXVELFJOOI 1.5 0
04
FIGURE -7'- '7 FLECHT 3316B (15x]5) BENCHMARK f3316v25.in 32-5014735-00 P=var,TCO= 1100,Q=0.84,TI= var TSUB =var,VIN =var Thu ct11ZGDNVELFJOOI a,,
4-.
0
'mu Ocl I I