ML15261A162
| ML15261A162 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/06/1998 |
| From: | Labarge D NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| TAC-M88660, TAC-M96728, TAC-M98661, TAC-M98662, TAC-M99349, TAC-M99350, TAC-M99351, NUDOCS 9802240010 | |
| Download: ML15261A162 (22) | |
Text
February 6, 1998 L!CENSEE:
Duke Egy Corporation FACILITIES:
Oconee Nuclear Station, Units 1 and 2
SUBJECT:
MEETING
SUMMARY
- MEETING OF JANUARY 27, 1998, REGARDING CRITICAL HEAT FLUX AND UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) CHAPTER 15 TOPICAL REPORTS (TAC NOS. M96728, M88660, M98661, M98662, M99349, M99350, AND M99351)
REFERENCES:
(1) Meeting Notice by D.E. LaBarge, January 12, 1998 (2) Letter, M. S. Tuckman to NRC, "Oconee Nuclear Station Transition to Framatome MkB1 1 Fuel," dated December 2, 1997 (3) Letter, M. S. Tuckman to NRC, "Use of BWU-Z Critical Heat Flux Correlation for Mark-B1 1 Fuel," dated April 22, 1997 (4) Letter, M. S. Tuckman to NRC, "Topical Report DPC-NE-3000P, Revision 2," dated December 23, 1997 (5) Letter, M. S. Tuckman to NRC, "UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-P," dated July 30, 1997 On January 27, 1998, the staff met with Duke Energy Corporation (DEC) personnel to discuss the contents of DEC's topical reports dealing with conversion to Mark B-11 fuel at Oconee and changes to Chapter 15 of the Oconee UFSAR that were submitted for staff review. lists the meeting participants. Enclosure 2 is the handout provided by DEC.
ORIGINAL SIGNED BY:
David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosures:
- 1. Meeting Attendees
- 2. DEC Handout cc w/encls: See next page Hard copy w/enclosures E-Mail w/enclosure 1 CYLiang EWeiss C PE tliU SCollins/FMiraglia JJohnson, RI1 PUBLIC BBoger MScott, RII PD 11-2 Rdg.
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GA RE UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-001 February 6, 1998 LICENSEE:
Duke Energy Corporation FACILITIES:
Oconee Nuclear Station, Units 1 and 2
SUBJECT:
MEETING
SUMMARY
- MEETING OF JANUARY 27, 1998, REGARDING CRITICAL HEAT FLUX AND UPDATED FINAL SAFETY ANALYSIS REPORT (UFSAR) CHAPTER 15 TOPICAL REPORTS (TAC NOS. M96728, M88660, M98661, M98662, M99349, M99350, AND M99351)
REFERENCES:
(1) Meeting Notice by D.E. LaBarge, January 12, 1998 (2) Letter, M. S. Tuckman to NRC, "Oconee Nuclear Station Transition to Framatome MkB1 1 Fuel," dated December 2, 1997 (3) Letter, M. S. Tuckman to NRC, "Use of BWU-Z Critical Heat Flux Correlation for Mark-B11 Fuel," dated April 22, 1997 (4) Letter, M. S. Tuckman to NRC, "Topical Report DPC-NE-3000P, Revision 2," dated December 23, 1997 (5) Letter, M. S. Tuckman to NRC, "UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-P," dated July 30, 1997 On January 27, 1998, the staff met with Duke Energy Corporation (DEC) personnel to discuss the contents of DEC's topical reports dealing with conversion to Mark B-11 fuel at Oconee and changes to Chapter 15 of the Oconee UFSAR that were submitted for staff review. lists the meeting participants. Enclosure 2 is the handout provided by DEC.
David E. LaBarge, Senior Project Manager Project Directorate 11-2 Division of Reactor Projects - 1/Il Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287
Enclosures:
- 1. Meeting Attendees
- 2. DEC Handout cc w/encls: See next page
Oconee Nuclear Station cc:
Mr. Paul R. Newton Mr. Ed Burchfield Duke Energy Corporation, PB05E Compliance 422 South Church Street Duke Energy Corporation Charlotte, North Carolina 28242 Oconee Nuclear Site P. 0. Box 1439 J. Michael McGarry, Ill, Esquire Seneca, South Carolina 29679 Winston and Strawn 1400 L Street, NW.
Ms. Karen E. Long Washington, DC 20005 Assistant Attorney General North Carolina Department of Mr. Robert B. Borsum Justice Framatome Technologies P. 0. Box 629 Suite 525 Raleigh, North Carolina 27602 1700 Rockville Pike Rockville, Maryland 20852 L. A. Keller Manager - Nuclear Regulatory Manager, LIS Licensing NUS Corporation Duke Energy Corporation 2650 McCormick Drive, 3rd Floor 526 South Church Street Clearwater, Florida 34619-1035 Charlotte, North Carolina 28242-0001 Senior Resident Inspector Mr. Richard M. Fry, Director U.S. Nuclear Regulatory Commission Division of Radiation Protection 7812B Rochester Highway North Carolina Department of Seneca, South Carolina 29672 Environment, Health, and Natural Resources Regional Administrator, Region II 3825 Barrett Drive U. S. Nuclear Regulatory Commission Raleigh, North Carolina 27609-7721 Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Mr. William R. McCollum Atlanta, Georgia 30303 Vice President, Oconee Site Duke Energy Corporation Max Batavia, Chief P. 0. Box 1439 Bureau of Radiological Health Seneca, South Carolina 27679 South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 County Supervisor of Oconee County WaShalla, South Carolina 29621
LIST OF PARTICIPANTS MEETING WITH DUKE ENERGY CORPORATION JANUARY 27, 1998 NAME AFFILIATION Anthony Attard NRC/NRR/Reactor Systems Branch Herb Berkow NRC/NRR/Project Directorate 11-2 Kenneth Canady Duke Energy Corporation' Richard Clark Duke Energy Corporation Ron Gribble Duke Energy Corporation Tai Huang NRC/NRR/Reactor Systems Branch Walton Jensen NRC/NRR/Reactor Systems Branch Lee Keller Duke Energy Corporation Laurence Kopp NRC/NRR/Reactor Systems Branch David LaBarge NRC/NRR/Project Directorate 11-2 Lambros Lois NRC/NRR/Reactor Systems Branch Chu-Yu Liang NRC/NRR/Reactor Systems Branch Frank Orr NRC/NRR/Reactor Systems Branch Frank Rinaldi NRC/NRR/Project Directorate 11-2 Robert Saint Clair Duke Energy Corporation Gregg Swindlehurst Duke Energy Corporation Peter Tam NRC/NRR/Project Directorate 11-2 Eric Weiss NRC/NRR/Reactor Systems Branch Enclosure I
Oconee Transition to MkB 11
+ FCF MkB11: New 15x15 product: mixing vanes,.416"OD
" First full batch 03C19 (fuel delivery 2/2000)
+ Cycle design begins 11/98.
- Four lead assemblies currently in 1st cycle 02C 16
" End of 1st Cycle PIE scheduled for May '98 R
Duke 4Power.
A Duke Energy Company
Previous MkB 11 NRC Interactions
- January 31, 1995 Duke and Framatome met with NRC to present the MkB1 1 development program and lead assembly analysis and irradiation plans.
As part of this presentation Framatome discussed a MkB1 1 mixing vane grid design change and an intent to use the BWU correlation on the MkB1 1 LTAs.
- August 15, 1995 Duke met with NRC and presented the status of supporting topicals and the then-current status of the MkB1 1 fuel assembly development program.
- May 1996 four lead MkB1 1 fuel assemblies began their irradiation in Oconee 2 cycle
- 16. This cycle will shut down in February of 1998, and the first cycle of post irradiation-examination will be conducted during this outage.
A Duke 4# Power.
A Duke Energy Company
OCONEE Mk-B111 DESIGN SCHEDULE 477 EFPD 470 EFPD 484 EFPD 490 EFPD 470 EFPD 490 EFPD
!:M C1 1L 1 :11 ICYCLE 11 Ci ~E ii 450 EFPD 470 EFPD 500 EFPD 507 EFPD 490 EFPD 500 EFPD C ~1~EI4 iiikUCVCLE 1$cycLE C Lk 11j~
t CYCLE18 I7ViE1U ii V
C>
437 EFPD 445 EFPD 480 EFPD 490 EFP0 495 EFPD 479 EFPD HYLEI
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CYLE
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1994 1995 1996 1997 1998 1999 2000 2001 2002 ft Duke 4Power.A A Duke Energy Company
I B11 FUEL ASSEMBLY Leaf Holddown I
Spring Floating Inconel Upper End Grid Quick Disconnect Instrument Tube-.
Flow Mixing Reduced Grids Diameter Fuel Rod Optimized Bypass Flow Guide Tubes Intermediate Cross Section Zircaloy Spacer Grids Inconel Lower o
.~-
End Grid FIT li 10 0
0 0
Debris Resistant Lower End Plug Anti-Straddle Lower End Fitting Reconstitutable Bottom View
\\-Lower End Fitting
Oconee MkB 11 Design Comparison with Current Fuel Design Feature Current Mk-B10L fuel assembly design Mk-B11 Fuel assembly dry weight, lbs 1563 1480 Top nozzle design Quick disconnect UEF Quick disconnect UEF Number of spacer grids 8
8 Type of spacer grids non-mixing vane mixing vane CRGT ID, inches 0.498 0.498 IT ID, inches 0.441 0.441 Fuel rod cladding OD, inches 0.430 0.416 Cladding material low tin Zircaloy-4 low tin Zircaloy-4 Fuel rod pre-pressure, psig proprietary unchanged Pellet stack height, inches 142.29 143.05 M Duke ow Power.
A Duke Energy Company
Oconee Topical Status Topical Title Submittal SER Need Date
- 1. FCF MkB1 1 Fuel Assembly Design Topical (BAW-1 0229P) 9/30/97 12/98
- 2. FCF BWU Critical Heat Flux Correlations Addendum 1 9/96 1/98 (BAW-1 01 99P)
- 3. Duke Thermal-Hydraulic Statistical Core Design 4/22/97 10/98 Methodology, Addendum D (DPC-NE-2005)
- 5. Duke Thermal Hydraulic Transient Analysis 12/97 10/98 Methodology Revision (DPC-NE-3000-P, Rev 2)
A Duke 4F' Power.
A Duke Energy Company
CHF and TH Methods o FCF BWU CHF Correlation Addendum 1 (BAW-10199P) uses same "universal" (polynomial) form.
New data on MkB 11 (.416"OD mixing vane fuel) used to develop a performance factor (multiplier).
- Duke SCD Topical Addendum D (DPC-NE-2005) is identical in approach to previous addenda.
Explicit propagation of statepoints with VIPRE-01.
A Duke 4 #Power.
A Duke Energy Company
LTA Core Locations Oconee 2 Cycle 16 Oconee 2 Cycle 17 Oconee 2 Cycle 18 1 2 3
4 5
6 7
8 9
10 11 12 13 14 15 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 B -
-B
-B C
C C
o -
D D -
E
-E E-F--
F--
F F
G--
GG M
M N -
N-N O
O 0
RR R
LTA Cycle Average Max. Pin = 1.26 LTA Cycle Average Max. Pin = 0.65 LTA Cycle Average Max. Pin = 0.99
& Duke 4M Power.
A Duke Energy Company
LTA 3-Cycle Exposure 1.6 1.3 CL
- 0.
- 1
- 0 0 0
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EFPD 0u-2C16Co re 02C1 6LTA-.0-2C1 7LTA - -A-0O2C1 8LTA
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A Duke Energy Company
02EOC16 BIl PIE Scope Inspection
- of FAs 0
Full length visuals 6
Fuel rod oxide/diameter 3
Fuel assembly growth/bow 6
Fuel assembly water channel 2
Guide tube oxide/width/plug gage 1
Spacer grid position 2
Duke 4W Power.
A Duke Energy Company
Nuclear Design Changes
- FCF Mark B-l l fuel design.
- Use of SIMULATE-3K for Rod Ejection Accident (REA) analysis.
& Duke C&
Power.
A Duke Energy Company
Mark B-I1 Design Model
- No changes from currently approved models except input parameters to describe B-I 1 fuel and utilization of SIMULATE 3K for REA analysis as described in DPC NE-3005P.
- Uncertainty factors developed and approved in DPC-NE-1004A for B&W 177-assembly plants will be utilized.
& Duke aftPower.
A Duke Energy Company
Application of Methods to B-i1
- No new isotopes introduced by B-11.
- Utilizes the same burnable poisons at B-10.
- Previous validation of Mark-BW fuel at MNS/CNS produced no change in uncertainties from OFA fuel.
- Criteria for zero power physics tests, power escalation tests, reactivity anomalies, and power distributions will remain unchanged.
& Duke 4& Power.
A Duke Energy Company
DPC-NE-3005-P: UFSAR Chapter 15 Transient Analysis Methodology
- Submitted for NRC review 7/30/97 (review is underway)
- Requesting review complete by 10/98
- Needed for Mk-B 11 fuel assembly design (03C 19)
- Needed for ITS conversion (analytical bases for T. S.)
- Same approach as NRC-approved McGuire/Catawba topical reports
- Modem methods to replace 1970s vintage B&W analyses
- Minor revision to DPC-NE-3000 submitted 12/23/97
- Modeling related to the Mk-B 11 fuel assembly
- Modeling related to the BWU-Z CHF correlation
- Minor methodology/model changes
DPC-NE-3005-P: UFSAR Chapter 15 Transient Analysis Methodology Philosophical Approach
- Upgrade Chapter 15 analyses to be more modem (Duke already licensed McGuire/Catawba Ch. 15 reanalyses)
- Modem industry standard computer codes
- Most codes and models already reviewed and approved by the NRC
- Meaningful/limiting scenarios
- Modem acceptance criteria
- Consistent with technical specifications
- Conservative initial conditions
- Conservative boundary conditions
- Careful selection of single failures Careful modeling of control systems and operator actions)
High level of detail for NRC review First application of SIMULATE-3K for licensing First application of RETRAN lD kinetics in a PWR
- Among the first applications of RETRAN-3D (limited scope)
- Scope and content discussed with NRC on 8/15/95
DPC-NE-3005-P: UFSAR Chapter 15 Transient Analysis Methodology Comparison of Present and Future UFSAR Chapter 15 Present Future 15.2 Startup Accident Same (RCPs per T. S.)
15.3 Rod Withdrawal Accident at Rated Power Other power levels also 15.4 Moderator Dilution Accident Modem scenarios 15.5 Cold Water Accident One RCP per T. S.
(RCP startup) 15.6 Loss of Coolant Flow Accident All RCP combinations (locked rotor also) 15.7 Control Rod Misalignment Accidents Also statically (Dropped rod) misaligned rod 15.8 Loss of Electric Load Accidents Turbine trip 15.9 Steam Generator Tube Rupture Realistic scenario 15.12 Rod Ejection Accident Same (3D) 15.13 Steam Line Break Same (FW isolation)
Also small SLB misalined ro
DPC-NE-3005-P: UFSAR Chapter 15 Transient Analysis Methodology Table of Contents 1.0 Introduction and Summary 2.0 Simulation Codes and Models 3.0 Safety Analysis Physics Parameters 4.0 Safety Analysis Setpoint Methodology 5.0 Startup Accident 6.0 Rod Withdrawal at Power 7.0 Moderator Dilution Accident 8.0 Cold Water Accident 9.0 Loss of Coolant Flow 10.0 Locked Rotor 11.0 Control Rod Misalignment Accident 12.0 Turbine Trip 13.0 Steam Generator Tube Rupture 14.0 Rod Ejection 15.0 Steam Line Break 16.0 Small Steam Line Break
Summary:
MkB 11 Transition
- NRC support of FCF's CHF correlation and fuel assembly mechanical design topicals.
- NRC support of Duke's topical report review schedules
+ NRC Support of Duke's planned submittals of reload reports and FSAR markups for the first batch of each unit.
A Duke 4W Power.
A Duke Energy Company