ML15244A754
| ML15244A754 | |
| Person / Time | |
|---|---|
| Site: | Oconee, Mcguire, Catawba, McGuire  |
| Issue date: | 06/25/1992 |
| From: | Tim Reed Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9207020018 | |
| Download: ML15244A754 (13) | |
Text
June 25, 1992 Docket Nos. 50-369 and 50-370 50-413 and 50-414 60-269, 50-270, and 50-287 LICENSEE:
Duke Power Company FACILITY:
McGuire, Catawba, and Oconee Nuclear Stations
SUBJECT:
SUMMARY
OF MEETING WITH DUKE POWER COMPANY ON TOPICAL REPORT REVIEW SCHEDULES On June 9, 1992, the NRC staff met with representatives of Duke Power Company (DPC) to discuss the schedule for NRC review of DPC topical reports that are planned to be submitted in the next several years. Meeting attendees are listed in Enclosure 1. The handouts distributed during the meeting are provided as Enclosure 2.
Each of the topical reports listed in DPC's April 10, 1992, letter were discussed for relative priority. The staff will incorporate this input into the planned scheduling of these activities. DPC-NE-3004 is the topical with the most immediate priority since it is required to support the McGuire Unit 1 steam generator changeout in September 1995 (early 1994 submittal date). The staff is exploring an alternative audit/review process to review the use of TACO-3 rather than the traditional topical report review. DPC committed to update their April 10, 1992, letter to incorporate dates as to when the subject topicals will be needed to support DPC licensing activities. DPC also discussed the current status and preliminary data taken from their ongoing reconstituted fuel geometry critical heat flux tests.
/s/
Timothy A. Reed, Project Manager Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Enclosures:
- 1. List of Attendees DISTRIBUTION
- 2. DPC Handouts SEE NEXT PAGE M
cc w/enclosures:
See next page OFC PDII-3 PD I-3PM D:
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/A/92 OFFICIAL RECORD COPY Document Name:
DPCMTG.SUM 9207020018 920625 PDR ADOCK 05000269 P
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 June 25, 1992 Docket Nos. 50-369 and 50-370 50-413 and 50-414 60-269, 50-270, and 50-287 LICENSEE:
Duke Power Company FACILITY:
McGuire, Catawba, and Oconee Nuclear Stations
SUBJECT:
SUMMARY
OF MEETING WITH DUKE POWER COMPANY ON TOPICAL REPORT REVIEW SCHEDULES On June 9, 1992, the NRC staff met with representatives of Duke Power Company (DPC) to discuss the.schedule for NRC review of DPC topical reports that are planned to be submitted in the next several years. Meeting attendees are listed in Enclosure 1. The handouts distributed during the meeting are provided as Enclosure 2.
Each of the topical reports listed in DPC's April 10, 1992, letter were discussed for relative priority. The staff will incorporate this input into the planned scheduling of these activities. DPC-NE-3004 is the topical with the most immediate priority since it is required to support the McGuire Unit 1 steam generator changeout in September 1995 (early 1994 submittal date).
The staff is exploring an alternative audit/review process to review the use of TACO-3 rather than the traditional topical report review. DPC committed to update their April 10, 1992, letter to incorporate dates as to when the subject topicals will 'be needed to support DPC licensing activities. DPC also discussed the current status and preliminary data taken from their ongoing reconstituted fuel geometry criti heat flux tests.
Timothy A. Reed, Project Manager Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Enclosures:
- 1. List of Attendees
- 2. DPC Handouts cc w/enclosures:
See next page
Duke Power Company Catawba Nuclear-Station McGuire Nuclear Station Oconee Nuclear Station cc:
Mr. R. C. Futrell Mr. Alan R. Herdt, Chief Regulatory Compliance Manager Project Branch f3 Duke Power Company U.S. Nuclear Regulatory Commission 4800 Concord Road 101 Marietta Street, NW, Suite 2900 York, South Carolina 29745 Atlanta, Georgia 30323 Mr. A.V. Carr, Esq.
North Carolina Electric Membership Duke Power Company Corp.
422 South Church Street P.O. Box 27306 Charlotte, North Carolina 28242-0001 Raleigh, North Carolina 27611 J. Michael McGarry, 111, Esq.
Saluda River Electric Cooperative, Winston and Strawn Inc.
1400 L Street, N.W.
P.O. Box 929 Washington, D. C. 20005 Laurens, South Carolina 29360 North Carolina MPA-1 Senior Resident Inspector Suite 600 Route 2, Box 179N P.O. Box 29513 York, South Carolina 29745 Raleigh, North Carolina 27626-0513 Mr. Frank Modrak U.S. Nuclear Regulatory Commission Project Manager, Mid-South Area 101 Marietta Street, NW, Suite 2900 ESSD Projects Atlanta, Georgia 30323 Westinghouse Electric Corp.
MNC West Tower - Bay 241 Mr. Heyward G. Shealy, Chief P.O. Box 355 Bureau of Radiological Health Pittsburgh, Pennsylvania 15230 South.Carolina Dept. of Health and Environmental Control County Manager of York County 2600 Bull Street York County Courthouse Columbia, South Carolina 29201 York, South Carolina 29745 Ms. Karen E. Long Richard P. Wilson, Esq.
Assistant Attorney General Assistant Attorney General North Carolina Dept. of Justice S.C. Attorney General's Office P.O. Box 629 P.O. Box 11549 Raleigh, North Carolina 27602 Columbia, South Carolina 29211 Piedmont Municipal Power Agency Licensing 121 Village Drive Duke Power Company Greer, South Carolina 29651 P.O. Box 1007 Charlotte, North Carolina 28201-1007
Duke Power Company Catawba Nuclear Station McGuire Nuclear Station Oconee Nuclear Station cc:
Dr. John M. Barry Mr. M. E. Patrick Mecklenburg County Compiance Dept. of Environmental Protection Duke Power Company 700 N. Tryon Street Oconee Nuclear Site Charlotte, North Carolina 28202 P.O. Box 1439 Seneca, South Carolina 29679 County Manager of Mecklenburg County 720 East Fourth Street Mr. Robert B. Borsum Charlotte, North Carolina 28202 Babcock t Wilcox Nuclear Power Division Mr. R. 0. Sharpe Suite 525 Compliance 1700 Rockville Pike Duke Power Company Rockville, Maryland 20852 McGuire Nuclear Site 12700 Hagers Ferry Road Manager, LIS Huntersville, North Carolina 28078-8985 NUS Corporation Washington, DC 20005 2650 McCormick Drive, 3rd Floor Senir Rsidnt IspetorClearwater, Florida 34619-1035 Senior Resident Inspector c/o U.S. Nuclear Regulatory Commission Senior Resident Inspector 12700 Hagers Ferry Road U. S. Nuclear Regulatory Commission Huntersville, North Carolina 28078 Route 2, Box 610 Seneca, South Carolina 29678 Mr. Dayne H. Brown, Director Department of Environmental, Mr. M. S. Tucknan Health and Natural Resources Vice President, Catawba Site Division of Radiation Protection Duke Power Company P.O. Box 27687 4800 Concord Road Raleigh, North Carolina 27611-7687 York.South Carolina 29745 Office of Intergovernmental Relations Mr. T. C. McMeekin 116 West Jones Street Vice President, McGuire Site Raleigh, North Carolina 27603 Duke Power Company 12700 Hagers Ferry Road County Supervisor of Oconee County Huntersville, North Carolina 28078-8985 Walhalla, South Carolina 29621 Mr. J. W. Hampton Vice President, Oconee Site Duke Power Company P. 0. Box 1439 Seneca, South Carolina 29679
June 25, 1992 MEETING
SUMMARY
DATED:
DISTRIBUTION:
Docket File NRC/LOCAL PDRs PDII-3 Reading File McGuire Reading Catawba Reading Oconee Reading TReed RMartin LWiens DMatthews LBerry TMurley/FMiraglia JPartlow SVarga GLainas OGC EJordan RJones SLWu LPhillips ACRS (10)
JWechselberger, EDO LReyes, RII
ENCLOSURE 1 LIST OF ATTENDEES NAME ORGANIZATION B. JONES NRC/REACTOR SYSTEMS T. REED NRC/McGUIRE PROJECT MANAGER L. WIENS NRC/OCONEE PROJECT MANAGER R. MARTIN NRC/CATAWBA PROJECT MANAGER S. L. WU NRC/REACTOR SYSTEMS L. PHILLIPS NRC/REACTOR SYSTEMS R. CRIBBLE DPC S. GEWEHR DPC K. CANADY DPC J. ABBOT DPC
AGENDA DUKE/NRC MEETING DUKE TOPICAL REPORTS
- 1.
Topical Report Submittal Schedules (Canady)
- 2.
Oconee, McGuire, Catawba TACO3 Fuel Mechanical Methodology Report (Abbott)
- 3.
Duke Power Co. T/H SCD Methodology Topical Report (Abbott)
- 4.
Status of Reconstituted Geometry CHF Tests (Gribble)
- 5.
NRC's Review Schedule (Canady)
DUKE POWER TOPICAL REPORTS Submittal Number le Date Comments DPC-NE-3003 Oconee Nuclear Station - Mass 1/1/93 and Energy Release and Containment Response Methodology DPC-NE-3004 McGuire/Catawba Nuclear 12/1/93 Stations - Mass and Energy Release and Containment Response Methodology DPC-NE-3005 Oconee Nuclear Station - FSAR 12/1/93 Chapter 15 System Transient Analysis Methodology DPC-NE-2005 Duke Power Company 10/1/92 Oconee/McGuire/
Thermal/Hydraulic Statistical Catawba & other Core Design Methodology PWR plants using mixing vane fuel DPC-NE-2006 DCHF-3 Correlation for 10/1/93 Predicting Critical Heat Flux in Mixing Vane Grid Fuel Assemblies DPC-NE-2008 Oconee, McGuire, and Catawba 12/1/92 Nuclear stations (TACO3) Fuel Rod Mechanical Methodology DPC-NE-2007 Oconee, McGuire, and Catawba 8/1/92 Justification of fuel Nuclear Stations Fuel rod vacancies Reconstitution Analysis Methodology
RELOAD MECHANICAL ANALYSES BACKGROUND
- Currently use TACO2 with CROV 6.3.
- Mechanical Analyses evaluated are:
- Pin Pressure
- Linear Heat Rate to Melt
- Creep-Collapse
- Cladding Strain
- ECCS Analysis Interface Criteria
- Current Burnup Limits for Oconee using TACO2 are 48000 to 52500 MWD/MTU depending on fuel type.
- Duke is beginning to bump those limits.
- B&W does not support TACO2 for their new fuel (MK-B9).
- Especially important for ECCS Analysis Interface.
- As a consequence of the last two bullets, Duke Power will transition to TACO3.
FUEL MECHANICAL RELOAD ANALYSIS METHODOLOGY FOR MARK-BW FUEL DPC-NE-2001-A SEPTEMBER 1987 REVISION 1 JANUARY 1990 APPROVED OCTOBER 1990 DUKE POWER COMPANY
-DESIGN ENGINEERING DEPARTMENT MECHANICAL/NUCLEAR DIVISION NUCLEAR ENGINEERING MECHANICAL AND THERMAL HYDRAULICS ANALYSIS
-3 initial conditions. We thus consider that the licensee's use of TACO2 to determine ECCS initial conditions is acceptable for Mark-BW fuel in McGuire and Catawba reload applications.
3.0 CONCLUSION
S We have reviewed the licensee's submittal concerning the use of methodology described in DPC-NE-2001, Rev. 1, for Mark-BW fuel reloads in McGuire and Catawba. Based on the use of previously approved analytical methods and the approved TACO2 and CROV codes, and the similarity between Mark-BW and Mark B and Mark C fuel, we conclude that the DPC-NE-2001, Rev. 1, report is acceptable for Mark-BW fuel licensing applications in McGuire and Catawba.
We also determine that there are no unreviewed safety questions and no need of Technical Specification changes for McGuire and Catawba.
This approval is limited to the use of the TACO2 code. If, in the future, the licensee decides to use the newer.approved code, TACO3, the staff requires the licensee to demonstrate its proficiency in using the TACO3 code.
Principal Contributors:
Shih-Liang Wu,SRXB:DST S. S. Kirslis, PDII-3:DRPI/II K. N. Jabbour, PDII-3:DRPI/II T. A. Reed, PDII-3:NRR:DRPI/II Dated:
October 15, 1990
OCONEE, McGUIRE, AND CATAWBA NUCLEAR STATIONS (TACO3) FUEL ROD MECHANICAL METHODOLOGY (DPC-NE-2008)
DUKE PLAN:
- Per McGuire/Catawba Reload Analysis Methodology for MARK-BW Fuel SER (DPC-NE-2001-A), Duke Power proposes a report demonstrating proficiency in the use of TACO3 in lieu of submitting a topical report.
- Report will include all fuel mechanical analyses requiring the use of TACO3 and is not intended for formal review.
- Duke Power will use the approved B&W TACO3 Methodology.
- When LASP gets NRC approval in April 93, Duke Power will use the approved methodology for pin pressure analyses.
- When CROV 8.0 gets NRC approval in May 93, Duke Power will use the approved code for creep-collapse analyses.
- Duke Power does not intend to make and additional submittal for the use of CROV 8.0.
- Submittal Date: 12/1/92 QUESTIONS:
- What does the NRC consider sufficient for demonstrating proficiency?
TACO3 REPORT OUTLINE
- Report will be written like a topical report but is not intended for review as a topical report.
- Report will be broken into 5 major sections with each section covering a TACO3 Analysis.
- Pin Pressure
- Linear Heat Rate to Melt
- Creep-Collapse
- Cladding Strain
- ECCS Analysis Interface Criteria
- Duke Power will use the report internally as the basis for our generic analyses.
- Each section will discuss nominal inputs and sensitivities.
- For those analyses requiring the input of uncertainties (e.g. pin pressure analysis), the uncertainties will be discussed as will the sensitivity of the final result to those uncertainties.
- Each section will discuss the differences in input between TACO2 and TACO3.
- Finally, each section will essentially outline a methodology for performing the corresponding analysis.
- An example of what typical results might look like for the pin pressure and LHRTM analyses are included on the next pages.