ML15264A591
| ML15264A591 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/22/1989 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| TAC-69377, TAC-69378, TAC-69379, NUDOCS 8903290434 | |
| Download: ML15264A591 (5) | |
Text
March 22, 1989 Docket Nos.:
50-269, 50-270, and 50-287 Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Tucker:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING TOPICAL REPORT DPC-NE-2003, "CORE THERMAL-HYDRAULIC METHODOLOGY USING VIPRE-01" (TACS 69377, 69378, AND 69379)
The NRC is reviewing your topical report DPC-NE-2003, "Core Thermal-Hydraulic Methodology Using VIPRE-01" for Oconee Nuclear Station, Units 1, 2, and 3 submitted August 31, 1988. We find that further information, as indicated in the enclosure, is required to complete our review.
Your response to the enclosed questions is requested within 60 days of the date of this letter.
If you have any questions regarding this matter, I may be contacted at (301) 492-1442.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Orb1fita~l Sig ned By,:
Darl S. Hood, Acting Project Manager Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosure:
See next page DISTRIBUTION:
Docket File NRC PDR Local PDR PDII-3 Reading G. Lainas 14-E-4 E. Adensam 14-H-3 D. Matthews 14-H-25 M. Rood 14-H-25 D. Hood 14-H-25 0 F161d h
er S. Brewer 14-H-25 03/20/89 3/ 89 OGC (For inform. Only) 15-B-18 u'1/
11 E. Jordan MNBB-3302 PDhIP 3
B. Grimes 9-A-2 DHood:l
,_DMatthews Y. Hsii 8-E-23 031i,/89 03/Z189 W. Hodges 8-E-23 ACRS (10)
P-315 Oconee Plant File 903290434 890322 PDR ADOCK 05000269 1
M P
PIP D
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CIO March 22, 1989 Docket Nos.: 50-269, 50-270, and 50-287 Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Tucker:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING TOPICAL REPORT DPC-NE-2003, "CORE THERMAL-HYDRAULIC METHODOLOGY USING VIPRE-01" (TACS 69377, 69378, AND 69379)
The NRC is reviewing your topical report DPC-NE-2003, "Core Thermal-Hydraulic Methodology Using VIPRE-01" for Oconee Nuclear Station, Units 1, 2, and 3 submitted August 31, 1988. We find that further information, as indicated in the enclosure, is required to complete our review.
Your response to the enclosed questions is requested within 60 days of the date of this letter. If you have any questions regarding this matter, I may be contacted at (301) 492-1442.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely, Darl S. Ho
, Acting Project Manager Project Directorate 11-3 Division of Reactor Projects -
I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc w/enclosure:
See next page
Mr. H. B. Tucker Oconee Nuclear Station Duke Power Company Units Nos. 1, 2 and 3 cc:
Mr. A. V. Carr, Esq.
Mr. Paul Guill Duke Power Company Duke Power Company P. 0. Box 33189 Post Office Box 33189 422 South Church Street 422 South Church Street Charlotte, North Carolina 28242 Charlotte, North Carolina 28242 J. Michael McGarry, III, Esq.
Bishop, Liberman, Cook, Purcell & Reynolds Mr. Alan R. Herdt, Chief 1400 L Street, N.W.
Project Branch #3 Washington, D.C. 20005 U.S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900
'Mr. Robert B. Borsum Atlanta, Georgia 30323 Babcock & Wilcox Nuclear Power Generation Division Suite 525 1700 Rockville Pike Rockville, Maryland 20852 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 Senior Resident Inspector U.S. Nuclear Regulatory Commission Route 2, Box 610 Seneca, South Carolina 29678 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION ON DPC-NE-2003 CORE THERMAL-HYDRAULIC METHODOLOGY USING VIPRE-01
- 1. Section 4.0 of the topical report describes the nodalization sensitivity study performed to demonstrate that the simplified core models to be used for licensing calculations are conservative relative to the more detailed core model.
(a) Was the study performed with the same thermal-hydraulic models and/or correlations to be used for licensing calculation?
If not, identify those models and correlations which are not the same.
(b) Would the use of different correlations and/or models lead to different nodalization sensitivity results? Demonstrate the conservatism of the simplified core model with the final T-H models for licensing application.
(c) It is understood that only the BWC correlation will be used for critical heat flux calculation. What do you intend to do if the core conditions are outside the ranges of applicability of the BWC correlation?
- 2. Section 5.5 states that the spacer grid form loss coefficients for the individual subchannels are determined analytically by the vendor from the overall grid form loss coefficient. Provide sufficient detail of the analytical determination of the individual subchannel form loss coefficients. Are these values for single or two phase flow?
- 3. Section 5.8.2 discusses the determination of the value (Proprietary) of the turbulent mixing coefficient to be used for all Oconee Nuclear Station core thermal-hydraulic analyses based on vendor prediction of the mixing test results.
Explain the process of vendor prediction of mixing test results andmixing coefficient, and explain how this correlates to the Oconee computation.
- 4. Section 5.8.2 also discusses the selection of the turbulent momentum factor (FTM) from the sensitivity study performed with the FTM of 0.0, 0.8 and 1.0.
(a) Justfy the selected value which is not the most conservative value as shown in Table 5-4.
(b) Explain how and why only the three values of FTM were selected for the sensitivity study.
- 5. Section 5.10 states that a new routine is added to the VIPRE-01 code to generate axial power shapes with inlet, symmetric, or outlet peaks.
Provide sufficient details of this routine.
- 6. In Section 6.6, the inputs for the fuel gap conduction model are selected through a sensitivity study performed by varying three input parameters, i.e., pellet-cladding gap size, gas composition and pellet radial power frofile. Explain how this study enables the selection of conservative values of the eight parameters for input to the conduction model.
- 7. Section 6.6 also indicates that a sensitivity study shows very little difference in the pump coastdown results with regard to the choice of nucleate boiling correlation. Provide more detail of the sensitivity study performed to select the nucleate boiling correlation.