ML20147C970
| ML20147C970 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 01/14/1988 |
| From: | Nauman D SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8801200022 | |
| Download: ML20147C970 (2) | |
Text
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j th Dectric & Gas Company n
a Co4umtwa. SC 29218 Nuclear Operatons (803) 748-3513 SCE&G j
-m January 14, 1988 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 Cycle 5 Reload Using PH0ENIX-P Gentlemen:
The refueling shutdown at the end of Virgil C. Summer Unit 1/ Cycle 4 is planned to commence during the month of October, 1988.
This letter is to advise you of South Carolina Electric & Gas Company's (SCE&G) plans to reference the Westinghouse PH0ENIX-P computer code, described below, in support of the upcoming Cycle 5 reload design.
The PHOENIX-P Topical. WCAP-11596, was submitted to the Staff in early December 1987 for their review and approval. The topical submittal is consistent with the Staff's scheduling guidance that reload analyses based on models and methods that are not yet approved by the Staff be submitted at least six months prior to the date that a license amendment is required to authorize restart.
The PH0ENIX-P computer code is being introduced in core design applications in order to improve core physics prediction accuracy for all Westinghouse Pressurized Water Reactor (PWR) fuel products.
The PH0ENIX-P computer code includes a new library based on ENDF/8-V, automation and capabilities necessary for the generation of physics parameters for PWR dimensional codes.
The PH0ENIX-P computer code has been benchmarked extensively against critical experiments and core follow data from operating PWR reactors.
The Westinghouse qualification data included detailed verification of the PHOENIX-P library and methodology against integrsi parameters available from critical experiments.
Comparison of global reactivity predictions were made against the Strawbridge and Barry criticals, the KRITZ high-temperature criticals, and the Babcock & Wilcox spatial criticals.
Local reactivity and power distribution predictions were compared against directly measured rod power from the Babcock & Wilcox critical experiments.
Isotopics measurements from the Saxton and Yankee cores were compared against the PH0ENIX-P predictions to assess the code's accuracy in predicting buildup and depletion of higher-order isotopes as a function of burnup.
Excellent agreement in all compared parameters confirms the validity of the cross section library and methodology employed by the PHOENIX-P computer program.
'8801200022 880114
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Nuclear Regulatory Commission Cycle 5 Reload Using PHOENIX-P t
January 14, 1988 Page 2 l
PHOENIX-P based cross sections were also used by Westinghouse in the Advanced Nodal Code (ANC) core models to produce physics predictions for comparison against reliable measured core data.
Several reactor cores were included in the data base, covering a diversified range of product features, core sizes, and fuel management schemes.
Presented were comparisons of measured versus predicted physics parameters obtained from the hot zero power physics tests and core follow analysis.
The comparisons included hot zero power critical boron concentration, isothermal temperature coefficient, control bank worth, core follow boron concentration, and core follow assembly power distribution.
For all parameters compared, the agreement between PH0ENIX-P/ANC predictions and measurements was quite good, with the mean differences close to zero and very small standard deviations.
The qualification data presented in WCAP-11596 provide the basis for the implementation of the PHOENIX-P computer program in generating physics parameters for dimensional design codes.
The new methodology will confirm that the conclusions given in the currently approved reload methodology (WCAP-9272-P-A) are valid when the PHOENIX-P computer code is applied to the Virgil C. Summer Cycle 5 core design calculations.
In summary, pending NRC approval of the PH0ENIX-P computer code topical.
WCAP-11596, for which an expedited NRC review and approval has been requested by March 1988, the Cycle 5 reload design will proceed using the PHOENIX-P computer code under the provisions of 10CFR50.59.
If you have any questions, please contact us at your convenience.
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- 0. W. Dixon, Jr./T. C. Nichols, Jr.
X. E. Beale E. C. Roberts K. E. Nodland W. A. Williams, Jr.
J. C. Snelson Group Managers G. O. Percival j
J. N. Grace R. L. Prevatte
- 0. S. Bradham J. B. Knotts, Jr.
O. R. Moore NPCF C. A. Price File C. L. Ligon (NSRC)
R. M. Campbell, Jr.
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