ML20247D252

Forwards MICBURN-3/CASMO-3/TABLES-3/SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 Through 13. Models Used to Calculate Engine Values & Detector Response Data at Numerous steady-state Exposure Points

ML20247D252
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/27/1989
From:	Capstick R VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247D253	List: ML20247D252 ML20247D299
References
BVY-89-29, NUDOCS 8903310009
Download: ML20247D252 (2)

Text

_ _ _ _

VERMONT YANKEE

• NUCLEAR POWER CORPORATION

.- s RD 5. Bex 169, Ferry Road. B attleboro, VT 05301 REPLY TO Y ENGINEERING OFFICE 580 MAIN STREET BOGoN, MA 0m0 March 27, 1989 e 83 77u7u BVY 89-29 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

References:

(a) License No. DPR-28 (Docket No. 50-271)

(b) Letter, YAEC to USNRC, FVY 88-026, dated April 11, 1988 (c) Letter, YAEC to USNRC, FVY 88-75, dated September 12, 1988 (d) Letter, VYNPC to USNRC, FVY 88-89, dated October 13, 1988

Subject:

Submitta1 of, "MICBURN-3/CASM0-3/ TABLES-3/ SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 through 13," Report

Dear Sir:

In accordance with the schedule provided in our letter of October 13, 1988 [ Reference (d)}; Vermont Yankee herewith submits the subject report for your review and approval. This report benchmarks the MICBURN-3/CASMO-3/ TABLES-3/ SIMULATE-3 code package against several recent cycles of Vermont Yankee operating data. The models are used to calculate eigenvalues and detector response data at numerous steady-state exposure points. These calculations are compared to plant measurements; i.e.,

criticality and Traversing Incore Probe (TIP) data. The consistency and accuracy of the comparisons validate these codes for reload design, steady-state licensing, and plant support applications.

The generic topical CASMO-3 cross section generation code was submitted on April 11, 1988 [ Reference (b)). The generic topical SIMULATE-3 steady-state three-dimensional (3-D) reactor physics code was submitted on September 12, 1988 [ Reference (c)]. In the enclosed benchmarking report, both cold critical startup and hot steady-state full power operation are modeled.

Extensive 3-D comparisons are made between the model-calculated and plant-measured detector responres. The results show improved agreement with plant data in comparison to the current methods.

8903310009 890327 l' l PDR ADOCK 05000271 P PDC j l

United States Nuclear Regulatory Commission March 27, 1989 Attention: Document Control Desk Page 2 As stated in our letter of October 13, 1988 [ Reference (d)], these methods are planned to be applied in the Vermont Yankee Cycle 15 analysis.

Because calculations must begin in September 1989 in order to meet a Cycle 15 startup scheduled for October 1990, we request that your review and approval of the subject report be conducted on a schedule consistent with these schedular requirements.

We trust this submittal is satisfactory; however, should you have any questions or require further information concerning this matter, please contact this office. Further, Vermont Yankee is prepared to meet and discuss

) this submittal at your convenience.

Very truly yours, VERMONT YANKEE NU LEAR POWER CORPORATION he f)

R. W. C Qstick Licensing Engineer RWC/sf/0277w Enclosure cc: USNRC Project Manager, VYNPC USNRC Region I USNRC Resident Inspector, VYNPS I

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