ML20044B840

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Advises NRC of Util Intention to Utilize FROSSTEY-2 Methodology in Generation of Reload Analyses for Upcoming Cycle 14 & Subsequent Operating Cycles
ML20044B840
Person / Time
Site: Maine Yankee
Issue date: 03/05/1993
From: Hebert J
Maine Yankee
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JRH-93-45, MN-93-26, NUDOCS 9303100219
Download: ML20044B840 (2)


Text

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MaineYankee REllABLE ELECTRICITY FOR MAINE SINCE 1972 EDtSON DRIVE. AUGUSTA, MAINE 04330.(207) 622 4868 March 5, 1993 MN-93-26 JRH-93-45 UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Washington, DC 20555

Reference:

(a)

License No. DPR-36 (Docket No. 50-309)

Subject:

Use of the FROSSTEY-2 Methodology for Reload Analyses Gentlemen:

With this letter, Maine Yankee is informing the NRC of our intention to utilize the FROSSTEY-2 methodology in the generation of reload analyses for the upcoming Cycle 14 and subsequent operating cycles.

The references, including the Safety Evaluations Report (SER), defining this methodology are listed in Attachment A of this letter.

The FROSSTEY-2 fuel performance code is intended for use in the loss-of-coolant accident (LOCA) analysis as well as for other accidents, transients, and normal operation. The code provides for the determination of the stored energy and fuel rod internal pressures for the LOCA analysis and other analyses requiring a fuel pin thermal performance model that is capable of calculating fuel and cladding behavior, including the fuel-clad gap conductance, as a function of rod burnup..The parameters affecting fuel performance, such as fission gas release, clad dimensional changes, fuel densification, fuel thermal expansion, and fuel swelling are accounted for in the methodology. The methodology limitations are defined in the Technical Evaluation Report which accompanies the SER.

Please contact us if you have questions concerning the use of this methodology at Maine Yankee.

Very truly yours,

>ew h 6

James R. Hebert, Manager Licensing & Engineering Support Department JRH/ jag Attachment c:

Mr. Thomas T. Martin Mr. Charles S. Marschall i

Mr. E. H. Trottier Mr. Patrick J. Dostie 090088 Hr. Clough Toppan 3

m'Me 9303100219 930305

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PDR ADDCK 05000309 p

PDR

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ATTACHMENT A

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References for FROSSTEY-2 Methodology i

a.

Report, S. P. Schultz and K. E. St. John, " Methods for the Analysis of 0xide Fuel Rod Steady-State Thermal Effects (FROSSTEY): Code /Model Description Manual," YAEC-1249P, dated April 1981.

b.

Report, S. P. Schultz and K. E. St. John, " Methods for the Analysis of 0xide Fuel Rod Steady-State Thermal Effects (FROSSTEY): Code Qualification and Application," YAEC-1265P, dated June 1981.

c.

Letter from R. W. Capstick (VYNPC) to USNRC, "Vermoat Yankee LOCA Analysis i

Method FROSSTEY Fuel Performance Code (FROSSTEY-2)," FVY 87-116, dated December 16, 1987.

d.

Letter from R. W. Capstick (VYNPC) to USNRC, " Response to NRC Request for Additional Information on the FROSSTEY-2 Fuel Performance Code," BVY 89-65, dated July 14, 1989.

e.

Letter from R. W. Capstick (VYNPC) to USNRC, " Supplemental Information on the i

FROSSTEY-2 Fuel Performance Code," BVY 89-74, dated August 4,1989.

f.

Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Responses to Request for l

Additional Information on FROSSTEY-2 Fuel Performance Code," BVY 90-045, dated April 19, 1990.

g.

Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Supplemental Information to VYNFC April 19, 1990, Response Regarding FROSSTEY-2 Fuel Performance Code," BVY 90-054, dated May 10, 1990.

j h.

Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, " Responses to Request for Additional Information on FROSSTEY-2 Fuel Performance Code," BVY 91-024, dated March 6, 1991.

j i.

Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, "LOCA Relatea Responses to Open Issues on FROSSTEY-2 Fuel Performance Code," BVY 92-39, dated March 27, 1992.

l j.

Letter from L. A. Tremblay, Jr. (VYNPC) to USNRC, "FROSSTEY-2 Fuel Performance Code - Vermont Yankee Response to Remaining Concerns," BVY 92-54, dated May 15, 1992.

k.

Letter from P. Sears (USNRC) to L. A. Tremblay (VYNPC), " Vermont Yankee Nuclear Power Station, Safety Evaluation of FROSSTEY-2 Computer Code," NVY 92-178, dated September 24, 1992.

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