BVY-97-110, Forwards Rept YAEC-1941, Addl Benchmarking of BWRs Using CASMO-3/SIMULATE-3, Which Demonstrates Suitability of Using Codes for BWR Operational Support & Reload Licensing.Various Graph Pgs of Submittal Had Data Cut from Left Margin Area

Forwards Rept YAEC-1941, Addl Benchmarking of BWRs Using CASMO-3/SIMULATE-3, Which Demonstrates Suitability of Using Codes for BWR Operational Support & Reload Licensing.Various Graph Pgs of Submittal Had Data Cut from Left Margin Area

ML20210T546
Person / Time
Site:	Vermont Yankee
Issue date:	09/10/1997
From:	Duffy J VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20210T552	List: BVY-97-110, Forwards Rept YAEC-1941, Addl Benchmarking of BWRs Using CASMO-3/SIMULATE-3, Which Demonstrates Suitability of Using Codes for BWR Operational Support & Reload Licensing.Various Graph Pgs of Submittal Had Data Cut from Left Margin Area ML20210T555
References
BVY-97-110, NUDOCS 9709150194
Download: ML20210T546 (2)

Text

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VERMONT YANKEE NUCLEAR POWER CORPORATION

. - Ferry Road, Brattleboro, VT 05301-7n02 v ENGINEERIN OFFICE

• 580 MAIN STREET

• BOLTON. MA 01740 (506) 77H711 September 10,1997 BVY 97-110 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 205ES

References:

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

(b) Letter, VYNPC to USNRC, NVY 97 69, dated May 22,1997 (c) Letter, VYNPC to USNRC, BVY 89 29, dated March 27,1989 i

(d) Letter, USNRC to VYNPC, NVY 90-53, dated March 15,1990  :

(e) Letter, VYNPC to USNRC, BVY 95-115, dated October 31,1995 l (f) Letter, USNRC to VYNPC, NVY 96-175, dated November 5,1996. l

Subject:

Submittal of YAEC-1941 " Additional Benchmarking of Boiling Water Reactors Using i CASMO-3/ SIMULATE-3." l l

As committed to in Reference (b), Vermont Yankee is submitting, for NRC information, YAEC 1941, " Additional Benchmarking of Bailing Water Reactors Using CASMO-3/ SIMULATE-3." i This report demonstrates the suitability of using these codes for BWR operational support and r; load licensing using advanced fuel types such rs the GE11 and GE13.

In Reference (c), Vermont Yankee submitted the CASMO-3/ SIMULATE-3 topical report (YAEC- l 1683) for NRC review. The topical report benchmarked Cycles 9 through 13 of Vermont

- Yankee and described in detail the codes and the plant specific models. NRC approved use of these codes in Reference (d). The SER accompanying Reference (d) states three restrictions er conditions. These restrictions / conditions continue to be met in the attached topical report as described below:

~ 1). Spacer corrections and bowed channel cross sections should be used in the appIlcation of the Vermont Yankee model. 1 The Vermont Yankes model used in YAEC-1941 uses spacer correction and an g appropriate amount of bowed channel cross-sections. '

2) - A, pilcation of the model should be restricted to the range of the operating conditions existing throughout the Vermont Yankee benchmarked Cycles 9-13.

Vermont Yankee has validated and used SIMULATE-3 to model low power / low flow cases for the kinetics data used in the LAPUR stability model, YAEC-1926, submitted in Reference (e) and approved by NRC in Reference (f), YAEC-1941 provides i benchmarks and documents low power / low flow cases to plant data. No additional approvalis required or sought.

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VERMONT YANKEL NUCLLAR POWER CORPORATION

' United States Nuclear Regulatory Commission September 10,1997 Page 2 of 2

3) Should new fuel designs be introduced In the future, additional validation will be required for this system of codes.

Pilgrim Nuclear Power Station (PNPS) introduced the GE11 in Cycle 11. YAEC 1941 benchmarks three cycles of PNPS including Cycle 11. GE11 is neutronically similar to the GE13 bundle which will be used in Vermont Yankee Cycle 20. The benchmark in YAEC-1941 validates that the CASMO-3/ SIMULATE-3 system of codes can successfully model the advanced fus; designs.

in Reference (b) Vermont Yankee indicated that the SIMUL. ATE-3 benchmarks would be submitted for NRC review and approval. However, since the benchmarks presented in YAEC-

- 1941 satisfy all of the restrictions / conditions stated in Reference (d), the report is being

- subrnitted for information only. Vermont Yankee intends to use this model for analysis of the Cycle 20 reload (Spring 1998 refueling outage).

Vermont Yankee makes no new commitments with this letter.

We trust that this submittalis satisfactory. However, if additionalinformation is required, please contact this office.

Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION nrt& b James J. Duffy Licensing Engineer c: tJSNRC Region 1 Administrator USNRC Resident inspector -VYNPS USNRC Project Manager - VYNPS ,

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