ML20073D446

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Forwards Rev 0 to Topical Rept ENEAD-02-NP, Verification of Cecor Coefficient Methodology for Application to PWRs of Entergy Sys for Review & Approval
ML20073D446
Person / Time
Site: Arkansas Nuclear, Waterford  Entergy icon.png
Issue date: 09/23/1994
From: Titus F
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20073D447 List:
References
CNRO-94-00021, CNRO-94-21, NUDOCS 9409270212
Download: ML20073D446 (3)


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Fred W. Titus

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o September 23,1994 U.S. Nuclear Regulatory Commission Mail Station PI-137 Washington, D.C. 20555 Attention:

Document Control Desk

SUBJECT:

Request For Review of Entergy Topical Report Verification of CECOR Coefficient Methodology for Application to Pressurized Water Reactors of the Enterev S ggm, (ENEAD-02-NP, Revision 0)

J Arkansas Nuclear One Unit 2 Docket No. 50-368 License No. NPF-6 Waterford 3 Steam Electric Station Docket No. 50-382 License No. NPF-38 CNRO-94/00021 Gentlemen:

Entergy Operations, Inc. is submitting by this letter for your review and approval the attached topical report. This report describes the methodology used at Entergy Corporation to determine the library coef6cients and the resultant " reliability factors" associated with the Entergy CECOR core power distribution monitoring computer program. The results contained in this document were derived from extensive benchmarking efforts performed by Entergy personnel on two Entergy pressurized water reactors: Arkansas Nuclear One - Unit 2 (ANO-2), and the Waterford Steam Electric Station - Unit 3 (WSES-3)

Entergy Operations provides cycle specific data libraries to ANO-2 and WSES-3 for the CECOR core power distribution monitoring pregram based on the NRC approval of 2CUtiR a

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Request For Review of Entergy Topical Report Verification of CECOR Coefficient Methodolouv for Application to Pressurized Water Reactors of the Entergv System, (ENEAD-02-NP, Resision 0)

September 23,1994 CNRO-94/00021 Page 2 of 3 Verification of CECOR Coeflicient Methodology for Application to Pressurized Water Reactors of the Middle South Utilities, MSS-NA3-P (Approved 8/30/85). In this report CECOR libraries were based on using the design computer codes, PDQ and EPRI-NODE-P. Entergy Operations now proposes to use the design computer codes SIMULATE and CASMO to generate libraries for CECOR at ANO-2 and WSES-3. The benefits from using the new codes are to: 1) allow the use of the same codes for all Entergy reactor units; 2) increase the ability to model more advanced core designs, and 3) reduce the reliability factors associated with the CECOR library generation process.

The CASMO and SIMULATE codes themselves have been approved by the NRC for use by at least one other utility, but this approval did not address EOI plants. In order to qualify these codes for generating CECOR libraries for Entergy PWRs, we have prepared this Entergy application specific topical report for your review.

Entergy Operations requests your review and approval of the attached topical report for use at ANO-2, and WSES-3. In order to meet our refueling schedules, we request your approval by October 1,1995.

Sincerely,

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s Request For Review of Entergy Topical R'eport Veriftcation of CECOR Coeflicient Methodology for Application to Pressurized Water Reactors of the Entergy System.

(ENEAD-02-NP, Revision 0)

September 23,1994 CNRO-94/00021 Page 3 of 3 cc:

Mr. R. P. Barkhurst, w/o Mr. J. L. Blount, w/o Mr. R. F. Burski, w/o Mr. L. J. Callan, w/o Mr. J. L. Colvin, w/o Mr. C. B. Franklin, w/a Mr. G. Kalman, w/a Mr. H. W. Keiser, w/o Mr. R. B. Lang, w/a Mr. L. W. Laughlin.w/a Mr. R. B. McGehee, w/o Mr. J. L. Milhoan, w/o Mr. D. C. Mims, w/o Mr. F. T. Philpott, w/a Mr. N. S. Reynolds, w/o Mr. J. C. Robens, w/o Mr. D. W. Vinci, w/o Mr. D. L. Wigginton, w/a Mr. J. W. Yelverton, w/o DCC (ANO)

Records Center (WF-3)

Corporate File [

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