ML20211A355

Forwards Safety Evaluation Re Use of VIPRE-01 thermal- Hydraulic Code & WRB-1 Critical Heat Flux Correlation W/Min DNBR Limit of 1.17.Code & Correlation Acceptable

ML20211A355
Person / Time
Site:	Prairie Island
Issue date:	05/30/1986
From:	Diianni D Office of Nuclear Reactor Regulation
To:	Musolf D NORTHERN STATES POWER CO.
Shared Package
ML20211A361	List: ML20211A355 ML20211A379
References
NUDOCS 8606110141
Download: ML20211A355 (3)

Text

,~ i Docket Nos. 50-282/306 Igtf 3 01986 Mr. D. M. Musolf, Manager Nuclear Support Services Northern States Power Company 414 Nicollet Mall Midland Square, 4th Floor Minneapolis, Minnesota 55401

SUBJECT:

TOPICAL REPORT RELOAD SAFETY EVALUATION METHODS, NSPNAD-8102P, Rev. 3, (VIPRE-01) PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT NOS. 1 AND 2 We have completed our review of Northern States Power Company's Reload Safety Evaluation Methods, NSPNAD-8102P, Rev. 3, dealing with the thermal margin analysis for the fuel assemblies at the Prairie Island Nuclear Generating Plant Unit Nos. I and 2. By letter dated April 19, 1985 and additional information provided by letters dated November 19, and December 5, 1985, you submitted Revision 3 to NSPNAD-8102P describing the applications of the VIPRE-01 Code in place of COBRA-IIIC/MIT and the WRB-1 Critical Heat Flux correlation in place of W-3 for analyzing the thermal margin for fuel reloads at Prairie Island.

We find that the use of the VIPRE-01 thermal hydraulic code and WRB-1 Critical Heat Flux (CHF) correlation with a minimum departure from nucleate boiling ratio (DNBR) limit of 1.17 for the Prairie Island Units is acceptable. We will require that you follow the EPRI quality assurance procedure regarding the VIPRE-01 modifications. In addition, the acceptance criterion for the condition IV events appearing in revision 3 of NSPNAD-8102P are to be replaced with the original criterion that would include the DNBR limit of 1.17 for the WRB-1 correlation. Five copies of revision 4 of i

8606110141 860530 PDR ADOCK 05000282 P PDR

NSPNAD-8102P containing the original criterion should be forwarded to the Commission within 30 days from receipt date of this letter. We consider our review of the VIPRE-01 Code and the WRB-1 (CHF) complete. <

A copy of our Safety Evaluation is enclosed.

Sincerely, Dominic C. Dilanni, Project Manager Project Directorate #1 Division of PWR Licensing-A

Enclosure:

3 Safety Evaluation p cc's: See Next Page Office: LA/ PAD #1 PM/ PAD #1)d PD/ PAD #

Surname: PShuttlewNfh DDilanni/tg Glear Date: 05// 86 05/f4/86 05 /86

Mr. D. M. Musolf Prairie Island Nuclear Generating Northern States Power Company Plant cc:  ;

Gerald Charnoff, Esq.

Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Washington, DC 20036 Executive Director Minnesota Pollution Control Agency 1935 W. County Road, B2 Roseville, Minnesota 55113 Mr. E. L. Watz1, Plant Manager Prairie Island Nuclear Generating Plant Northern States Power Company Route 2 Welch, Minnesota 55089 Jocelyn F. Olson, Esq.

Special Assistant Attorney General Minnesota Pollution Control Agency 1935 W. County Road, B2 Roseville, Minnesota 55113 U.S. Nuclear Regulatory Commission Resident Inspector's Office Route #2, Box 500A Welch, Minnesota 55089 Regional Administrator, Region III U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. William Miller, Auditor Goodhue County Courthouse Red Wing, Minnesota 55066

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