ML19262B583

Discusses Potential Deficiency,Per 791116 Telcon to Nrc. Westinghouse Review Reveals That Dropped Rod Safety Analysis Deficiency May Affect Four Addl Loop Plants.Further Info Will Be Provided by FSAR Revision

ML19262B583
Person / Time
Site:	Wolf Creek, Callaway, Sterling
Issue date:	12/14/1979
From:	Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
SLNRC-79-22, NUDOCS 7912280593
Download: ML19262B583 (2)

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SNUPPS Standardized Nuclear Unit Power Ptent System 5 Choke Cherry Road Rockville, Marytend 20050 (301) 86M010 December 14, 1979 SLNRC 79-22 File: 0491.10.2 SUBJ: Rod Drop Analysis Mr. Boyce Grier Director, Region I Office of Inspection and Enforcement U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, Pennsylvania 19406 Docket Nos: STN 50-482, STN 50-483, STN 50-485, STN 50-486 Ref: 1. SNUPPS letter to NRC Region I, SLNRC 79-5, dated April 26, 1979, Rod Drop Safety Analysis

2. Westinghouse letter (T.M. Anderson), NS-TMA-2167, to USNRC (A.

Schwencer),datedNovember 15, 1979, same subject.

Dear Mr. Grier:

On November 16, 1979, SNUPPS informed the Nuclear Regulatory Commission, Region I Office of Inspection and Enforcement, of a potential deficiency involving the dropped rod safety analysis. The information was communicated by telephone to Mr. Bateman of your staff pursuant to 10 CFR 50.55(e).

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Reference 1 withdrew an initial notification of a reportable deficiency con-cerning the dropped rod analysis on the basis of Westinghouse studies for four loop plants. Reference 1 also indicated that the matter would be further examined. As a result of that ongoing review, Westinghouse determined that the original concern may, in fact, involve four loop plants such as SNUPPS.

Reference 2 described the specific concerns with the single and multiple rod drop analyses.

SNUPPS will continue to pursue the resolution of this matter and will address it in a revision to the SNUPPS FSAR. A permanent resolution of the concern is expected by mid - 1980. However, should a pennanent fix not be approved prior to start-up of the first SNUPPS plant, procedural changes can be adopted as an interim solution.

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SLNRC 79-22 File: 0491.10.2 Page 2 As further information is available on this matter, SNUPPS will inform ths NRC.

Ver truly yours,

<-h--< \ C Nicholas A. Petrick RLS/yt cc: Mr. James G. Keppler, Director, Region III, USNRC Mr. Karl V. Seyfrit, Director, Reaion IV, USNRC Mr. Victor Stello, Jr. , Director, Office of Inspection ./

and Enforcement, USNRC, Washington, D.C.

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