ML20004B245

Submits Supplemental Info Responding to Open Item 5 of NUREG-0519,SER for Facility.Ge 810512 Rept Re Fuel Swell & Rupture Model Experimental Data Review & Sensitivity Studies Indicate ECCS Analysis Is Adequate

ML20004B245
Person / Time
Site:	LaSalle
Issue date:	05/21/1981
From:	Delgeorge L COMMONWEALTH EDISON CO.
To:	Schwencer A Office of Nuclear Reactor Regulation
References
RTR-NUREG-0519, RTR-NUREG-519 NUDOCS 8105270440
Download: ML20004B245 (2)

Text

Commonwealth Edison One Fast National Plaza. Chicago, Illinds Address Reply to: Post Office Box 767 Chicago. Illinois 60690 May 21, 1981 y'y .

9 j ."

Mr. A. Schwencer, Chief Licensing Branch 2 C 'lr- d Division of Licensing 'j L~

7' U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Q[o ff, c3 e

Subject:

LaSalle County Station Units 1 and 2 O. s \uA Supplemental Information Responding to Open Item 5 (NUREG-0519, Section 1.9)

NRC Docket Nos. 50-373/374

Dear Mr. Schwencer:

As has been indicateo previously, Commonwealth Edison juoges that the current analyses in FSAR Section 6.3.3 adequately addresses the NRC Staff questions relative to fuel material models that are used in emergency core cooling system evaluations. This judgement has been supported by generic assessment made by the NSSS vendor in 1980. Furthermore, the position stated by the ACRS in its letter to the NRC on September 9, 1980, that " implementation of the NUREG-0630 models ind other significant changes in the evaluation '

models be held in abeyance until a thorough revision of Appendix K requirements can be undertaken by the NRC Staff", suppcrts the position that changes are not required at this time.

However, in order to resolve the NRC Staff concern, General Electric has performed and submitted to the Staff, a report entitled

" General Electric Fuel Swell and Rupture Model Experimental Data Review and Sensitivity Studies" dated May 12, 1981. This report, which covers GE BWR fuel of the type used at LaSalle County Station, provides added assurance that the LaSalle County emergency core cooling analysis is adequ?te. It is judged that this GE report addresses the requirements in Section 4.2.3.3 of the LaSalle County Safety Evaluation Report (NUREG-0519) for supplemental calculations reconciled with the material models in NUREG-0630.

In the event there are any further questions in this regard, plaase direct them to this office.

Very truly,yours, 30 N /ibiyL f/o L. O. DelGeorge Nuclear Licensing Administrator cc: NRC Resident Inspector - LSCS 2042N "10sno