ML17261B028

Forwards Addl Info Re Proposed Tech Spec Amend Concerning Use of Reconstituted Fuel,Per 900315 Telcon.During Fuel Assembly Reconstitution,Failed Fuel Rods Will Be Placed W/ Filler Rods

ML17261B028
Person / Time
Site:	Ginna
Issue date:	03/23/1990
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson Office of Nuclear Reactor Regulation
References
NUDOCS 9004100223
Download: ML17261B028 (5)

Text

ACCELERATED ISTRIBUTION DEMONSTF&TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9004100223 DOC.DATE: 90/03/23 NOTARIZED: NO DOCKET g FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas 6 Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,'A.R. Project Directorate I-3 R

SUBJECT:

Forwards addi info re proposed Tech Spec amend concerning use of reconstituted fuel,per 900315 telcon.

D DISTRIBUTION CODE A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution S, NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 RECIPIENT COPIES RECIPIENT COPIES A ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PDl-3 LA 1 1 PD1-3 PD 1 1 D JOHNSON,A 5 5 D

INTERNAL: NRR/DET/ECMB 9H 1 NRR/DOEA/OTSB11 1 1 NRR/DST SE2 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 NRR/DST/SRXB SE 1 1 NUDOCS-ABSTRACT 1 OC LFMB 1 0 OGC/HDS2 1 1 RES/DSIR/EIB 1 EXTERNAL LPDR NSIC 1

1 1

1 NRC PDR 1,1 R

D D

NOTE TO ALL "RIDS" RECIPIENTS:

S PLEASE HELP. US TO REDUCE W~t CONTACT THE. DOCUMENT CONTROL DESK, ROOM PI-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISIRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19,

e C

C'. s~

~ lP iZuIIIII,Pi JIIIIiIIII I'7iy/ilmZZIIII

<L<<< 0 << ~

ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N Y. 14649-0001 March 23, 1990 TCL<:P<<ONC ARKA cooE 7<<< 546-2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Additional Information; Proposed Technical Specification Amendment Regarding Use of Reconstituted Fuel R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

On March 15, 1990, a telephone conference call was held. with personnel from Westinghouse, Rochester Gas and Electric Corporation and the NRC to discuss' proposed Technical Specification change for fuel reconstitution. As requested, attached is a summary of the DNB and seismic/LOCA discussions which pertain to this fuel reconstitution Technical Specification.

Very truly yours, Robert C. M ed Division Manager Nuclear Production RWEK095 Attachment xc: Mr. Allen R; Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale King of Prussia, Road Ginna Senior Resident Inspector PA 19406 ~< P-3+a 9s7aoq 9004i00223 05000244 ADOCK 900323 POo/

PDR PDC p f(1

ATTACHMENT On March 15, 1990, an RG&E/Nestinghouse telephone conference call with the NRC was held to respond to the NRC reviewer concerns on a requested. Ginna Technical Specification change for fuel reconstitution involving replacement of defective fuel rod(s) with filler rod(s) (stainless steel or Zircaloy-4). The NRC requested a summary of the key issues discussed in the conference call. The responses are as follows:

1. A conservative approach is utilized to determine the DNBR for all reconstituted assemblies which have filler rods that have replaced active fueled rods. Using approved NRC methods, an evaluation is performed assuming that the non-power producing filler rods operate at power levels equal to the highest power in any of the fueled rods in the reconstituted assembly. This results in DNBRs that are lower (less margin to the DNBR acceptance limit) than actually exists. The minimum DNBR must still be greater than the acceptance limit.

2. During fuel assembly reconstitution, the failed fuel rod(s) are to be replaced with filler rod(s). The filler rod(s) have outside diameters identical to the fuel rod diameter. The rod.

length is also the same. The grid strength will remain unchanged since the filler rod(s) will provide the same support in the grid cells as 'the fuel rods. For a small number of filler rod(s) (less than 10), the change in mass and stiffness of the fuel assembly will be insignificant. There will be negligible effects on fuel assembly dynamic properties, such as fuel fundamental frequency. Thus, the load carrying capability of the fuel assembly and grid spacers is not affected under the seismic and LOCA design loading conditions for the reconstituted fuel. It is anticipated that the same conclusion would be applicable for more than 10 filler rods; if this should occur specific evaluations will, be performed.

rz