ML20012B634

From kanterella
Jump to navigation Jump to search
Forwards Rev 1 to Tech Spec Tables 3-2 & 3-3 Re Min Margin to Allowable for Various Components & Welds in Facility Racks,As Followup to Tech Spec Change Request 175, Spent Fuel Pool Storage Capacity.
ML20012B634
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 03/08/1990
From: Beard P
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20012B635 List:
References
3F0390-03, 3F390-3, NUDOCS 9003150460
Download: ML20012B634 (2)


Text

, 1 pe ,.p

, g. 1 f

.l l I' ' [- %

7 ,. . -

t i .

I

' C O R POR A1 ION 1 -i lMarchL8, 1990

.  !3F0390-03

[.i

" U.S.. Nuclear Regulatory Commission

' Attn:? Document Control Desk

'.Washin'gton, D., C. - 20555 Subj e'ct: Crystal River Unit 3 Docket:No. 50-302

  • Operating License No. DPR-72 .

R Technical Specification Change Request No. 175 Revision 1, " Spent Fuel Pool Storage Capacity"

}-

l

Dear ~ Sir:

-Florida Power Corporation'(FPC) submitted Technical Specification Change Request No.= (TSCRN) 175 on October '31,1989. Tables 3-2 and  :

l'  : 3-3 of TSCRN 175 show the minimum ~ margin to allowable for the '

[' various = components and: welds on: the Crystal River - 3 racks. The l-  : margins listed- represent. the- limiting lo_ad combinations -and L Lenvelopel all; the. load. combinations ' listed in section. 3.6 of the

. licensing--report.provided to. support TSCRN 175. FPC is revising Tables'3-2 and 3-3 for.the reasons explained'below.

It was discovered,<while. reviewing drawings of' thel'B'. spent fuel pool '(SFP) , that; the new fuel elevator had note beenL considered

during-design of-the new SFP racks. One rack in Region 1 had to-be modified ' to delete 6 cells to make, .. space for the . . elevator.

f Information related ~to this modification / was included: in the

[ - origir'al Techcical Specification submittal in~ October. = - The final  !

!! results from ' the analysis performed . on the modified rack is.

included in the-attached tables'for Region 1.

}

' Westinghouse's review'of'FPC's SFP liner drawings identified that:

ten support pads: would span across ~ drainage. channels Lin the 'SFP.

L t

.Re-analysis by Westinghouse, based on the allowable bearing stress capacities from Gilbert / commonwealth, determined an increase in the-n ' size : of the support pads was needed to prevent local ' concrete spalling that could lead to liner damage or blockage;of the drain l

. system.. The increased-pad size creates a larger bearing area while I maintaining ~a~ margin'of. safety. This revision produced a slight l

1

'p l.9003150460

- PDR- ADOCK 900308 05000302 ; f' r l

l P. PDC  %

POST OFFICE BOX 210

  • CRYSTAL RIVE 1, FLORIDA 326294219 + (904) 795 6486 g'

"v A Florida Progress Company y

1 . .

5 y, .. :

~ March 8, 1990 3F0390-03 Page 2 l

., change-in the load distribution within the rack structure and the results are reflected in the attached tables. The margin in each

. caseLshows that.the racks meet the structural requirements of the  !

ASME Code. l Attached are the-replacement pages for Tables 3-2 and 3-3.

Sincerely,

. M. Beard, Jr.

Senior Vice President Nuclear Operations PMB/GMF Attachment xc: . Regional Administrator, Region II l Senior Resident Inspector j l

i i

I 1

i