3F0390-03, 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  |
| 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
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' C O R POR A1 ION 1
-i lMarchL8, 1990
[.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"
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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
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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.
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.Re-analysis by Westinghouse, based on the allowable bearing stress t
capacities from Gilbert / commonwealth, determined an increase in the-
' size : of the support pads was needed to prevent local ' concrete n
spalling that could lead to liner damage or blockage;of the drain
. system.. The increased-pad size creates a larger bearing area while maintaining ~a~ margin'of. safety.
This revision produced a slight l
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~ 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
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