ML082610237
| ML082610237 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/16/2008 |
| From: | Entergy Nuclear Operations |
| To: | Office of Nuclear Reactor Regulation |
| Chawla M, NRR/DORL, 415-8371 | |
| References | |
| FOIA/PA-2009-0026 | |
| Download: ML082610237 (9) | |
Text
-- Entergy Palisades Spent Fuel Pool Storage Interim Criticality Analysis September 16, 2008
- Entergy Purpose
" Proposed plan for Palisades Spent Fuel Pool (SFP) Storage Interim Criticality Analysis
" Technical Specification (TS) changes and timing 2
- Entergy Palisades SFP Design
- The Palisades SFP is currently divided into Region I and Region I1.
- Region I is an NUS rack that contains Carborundum neutron absorber plates.
- Region II is a Westinghouse rack that contains Boraflex, but the Boraflex is no longer credited. Fuel assembly storage is restricted in accordance with Palisades Technical Specifications.
° Soluble boron is already credited in the Region II criticality analysis.
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Entergy Palisades SFP Layout 47 AW FUEL TRANSFER MECHANISM EW ATE FW
! 2 3
4 S
1 7
9 10 11 12
'13 14 15 16 17 18
$9 20 21 21 23 24
'DDDDDDDUWWDWDD WDODDEIEJ o.EDEIEIDDEII:]E)DODDEJEI-]EFIEIIEIIE
.O~D WWUWOD DDWDDDDWSDWO SERVICE FI lrFý F-01:00 DE0D00 E0E00000EE0D0 PLA AOMII olWlO000DE000EE00000000E0E 711 71 72 73 74 75 76 77 78 79 80 51 82 B3 84 85 86 87 88 89 90 91 92 93 x
':ZrnO0nE0DD0r0W00 OO000W NEW FUEL STORAGE RACK
- E:
NUS (Region 1) racks on left 48 49 50 $1 52 53 54 5556 S?
8 " 60 61 62 63 64 65 66 67 66 0 AW~ EAW
,0000000i CM117OOEI00000:
- t
- crn~E wrn~
w
- j Ew 0O0000001110i iiw I GATE I 00 30 31 32 33 34 JS 36 37 38 39 40 41 42 Q3 4S 45 6
,~
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,g ~o I25 26 27 28 29 I.
GW HW FW LW KW LW MW NW OW PW OW i
i i
1I I
1 i
i !
!I II, RW TI I II I I"W 1W luw W -
WESTINGHOUSE CREDIT FOR BUINUP RACK SUMERS POWER COMPANY SADES NUCLEAR PLANT FUEL STATUS CASK WASHDOWN CON PALl NOT Westinghouse (Region II) racks on right North Tilt Pit - Top Right (5x10 rack in center is a NUS Rack) 4
Entergy Palisades SFP Loading The Carborundum in Region I is degraded.
In August 2008 Region I SFP racks were considered operable but degraded as allowed by GL 91-18.
- Commitment made to submit a License Amendment Request and obtain approval before addition of positive reactivity to Region I.
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Enterg Project Overview
- Obtain a new, "simple" criticality analysis and License Amendment Request (LAR) to support fuel receipt in February 2009 and for the 1 R20 outage fuel shuffle.
" This is the "Phase 1" or "interim" analysis that will utilize a checkerboard or other pattern utilizing open cells and soluble boron credit to facilitate a LAR review and approval.
- A "Phase 2" or "Long Term" analysis will be submitted in 2009 to support the fall of 2010 refueling outage.
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Entergy Interim Analysis & Assumptions
- AREVA (Lynchburg, VA) has been awarded a contract to perform the analysis.
- Only the criticality analysis of Region I will be revised
- Applicable to Region I racks with no credit for Carborundum Use of open cells as means of reactivity control Reduced enrichment (to the maximum used at Palisades)
Fuel burnup (depletion) and decay time are not credited for reactivity holddown Credit for soluble boron in accordance with 1 OCFR50.68 (limit credit to 850 ppm to match that used in Region II)
Margin is retained relative to the acceptance criteria, versus analysis results at the limits.
- TH, Dose, Structural and Handling Accidents are not changed 7
~Enterg Palisades Proposed Licensing Amendment License amendment for Region I reflects new assumptions including the following:
- Storage restrictions for SFP where appropriate.
- Credit soluble Boron in the SFP water but not the Carborundum
- Continued compliance with 10 CFR 50.68(b).
- Fuel enrichment decreased from 4.95 wt.% CZAE to 4.54 wt% CZAE.
- No credit for fuel burnup or decay time.
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Entergy Palisades Submittal Plans
- LAR submitted by November 26, 2008 with NRC approval by February 13, 2009.
° Advantage
- Allows for a fuel shuffle during the next refueling outage at Palisades, in March 2009.
" Disadvantage
- NRC review time is short.
Full core offload capability is not expected to be able to be maintained.
9