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F-28 Ou17, g,y, g l
F-28 Ou17, g,y, g R EA N A _YS S 0 7
l R EA N A _YS       S07          - E C RYS A       _        R VER 300_ 3 S 3 E s" TU E _ S"0 RAG E RAC <S                                                   '
- E C RYS A R V E R 300_ 3 S 3 Es" TU E _ S"0 RAG E RAC <S W"-
W"- 30RAr EX JEGRAJA~ Os _
30RAr EX JEGRAJA~ Os Holtec Report HI-982056 Holtec Project No:
l Holtec Report HI-982056 Holtec Project No:       80855 Report Class:           SAFETY RELATED Report Category: A HOLTEC INTERNATIONAL s
80855 Report Class:
230 Normandy Circle E.                   555 Uncoln Dr. West Palm Harbor FL 34683                     Marlton, NJ 08053 R               2
SAFETY RELATED Report Category: A HOLTEC INTERNATIONAL s
230 Normandy Circle E.
555 Uncoln Dr. West Palm Harbor FL 34683 Marlton, NJ 08053 2
R v


c
c F-28-0017. Rev. O i
        , ,                                                                                                                          F-28-0017. Rev. O i
1 REVIEW AND CERTIFICATION LOG oOctMENT NAME.
1 1
Reanalysis of the Crystal River Pool B Spent Fuel Storage Racks with Boraflex Degradation I!OLTEC DOCUMENT I D. NUMBER:
REVIEW AND CERTIFICATION LOG 1
111-982056 IIOLTEC PROJECT NUMBER:
oOctMENT NAME.
80855 1
Reanalysis of the Crystal River Pool B Spent Fuel Storage Racks with Boraflex Degradation I!OLTEC DOCUMENT I D. NUMBER:                 111-982056 IIOLTEC PROJECT NUMBER:
CUSTOMER, CLIENT:
80855                                                                                       1 CUSTOMER, CLIENT:                             Florida Power Corp.
Florida Power Corp.
l REVISION BLOCK REVISION               AUTIIOR                 REVIEW ER             QA & DATE               APPROVED'         D!STRIBUTION NUMBER                    & DATE                   & DATE                                           & DATE S.E. Turner           [*OC*uf# WO 'd b- A"E4 ORIGINAL                                        t (. h                                                               Ob w/s e e                10I         a)y u        N"~*
REVISION BLOCK REVISION AUTIIOR REVIEW ER QA & DATE APPROVED' D!STRIBUTION
* G    P_%
& DATE
w/t/16 en%
& DATE
M # T*
& DATE NUMBER S.E. Turner
* e t n&.- o co .
[*OC*uf# WO b-A"E4 t (. h N
REVISION I                                   h/                           vGv ta             /.               43       8-
* G P_%
                                      &,fgs"                     to/to/5r               t o 1o cl %               ifw/pg               f REVISION 2 REVISION 3 This document conforms to the requirements of the design specification and the applicable sections of the governing codes.
Ob ORIGINAL
'd 10I a)y
"~*
u w/t/16 w/s e e en%
e t n&.- o co.
REVISION I M # T*
* h/
vGv ta /.
43 8-
&,fgs" to/to/5r f
t o 1o cl %
ifw/pg REVISION 2 REVISION 3 This document conforms to the requirements of the design specification and the applicable sections of the governing codes.
Note: Signatures and orinted names required in the review block.
Note: Signatures and orinted names required in the review block.
* A revision of this document will be ordered by the Project Manager and carried out if any if the contents is materially affected during evolution of this project. The determination as to the need for revision will be made by the Project Manager.
A revision of this document will be ordered by the Project Manager and carried out if any if the contents is materially affected during evolution of this project. The determination as to the need for revision will be made by the Project Manager.
I       Must be Project Manager or his designee.
I Must be Project Manager or his designee.
x       Distribution:               C: Client i
x Distribution:
C: Client i
M: Designated Manufacturer F: Florida Office Report category on the cover page indicates the contractual status of this document as "-
M: Designated Manufacturer F: Florida Office Report category on the cover page indicates the contractual status of this document as "-
A-to be submitted to client for approval       != for client's information   N= not for external distribution I
A-to be submitted to client for approval
!= for client's information N= not for external distribution I
TIIE REVISION CONTROL OF TIIIS DOCUMENT IS BY A "  
TIIE REVISION CONTROL OF TIIIS DOCUMENT IS BY A "  


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F-98-0017. Rev, O l
F-98-0017. Rev, O l
Summary of Revisions I
Summary of Revisions Report HI-982056 Revision 1 Corrected typographical errors on Table 4.1.
l Report HI-982056 Revision 1 Corrected typographical errors on Table 4.1.                           l 1
1 l
l 1
1 I
I Holtec Report HI-982056
Holtec Report HI-982056


y.;s.co17. Rev. O TABLE OF CONTENTS
y.;s.co17. Rev. O TABLE OF CONTENTS


==1.0       INTRODUCTION==
==1.0 INTRODUCTION==
AND  
AND  


==SUMMARY==
==SUMMARY==
. . . . . . . .                            I 2.0         ANALYSIS CRITERIA AND ASSUMPTIONS                                   4 3.0         ACCEPTANCE CRITERIA . . . . . . . . . . . . . . .                   5 4.0         DESIGN AND INPUT DATA . . . . . . . . . . . . .                   7 5.0         METHODOLOGY . . . . . . . . . . . . . . . . . . . . . .             9 6.0         ANALYSIS RESULTS . . . . . . . . . . . . . . . . . . .             10 7.0         RE FE RENC E S . . . . . . . . . . . . . . . . . . . . . . . . . . 13               I I
I 2.0 ANALYSIS CRITERIA AND ASSUMPTIONS 4
Holtec Report HI-982056 e
3.0 ACCEPTANCE CRITERIA...............
5 4.0 DESIGN AND INPUT DATA.............
7 5.0 METHODOLOGY......................
9 6.0 ANALYSIS RESULTS...................
10 7.0 RE FE RENC E S..........................
13 Holtec Report HI-982056.
e


l                                                                                                   i l,       ,                                                                    F484017 Rev.O       l l
l i
LIST OF TABLES                               I 4.1       DESIGN BASIS FUEL ASSEMBLY SPECIFICATIONS 6.1       COMPARISON OF CALCULATIONS 6.2       REACTIVITY UNCERTAINTIES DUE TO MANUFACTURING TOLERANCES 6.3       REACTIVITY  
l, F484017 Rev.O l
LIST OF TABLES 4.1 DESIGN BASIS FUEL ASSEMBLY SPECIFICATIONS 6.1 COMPARISON OF CALCULATIONS 6.2 REACTIVITY UNCERTAINTIES DUE TO MANUFACTURING TOLERANCES 6.3 REACTIVITY  


==SUMMARY==
==SUMMARY==
REGION 1 (Checkerboard w/5%E Fuel) 6.4       REACTIVITY  
REGION 1 (Checkerboard w/5%E Fuel) 6.4 REACTIVITY  


==SUMMARY==
==SUMMARY==
REGION 2 (Fully Loaded) 6.5       REACTIVITY  
REGION 2 (Fully Loaded) 6.5 REACTIVITY  


==SUMMARY==
==SUMMARY==
REGION 2 (3 of 4 Loading) 6.6       REACTIVITY EFFECTS OF ABNORMAL AND ACCIDENT CONDITIONS
REGION 2 (3 of 4 Loading) 6.6 REACTIVITY EFFECTS OF ABNORMAL AND ACCIDENT CONDITIONS 6.7 EFFECT OF TEMPERATURE AND VOID ON CALCULATED
            ~
~
6.7       EFFECT OF TEMPERATURE AND VOID ON CALCULATED REACTIVITY OF STORAGE RACKS l
REACTIVITY OF STORAGE RACKS l
llottec Report Hi 982056 4                                                              - ii -
llottec Report Hi 982056
I
- ii -
* f
4 I
f


i . .
i 69%017' Rev. O l
69%017' Rev. O l 1
1 LIST OF FIGURES 1
l LIST OF FIGURES 1
l l
l l                 Fig. 4.1   REGION 1 FUEL STORAGE CELL l
Fig. 4.1 REGION 1 FUEL STORAGE CELL l
Fig. 4.2   REGION 2 FUEL STORAGE CELL l
Fig. 4.2 REGION 2 FUEL STORAGE CELL l
l 4
l 4
l                                                                        l l                                                                        l l
l l
l l
l l                                                                       I 1
l l
l i                                                                       l l
l i
1 l
l 1
l l
l l
l l
l l
Holtec Report HI-982056
l Holtec Report HI-982056
                                              - iii .
- iii.
l'                         ,
l'


bh17. Rey, o
bh17. Rey, o


==1.0         INTRODUCTION==
==1.0 INTRODUCTION==
AND  
AND  


==SUMMARY==
==SUMMARY==
 
The purpose of the present evaluation of the CR3 Pool B stora;;; racks is threefold: (1) to update the analyses, incorporating the more modern and improved methodologies that have become available in the last few years, (2) to determine the potential effect of Boraflex degradation on criticality safety, and (3) to confirm configurations for acceptable storage of fuel with enrichments up to 5 0.05% U-235. The updated evaluation encompasses both Regions I and 2 of Pool B at the Crystal River Nuclear Plant, and it considered the potential effects of up to 20% loss of the Botaflex absorber.
The purpose of the present evaluation of the CR3 Pool B stora;;; racks is threefold: (1) to update the analyses, incorporating the more modern and improved methodologies that have become available in the last few years, (2) to determine the potential effect of Boraflex degradation on criticality safety, and (3) to confirm configurations for acceptable storage of                         .
The present analyses are based on the existing Technical Specifications of acceptable bumup-enrichment combinations for safe storage of fresh and spent fuel. Region 1 of Pool B uses a flux-trap design and is designed for fresh fuel of 5.0% enrichment positioned in a checkerboard pattem with spent fuel of specified enrichment-bumup combinations. The Region I storage cells are separated by two Boraflex panels with a flux-trap water gap between the two panels, while Region 2 consists of a uniform array of cells, designed for l
l fuel with enrichments up to 5 0.05% U-235. The updated evaluation encompasses both l
spent fuel of specified enrichment bumup combinations.
Regions I and 2 of Pool B at the Crystal River Nuclear Plant, and it considered the potential effects of up to 20% loss of the Botaflex absorber.
These cells have a single Boraflex absorber panel between cells.
The present analyses are based on the existing Technical Specifications of acceptable                                   ,
i l
                                                                                                                                        . I bumup-enrichment combinations for safe storage of fresh and spent fuel. Region 1 of Pool l
The principal differences between the present analysis and the previous evaluationm are the following:
B uses a flux-trap design and is designed for fresh fuel of 5.0% enrichment positioned in a checkerboard pattem with spent fuel of specified enrichment-bumup combinations. The Region I storage cells are separated by two Boraflex panels with a flux-trap water gap between the two panels, while Region 2 consists of a uniform array of cells, designed for l                 spent fuel of specified enrichment bumup combinations.               These cells have a single i
Boraflex absorber panel between cells.
l The principal differences between the present analysis and the previous evaluationm are the following:
l l
l l
The present analysis uses the full 238 group cross-section set based on the ENDF/BV cross-sections in contrast to the l
The present analysis uses the full 238 group cross-section set based on the ENDF/BV cross-sections in contrast to the l
early 123-group set based on ENDF/BII cross-sections, This improvement is worth in excess of 1% in k.
early 123-group set based on ENDF/BII cross-sections, This improvement is worth in excess of 1% in k.
As peimitted in the USNRC guidelines, parametric l_                                   evaluations in the present analysis were performed for each of I
As peimitted in the USNRC guidelines, parametric l_
the . manufacturing tolerances and the associated reactivity Holtec Repon HI-982056 1-r                     - , --,          . - ,                  ._,.,-. ~_,   , ..                                -    , , , . . . . .
evaluations in the present analysis were performed for each of I
the. manufacturing tolerances and the associated reactivity Holtec Repon HI-982056 1-r
._,.,-. ~_,


1                                                                                                             l F-28-0017. Rev. O ,
1 F-28-0017. Rev. O uncertainties combined statistically. The previous analysism had assumed that all tolerances were at their " worst" value simultaneously everywhere throughout the racks. This improvement reduces reactivity by about 2 to 3% in k.
uncertainties combined statistically. The previous analysism had assumed that all tolerances were at their " worst" value                     l
The previous evaluation acknowledged that the axial distribution in Borallex gaps was random, but chose to assume 4 inch gaps on only two panels per cell, with all occurring at the fuel mid plane. Since there is no known justification or rationale for this unnecessarily conservative assumption, the present analysis calculated the effect of a random distribution of 4 inch gaps in all Boraflex panels, consistent with efTects observed in many rack blackness tests.
;                            simultaneously everywhere throughout the racks. This                             I improvement reduces reactivity by about 2 to 3% in k.
In contrast to the factors reducing the calculated reactivity, the USNRC guidelines require inclusion of an estimate of the uncertainty in depletion calculations (different from the plant's 5% penalty for uncertainty in knowing the burnup). As specified in the guidelines, this uncertainty was taken as 5% of the reactivity decrement from beginning oflife to the burnup ofinterest.
The previous evaluation acknowledged that the axial distribution in Borallex gaps was random, but chose to assume 4 inch gaps on only two panels per cell, with all occurring at the fuel mid plane. Since there is no known                         1 justification or rationale for this unnecessarily conservative assumption, the present analysis calculated the effect of a random distribution of 4 inch gaps in all Boraflex panels, l
Botaflex is now known to degrade under the influence of gamma radiation and chemical reaction with free radicals in the pool water. Over the first few years of use, the Boraflex will shrink, creating gaps distributed randomly in the axial direction. Over later years, as the gamma dose increases, the Boraflex panels will slowly begin to deteriorate, losing the neutron absorbing component (B C). The present analysis conservatively assumes the 4
consistent with efTects observed in many rack blackness tests.
presence of 4-inch gaps in all Boraflex panels. The potential reactivity consequences of concurrent loss of up to 20% of the Boraflex was also evaluated.
In contrast to the factors reducing the calculated reactivity, the USNRC guidelines require inclusion of an estimate of the uncertainty in depletion calculations (different from the plant's 5% penalty for uncertainty in knowing the burnup). As specified in the guidelines,         I this uncertainty was taken as 5% of the reactivity decrement from beginning oflife to the burnup ofinterest.
Results of the analysis confimi that, for the existing Technical Specification limits, there is sufficient margin in both Region 1 and Region 2 of the CR3 Pool B storage racks to accommodate both the potential gaps in the Boraflex and the concurrent loss of up to 20%
Botaflex is now known to degrade under the influence of gamma radiation and chemical reaction with free radicals in the pool water. Over the first few years of use, the Boraflex will shrink, creating gaps distributed randomly in the axial direction. Over later years, as the gamma dose increases, the Boraflex panels will slowly begin to deteriorate, losing the neutron absorbing component (B4 C). The present analysis conservatively assumes the presence of 4-inch gaps in all Boraflex panels. The potential reactivity consequences of concurrent loss of up to 20% of the Boraflex was also evaluated.
1 Results of the analysis confimi that, for the existing Technical Specification limits, there is sufficient margin in both Region 1 and Region 2 of the CR3 Pool B storage racks to accommodate both the potential gaps in the Boraflex and the concurrent loss of up to 20%
Holtec Report 111-982056 2-
Holtec Report 111-982056 2-


  , .                                                                                                                  F-084017, Rev. O of the Boraflex absorber material. In addition, Region 2 was evaluated with a 3-of-4 loading pattern, showing that, for this configuration, a significantly greater reactivity margin is available to accommodate more reactive fuel (lower burnup) or greater BoraSex degradation than is currently anticipated. Accident analyses were also performed, establishing that for the most serious fuel mis-loading accident (Region 2), criticality will not be reached, and that 350 ppm soluble boron is adequate to maintain the maximum k-effective below the regulatory limit. Recent USNRC Guidelines allow partial credit for soluble boron, and this would be more than adequate to protect against the most serious fuel handling accident.
F-084017, Rev. O of the Boraflex absorber material. In addition, Region 2 was evaluated with a 3-of-4 loading pattern, showing that, for this configuration, a significantly greater reactivity margin is available to accommodate more reactive fuel (lower burnup) or greater BoraSex degradation than is currently anticipated. Accident analyses were also performed, establishing that for the most serious fuel mis-loading accident (Region 2), criticality will not be reached, and that 350 ppm soluble boron is adequate to maintain the maximum k-effective below the regulatory limit. Recent USNRC Guidelines allow partial credit for soluble boron, and this would be more than adequate to protect against the most serious fuel handling accident.
fioltec Report iII-982056
fioltec Report iII-982056.


i l
i F-9&co17, gev. O 1
  .      .                                                                                                                                  l F-9&co17, gev. O 1
2.0 ANALYSIS CRITERIA AND ASSUMPTIONS To assure the true reactivity will always be less than the calcalated reactivity, the following conservative analysis criteria or assumptions were used:
2.0         ANALYSIS CRITERIA AND ASSUMPTIONS To assure the true reactivity will always be less than the calcalated reactivity, the following conservative analysis criteria or assumptions were used:
The racks contain the most reactive fuel authorized to be stored, without any control rods or burnable poison.
The racks contain the most reactive fuel authorized to be stored, without any control rods or burnable poison.
The moderator is pure, unborated water at a temperature within the design basis range corresponding to the highest
The moderator is pure, unborated water at a temperature within the design basis range corresponding to the highest reactivity.
,                                                  reactivity.
Criticality safety analyses are based upon an infinite radial array of cells; i.e., no credit is taken for radial neutron leakage.
Criticality safety analyses are based upon an infinite radial array of cells; i.e., no credit is taken for radial neutron leakage.
Neutron absorption in minor structural members is neglected; e.g., spacer grids are replaced by water.
Neutron absorption in minor structural members is neglected; e.g., spacer grids are replaced by water.
The analyses were based on the enrichment-burnup                                           j combinations in the current Technical Specifications and rack design details provided by Florida Power Corporation.
The analyses were based on the enrichment-burnup j
l The analyses assumed fresh Mark B-10F fuel in Region 1 checkerboarded with spent Mark B-10 fuel. Region 2 analyses assumed MARK B-10 fuel except for the accident analysis, which assumed Mark B10F fuel as the offending assembly. These two fuel types boundm all other fuel assemblies used at CR3 and now in storage. The analyses do not include burn B10F fuel.
combinations in the current Technical Specifications and rack design details provided by Florida Power Corporation.
1 Mark B10 and Mark-B10F fuel assemblies have axial i
The analyses assumed fresh Mark B-10F fuel in Region 1 checkerboarded with spent Mark B-10 fuel. Region 2 analyses assumed MARK B-10 fuel except for the accident analysis, which assumed Mark B10F fuel as the offending assembly. These two fuel types boundm all other fuel assemblies used at CR3 and now in storage. The analyses do not include burn B10F fuel.
Mark B10 and Mark-B10F fuel assemblies have axial i
blankets oflow-enriched fuel, which prevents the existence of higher reactivity fuel of lower-than-average burnup at the ends of the assembly. This precludes the penalty due to the axial distribution in burnup that might otherwise occur.
blankets oflow-enriched fuel, which prevents the existence of higher reactivity fuel of lower-than-average burnup at the ends of the assembly. This precludes the penalty due to the axial distribution in burnup that might otherwise occur.
The remaining assumptions are defined in Section 4.0.
The remaining assumptions are defined in Section 4.0.
i Holtec Report HI-982056 i
i Holtec Report HI-982056.
  ..          _ _ - -                                    _ _ . _ _ .    .x_.                ,__    ,,.        - _ . - _ . .
i
.x_.


l' L.- .
l' F-!8 001'/, Rev. O L.-
F-!8 001'/, Rev. O l                                                                                                        l L
l L
l         3.0     ACCEPTANCE CRITERIA
l 3.0 ACCEPTANCE CRITERIA t
,                                                                                                        I t
The CR3 Technical Specifications list the following enrichment-burnup combination limits j
The CR3 Technical Specifications list the following enrichment-burnup combination limits       j for acceptable storage of spent fuel in Pool B. Region 1 assumes 5.0% enriched fuel in a checkerboard pattern, alternating with spent fuel of the enrichment-burnup combination         l listed below. Region 2 assumes all cells filled with spent fuel of the enrichment-burnup combinations listed below.                                                                     I Region 1                             Region 2                         l Enrichment       Burnup,           Enrichment           Burnup,             l
for acceptable storage of spent fuel in Pool B.
                              % U-235       M WDIKau             % U-235           MWD /KgU             j 2.08             0.0               1.63                 0.0 3.00             11.2             2.04                 8.0 4.00           20.2               2.31                 15.0 5.00           30.3               3.20                 25.0 4.07                 35.0 5.20               45.0 Each of these combinations was analyzed with the 3-dimensional KEN 05a code.
Region 1 assumes 5.0% enriched fuel in a checkerboard pattern, alternating with spent fuel of the enrichment-burnup combination listed below. Region 2 assumes all cells filled with spent fuel of the enrichment-burnup combinations listed below.
The primary acceptance criterion is that the maximum k,y shall be less than 0.95, l
Region 1 Region 2 Enrichment
including calculation uncertair. ties and effects of mechanical tolerances. Applicable codes, standards, and regulations, or pertinent sections thereof, include the following:
: Burnup, Enrichment
General Design Criterion 62, Prevention of Criticality in Fuel Storage and   l Handhng.
: Burnup,
% U-235 M WDIKau
% U-235 MWD /KgU j
2.08 0.0 1.63 0.0 3.00 11.2 2.04 8.0 4.00 20.2 2.31 15.0 5.00 30.3 3.20 25.0 4.07 35.0 5.20 45.0 Each of these combinations was analyzed with the 3-dimensional KEN 05a code.
The primary acceptance criterion is that the maximum k,y shall be less than 0.95, including calculation uncertair. ties and effects of mechanical tolerances. Applicable codes, standards, and regulations, or pertinent sections thereof, include the following:
General Design Criterion 62, Prevention of Criticality in Fuel Storage and Handhng.
l USNRC Standard Review Plan, NUREG-0800, Section 9.1.2, Spent Fuel
l USNRC Standard Review Plan, NUREG-0800, Section 9.1.2, Spent Fuel
                                                                                                          ]
]
Storage.                                                                     '
Storage.
Holtec Report HI-982056 l
Holtec Report HI-982056 !
9
l 9


F-984017. Rev. O USNRC letter of April 14,1978, to all Power Reactor Licensees - OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications, including modification {{letter dated|date=January 18, 1979|text=letter dated January 18,1979}}.
F-984017. Rev. O USNRC letter of April 14,1978, to all Power Reactor Licensees - OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications, including modification {{letter dated|date=January 18, 1979|text=letter dated January 18,1979}}.
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L. Kopp, " Guidance On The Regulatory Requirements For Criticality Analysis Of Fuel Storage At Light-Water Reactor Power Plants",
L. Kopp, " Guidance On The Regulatory Requirements For Criticality Analysis Of Fuel Storage At Light-Water Reactor Power Plants",
USNRC Internal Memorandum L. Kopp to Timothy Collins, August 19, 1998 l
USNRC Internal Memorandum L. Kopp to Timothy Collins, August 19, 1998 l
l
i
                                                                .                                                                                1 i
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                                                                                                                                                  )
1 Holtec Repon HI-982056.
l 1
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Holtec Repon HI-982056 e


  -  - - . - . .        ~ . - . - - . - . . - - .- - . -..         -    - - - . . _ - -        . - . - -    -    .      ~. .-
~. -. - -. -.. - -.- -. -..
    ,        ,                                                                                              F-08-0017. Rev. @
~..-
4.0           DESIGN AND INPUT DATA 4.1           Fuel Assembly Desien Specifications Two fuel assembly designs were used in the analyses: the B&W Mark B-10 fuel and the Mark B10F, an enhanced version of the Mark B-10 fuel. Table 4.1 provides the pertinent design details for these assembly types. The Mark B-10 fuel bounds all fuel previously used at CR3m, except the B-10F fuel which was used in the analyses of Region 1 and for all fuel mis-loading accidents. Enrichments used are those specified in the current Technical Specifications. Any boron burnable poison which may be in the fresh fuel assemblies in IFBA rods would reduce reactivity, but was not included in the analyses.
F-08-0017. Rev. @
4.2           Pool B Region 1 Rack Design The nominal spent fuel storage cell used for the criticality analyses of Region I storage cells is shown iri Figure 4.1. The cell is composed of Boraflex absorber material
4.0 DESIGN AND INPUT DATA 4.1 Fuel Assembly Desien Specifications Two fuel assembly designs were used in the analyses: the B&W Mark B-10 fuel and the Mark B10F, an enhanced version of the Mark B-10 fuel. Table 4.1 provides the pertinent design details for these assembly types. The Mark B-10 fuel bounds all fuel previously used at CR3m, except the B-10F fuel which was used in the analyses of Region 1 and for all fuel mis-loading accidents. Enrichments used are those specified in the current Technical Specifications. Any boron burnable poison which may be in the fresh fuel assemblies in IFBA rods would reduce reactivity, but was not included in the analyses.
                                                                                                                                  )
4.2 Pool B Region 1 Rack Design The nominal spent fuel storage cell used for the criticality analyses of Region I storage cells is shown iri Figure 4.1. The cell is composed of Boraflex absorber material
mounted on the outside of a 0.060-inch-thick stainless steel box. The fuel assemblies are                   l centrally located in each storage cell on a nominal lattice spacing of 10.60 inches, with a 1.20-inch water flux-trap between the two (thennal-neutron opaque) Boraflex absorber panels. The Boraflex absorber (as confirmed by measurement of representative coupons) has a thickness of 0.085 inch and a nominal B-10 areal density of 0.0269 g/cm2 (0.023 g/cm2 minimum).
)
4.3           Pool B Region 2 Rack Design In Region 2, the storage cells are composed of a single Boraflex absorber panel between the stainless steel walls of adjacent storage cells. These cells, shown in Figure 4.2, are                   1 Holtec Report HI-982056
mounted on the outside of a 0.060-inch-thick stainless steel box. The fuel assemblies are centrally located in each storage cell on a nominal lattice spacing of 10.60 inches, with a 1.20-inch water flux-trap between the two (thennal-neutron opaque) Boraflex absorber panels. The Boraflex absorber (as confirmed by measurement of representative coupons) has a thickness of 0.085 inch and a nominal B-10 areal density of 0.0269 g/cm (0.023 2
                                                                        . 7 e
2 g/cm minimum).
                                                                                          .-._;c,
4.3 Pool B Region 2 Rack Design In Region 2, the storage cells are composed of a single Boraflex absorber panel between the stainless steel walls of adjacent storage cells. These cells, shown in Figure 4.2, are Holtec Report HI-982056 7
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F-984017, Rey, e -
F-984017, Rey, e -
located on a lattice spacing of 9.17 inches. The Boraflex absorber (as confirmed by the
located on a lattice spacing of 9.17 inches. The Boraflex absorber (as confirmed by the
: measurement of representative samples) has a thickness of 0.058 inch and a nominal B-10 areal density of 0.0134 g/cm2 (minimum of 0.015 g/cm2),
: measurement of representative samples) has a thickness of 0.058 inch and a nominal B-10 2
2 areal density of 0.0134 g/cm (minimum of 0.015 g/cm ),
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F-98-0017. Rev. O 1
F-98-0017. Rev. O 5.0 METHODOLOGY The primary criticality analyses were performed with the three-dimensional NITAWL-KENO 5a Monte Carlo code package. NITAWL was used with the 238-group SCALE-m 4.3 cross-section library and the Nordheim integral treatment for U-238 resonance shielding effects. Benchmark calculations, presented in Appendix A, indicate a bias of 0.0030
5.0     METHODOLOGY The primary criticality analyses were performed with the three-dimensional NITAWL-m KENO 5a Monte Carlo code package         . NITAWL was used with the 238-group SCALE-4.3 cross-section library and the Nordheim integral treatment for U-238 resonance shielding effects. Benchmark calculations, presented in Appendix A, indicate a bias of 0.0030
* 0.0012 (95%/95%)m. Verification calculations for the principal cases were made with the MCNP codeW (bias of 0.0009
* 0.0012 (95%/95%)m. Verification calculations for the principal cases were made with the MCNP codeW (bias of 0.0009
* 0.0011, as shown in Appendix A).                             j CASMO4, a two-dimensional deterministic codem using transmission probabilities, was used to evaluate the small reactivity effects of manufacturing tolerances. Validity of the CASMO4 code was established by comparison with KENO 5a and MCNP calculations.
* 0.0011, as shown in Appendix A).
j CASMO4, a two-dimensional deterministic codem using transmission probabilities, was used to evaluate the small reactivity effects of manufacturing tolerances. Validity of the CASMO4 code was established by comparison with KENO 5a and MCNP calculations.
In the geometric model used in the calculations, each fuel rod and each fuel assembly were explicitly described. The calculational model used a 4x4 array of cells with 4-inch gaps in the Boraflex randomly distributed axially. Reflecting boundary conditions effectively defined an infinite radial array of storage cells. In the axial direction, a 30-cm water reflector was used to conservatively describe axial neutron leakage. Each stainless steel box and all associated Boraflex panels were also explicitly described in the calculational model. The fuel cladding material was conservatively assumed to be zirconium; the actual Zircaloy, with a greater absorption cross-section, would slightly reduce reactivity.
In the geometric model used in the calculations, each fuel rod and each fuel assembly were explicitly described. The calculational model used a 4x4 array of cells with 4-inch gaps in the Boraflex randomly distributed axially. Reflecting boundary conditions effectively defined an infinite radial array of storage cells. In the axial direction, a 30-cm water reflector was used to conservatively describe axial neutron leakage. Each stainless steel box and all associated Boraflex panels were also explicitly described in the calculational model. The fuel cladding material was conservatively assumed to be zirconium; the actual Zircaloy, with a greater absorption cross-section, would slightly reduce reactivity.
Monte Carlo (KENO 5a) calculations inherently include a statistical uncertainty due to the random nature of neutron tracking. To minimize the statistical uncertainty of the KEN 05a calculated reactivities, a minimum of 1 million neutron histories was accumulated in each calculation, generally resulting in a statistical uncertainty of about 0.0006Ak (1 o ).
Monte Carlo (KENO 5a) calculations inherently include a statistical uncertainty due to the random nature of neutron tracking. To minimize the statistical uncertainty of the KEN 05a calculated reactivities, a minimum of 1 million neutron histories was accumulated in each calculation, generally resulting in a statistical uncertainty of about 0.0006Ak (1 o ).
Holtec Report HI-982056 4
Holtec Report HI-982056.
4


F-C8 0017 Rev. O 6.0     ANALYTICAL RESULTS 6.1     Code Comparison Calculations- KENO 5a and MCNP Two independent methods of analyses (KEN 05a and MCNP) were used to verify the reference CASMO4 calculations . In addition, these calculations serve to validate the CASMO4 code, since CASMO4 is a two-dimensional code and cannot be directly l
F-C8 0017 Rev. O 6.0 ANALYTICAL RESULTS 6.1 Code Comparison Calculations-KENO 5a and MCNP Two independent methods of analyses (KEN 05a and MCNP) were used to verify the reference CASMO4 calculations. In addition, these calculations serve to validate the CASMO4 code, since CASMO4 is a two-dimensional code and cannot be directly
      ~ validated against critical experiments. The USNRC guidelines, however, endorse .
~ validated against critical experiments. The USNRC guidelines, however, endorse.
CASMO and KEN 05a as acceptable methods ofcriticality analysis. Results of these code comparison calculations are listed in Table 6.1, corrected for bias. These results are considered to be in reasonable agreement, confirming the basic KEN 05a, MCNP and CASMO calculations.
CASMO and KEN 05a as acceptable methods ofcriticality analysis. Results of these code comparison calculations are listed in Table 6.1, corrected for bias. These results are considered to be in reasonable agreement, confirming the basic KEN 05a, MCNP and CASMO calculations.
      - 6.2     Evaluation of Uncertainti_es Calculations were made to determine the uncertainties in reactivity associated with 1
- 6.2 Evaluation of Uncertainti_es Calculations were made to determine the uncertainties in reactivity associated with 1
manufacturing tolerances. Tolerances that would increase reactivity were calculated; negative values are expected to be of equal magnitude but opposite in sign. Results of
manufacturing tolerances. Tolerances that would increase reactivity were calculated; negative values are expected to be of equal magnitude but opposite in sign. Results of
: these calculations are shown in Table 6.2. The reactivity effect was separately evaluated on a sensitivity study for each independent tolerance, and the results combined statistically.
: these calculations are shown in Table 6.2. The reactivity effect was separately evaluated on a sensitivity study for each independent tolerance, and the results combined statistically.
Tolerances considered include the following:
Tolerances considered include the following:
1
1 Tolerance in Boron loading in the Boraflex, Tolerance in Boraflex panel width, i
                                  - Tolerance in Boron loading in the Boraflex,                       l l
I Tolerance in water gap (Region 1),
                                  . Tolerance in Boraflex panel width,                               i I
k Holtec Report HI-982056 10 -
                                  . Tolerance in water gap (Region 1),                                 !
k Holtec Report HI-982056                                                                         l 10 -
l j
l j
e
e


F 980017, Rev. O
F 980017, Rev. O
                                          . Tolerance in box I.D. or lattice pitch (Region 2),
. Tolerance in box I.D. or lattice pitch (Region 2),
                                          . Tolerance in stainless steel thickness,
. Tolerance in stainless steel thickness,
                                          . Tolerance in fuel enrichment and in UO 2density, and '
. Tolerance in fuel enrichment and in UO density, and '
                                          . Tolerance in depletion calculations.
2
. Tolerance in depletion calculations.
These tolerance effects are relatively insensitive to enrichment or burnup. However, the i
These tolerance effects are relatively insensitive to enrichment or burnup. However, the i
tolerance on fuel enrichment is enrichment-dependent and is included in the summary tables.
tolerance on fuel enrichment is enrichment-dependent and is included in the summary tables.
6.3     Storage Rack Calculations                                                               -
6.3 Storage Rack Calculations 6.3.1 Region 1, Pool B
6.3.1   Region 1, Pool B
. Region 1 of Pool B is designed to accommodate a checkerboard pattern of unburned 5%
                . Region 1 of Pool B is designed to accommodate a checkerboard pattern of unburned 5%
fuel intermixed with fuel of various enrichment-burnup combinations as specified in the
fuel intermixed with fuel of various enrichment-burnup combinations as specified in the
                . Technical Specifications. Calculations for these specified cases are given in Table 6.3.
. Technical Specifications. Calculations for these specified cases are given in Table 6.3.
As shown in the table, the maximum reactivity values are well below the regulatory limit and are therefore acceptable. The highest reactivity occurs for 4.0 % enriched fuel checker-boarded with unburned Mark B-10F fuel of 5.0 % enrichment.
As shown in the table, the maximum reactivity values are well below the regulatory limit and are therefore acceptable. The highest reactivity occurs for 4.0 % enriched fuel checker-boarded with unburned Mark B-10F fuel of 5.0 % enrichment.
6.3.2 Region 2, Pool B - Fully Loaded l-Region 2 of Pool B is designed for fuel of various enrichment-bumup combinations as listed in the Technical Specifications. Calculations for the maximum reactivity for these cases is given in Table 6.4. The highest reactivity occurs for the 2.04 % enriched case, with the 5.2 % enrichment case slightly lower. In all cases the racks can safely I'
6.3.2 Region 2, Pool B - Fully Loaded l-Region 2 of Pool B is designed for fuel of various enrichment-bumup combinations as listed in the Technical Specifications. Calculations for the maximum reactivity for these cases is given in Table 6.4. The highest reactivity occurs for the 2.04 % enriched case, with the 5.2 % enrichment case slightly lower. In all cases the racks can safely I'
accommodate 29% loss of Boraflex thickness (in addition to the 4-inch axial random gaps). Thus, Region 2 of Pool B is acceptable for storage of the Technical Specification
accommodate 29% loss of Boraflex thickness (in addition to the 4-inch axial random gaps). Thus, Region 2 of Pool B is acceptable for storage of the Technical Specification
            }4oltec Report HI-982056 -       ,
}4oltec Report HI-982056 -
l                     _.                             l         l
l _.
l l


- -                                                                                    F-28-0017, Rev. O fuel, with some margin remaining.
F-28-0017, Rev. O fuel, with some margin remaining.
6.3.3   Region 2, Pool B - 3 of 4 Loading Pattern l
6.3.3 Region 2, Pool B - 3 of 4 Loading Pattern The potential effect of a 3-of-4 loading pattern was also evaluated as an alternative loading pattern. Results are given in Table 6.5 and shows that a very substantial margin below the regulatory limit exists for this pattern.
The potential effect of a 3-of-4 loading pattern was also evaluated as an alternative l
6.4 Abnormal and Accident Conditi2n1 The potential effect of abnormal and accident conditions were also considered as indicated in Table 6.6. Only the case of a mis-loaded fuel assembly was found to have more than a negligible impact. The mis-loading of a unburned Mark B-10F assembly into a Region I cell intended for spent fuel did not result in a k-effective that exceeded the 0.95 limit. In Region 2, however, the inadvertent loading of an unburned Mark B-10F assembly of 5.0% enrichment into an otherwise fully loaded rack, could potentially exceed the regulatory limit on k-effective, although criticality would not be reached. For this condition, calculations indicate that credit for 350 ppm soluble baron would maintain the maximum reactivity below the regulatory limit. A lower concentration would be required for protection in the 3 of 4 loading pattern so the fully loaded case (350 ppm) is controlling.
loading pattern. Results are given in Table 6.5 and shows that a very substantial margin 1
below the regulatory limit exists for this pattern.
l l
6.4     Abnormal and Accident Conditi2n1 The potential effect of abnormal and accident conditions were also considered as indicated in Table 6.6. Only the case of a mis-loaded fuel assembly was found to have more than a negligible impact. The mis-loading of a unburned Mark B-10F assembly into a Region I cell intended for spent fuel did not result in a k-effective that exceeded the 0.95 limit. In Region 2, however, the inadvertent loading of an unburned Mark B-l 10F assembly of 5.0% enrichment into an otherwise fully loaded rack, could potentially exceed the regulatory limit on k-effective, although criticality would not be reached. For this condition, calculations indicate that credit for 350 ppm soluble baron would maintain the maximum reactivity below the regulatory limit. A lower concentration would be required for protection in the 3 of 4 loading pattern so the fully loaded case (350 ppm) is controlling.
Temperature effects were also evaluated in the temperature range from 4'C to 120*C.
Temperature effects were also evaluated in the temperature range from 4'C to 120*C.
Results, given in Table 6.7 show that the temperature coefficient of reactivity is negative and that 4*C (maximum water density) corresponds to the highest reactivity.
Results, given in Table 6.7 show that the temperature coefficient of reactivity is negative and that 4*C (maximum water density) corresponds to the highest reactivity.
Line 261: Line 286:
F-C8 0017 Rev. O
F-C8 0017 Rev. O


==7.0     REFERENCES==
==7.0 REFERENCES==
 
l 1.
l                             1.             W.A. Witkopf and L.A. Hassler, " Crystal River Unit 3 Spent Fuel Storage Pool Criticality Analysis", BAW-2209, Revision 1, February 1995.
W.A. Witkopf and L.A. Hassler, " Crystal River Unit 3 Spent Fuel Storage Pool Criticality Analysis", BAW-2209, Revision 1, February 1995.
: 2.               R.M. Westfall, et. al.,"NITAWL-S: Scale System Module for Performing Resonance Shielding and Working Library Production"in SCALE A Modular Code System for Performing Standardized Comouter Analyses for Licensing Evaluation.. NUREG/CR-0200,1979.
2.
R.M. Westfall, et. al.,"NITAWL-S: Scale System Module for Performing Resonance Shielding and Working Library Production"in SCALE A Modular Code System for Performing Standardized Comouter Analyses for Licensing Evaluation.. NUREG/CR-0200,1979.
L.M. Petrie and N.F. Landers," KENO Va. An improved Monte Carlo Criticality Program with Subgrouping"in SCALE: A Modular Code System for Performinsz Standardized Computer Analyses for Licensing Evaluation., NUREG/V-0200,1979.
L.M. Petrie and N.F. Landers," KENO Va. An improved Monte Carlo Criticality Program with Subgrouping"in SCALE: A Modular Code System for Performinsz Standardized Computer Analyses for Licensing Evaluation., NUREG/V-0200,1979.
: 3.             M.G. Natrella, Exoerimental Statistics, National Bureau of Standards, Handbook 91, August 1963.
3.
l
M.G. Natrella, Exoerimental Statistics, National Bureau of Standards, Handbook 91, August 1963.
: 4.             J.F. Briesmeister, Ed., "MCNP - A General Monte Carlo N-Particle Transport Code, Version 4A", Los Alamos National Laboratory, LA-12625-M (1993).
l 4.
: 5.             A. Ahlin, M. Edenius, H. Haggblom, "CASMO- A Fuel Assembly Burnup Program," AE-RF-76-4158, Studsvik report (proprietary).
J.F. Briesmeister, Ed., "MCNP - A General Monte Carlo N-Particle Transport Code, Version 4A", Los Alamos National Laboratory, LA-12625-M (1993).
A. Ahlin and M. Edenius, "CASMO- A Fast Transport Theory Depletion -
5.
A. Ahlin, M. Edenius, H. Haggblom, "CASMO-A Fuel Assembly Burnup Program," AE-RF-76-4158, Studsvik report (proprietary).
A. Ahlin and M. Edenius, "CASMO-A Fast Transport Theory Depletion -
Code for LWR Analysis," ANS Transactions, Vol. 26, p. 604,1977.
Code for LWR Analysis," ANS Transactions, Vol. 26, p. 604,1977.
D. Knott,"CASMO4 Benchmark Against Critical Experiments",
D. Knott,"CASMO4 Benchmark Against Critical Experiments",
Line 276: Line 304:
I M. Edenius et al., "CASMO4, A Fuel Burnup Program, Users Manual" Studsvik Report SOA/95/1.
I M. Edenius et al., "CASMO4, A Fuel Burnup Program, Users Manual" Studsvik Report SOA/95/1.
l I
l I
Holtec Report HI-982056 e
Holtec Report HI-982056.
1     _                            . . . .          -.      -        - - - ,  -      .            -. . . - .
e 1


i F-28 0017, Rey, c         1 1
i F-28 0017, Rey, c Table 4.1 DESIGN BASIS FUEL ASSEMBLY SPECIFICATIONS l~
1 Table 4.1 1
l FUEL ROD DATA MARK B10 MARK B10F Outside diameter, in.
l DESIGN BASIS FUEL ASSEMBLY SPECIFICATIONS                                               I I
0.4300 0.428 Cladding inside diameter,in.
l~
0.3770 0.382 Cladding Material Zr-4 Stack density, gms UO /cc 10.208 10.522 2
l FUEL ROD DATA                     MARK B10                                     MARK B10F Outside diameter, in.             0.4300                                         0.428 Cladding inside diameter,in.       0.3770                                         0.382 Cladding Material                                                   Zr-4 l
-1 Pellet diameter, in.
Stack density, gms UO2 /cc         10.208                                 .      10.522             ,
0.3700 0.3742 l
                                                                                                                      -1 Pellet diameter, in.               0.3700                                         0.3742 Maximum enrichment, wt. %                                   5.00
Maximum enrichment, wt. %
5.00
* 0.05 l
* 0.05 l
l                  U-235                                                                                                 i I
U-235 l
l                  FUEL ASSEMBLY DATA Fuel rod array                                                   15 x 15 l                 Number of fuel rods                                                 208 l
FUEL ASSEMBLY DATA Fuel rod array 15 x 15 l
Fuel rod pitch, in.                                                 0.568 Number of control rod guide                                           17 and instrument thimbles l                   Thimble O.D., in. (nominal)       0.530                                         0.528 l
Number of fuel rods 208 l
l Thimble I.D., in. (nominal)       0.498                                         0.500 Holtec Report HI 982056 4
Fuel rod pitch, in.
0.568 Number of control rod guide 17 and instrument thimbles l
Thimble O.D., in. (nominal) 0.530 0.528 l
l Thimble I.D., in. (nominal) 0.498 0.500 Holtec Report HI 982056 4


  ~ . - . .     _ . ._ . _ _ _-_ _ .. ._._ .__ _ ._ y .. _ . _ . _ .. _ .. __                                   . - . . . _ , . .                _ _ _ . . _ _ - _-
~. -..
'"                                                                                                                                p.C8 0017. Rev. C Table 6.1 i-COMPARISON OF CALCULATIONS Case                                   CASMO                                     KENO
_.._. _ _ _-_ _..._._.__ _._ y.. _. _. _.. _.. __
p.C8 0017. Rev. C Table 6.1 i-COMPARISON OF CALCULATIONS Case CASMO KENO
* MCNP*
* MCNP*
: 1) Reg' I   all 5% fuel, k.                     0.9589                 0.9570
: 1) Reg' I all 5% fuel, k.
* 0.0014                 0.9541         0.0014
0.9589 0.9570
: 2) Reg 1     all 2.08% E                         0.7854                 0.7834
* 0.0014 0.9541 0.0014
* 0.0014                 0.7817
: 2) Reg 1 all 2.08% E 0.7854 0.7834
* 0.0014 0.7817
* 0.0014
* 0.0014
: 3) Reg 1     Checkerboard,                               -
: 3) Reg 1 Checkerboard, 0.8860 0.0014.
0.8860 0.0014.                 0.8823
0.8823
* 0.0014 l-                                           5% & 2.08%
* 0.0014 l-5% & 2.08%
l l                               4) Reg 2     1.63%E (4 of 4)                     0.9099                 0.9136
l l
* 0.0014                 0.9160
: 4) Reg 2 1.63%E (4 of 4) 0.9099 0.9136
* 0.0014-
* 0.0014 0.9160
: 5) Reg 2     1.63% (3 of 4)                               -
* 0.0014-0.8088
0.8088
* 0.0014 0.8165 0.0014
* 0.0014                0.8165 0.0014
: 5) Reg 2 1.63% (3 of 4)
* Includes Bias Holtec Report HI-982056 15 -
* Includes Bias Holtec Report HI-982056 15 -
  ,,                                                                                                                                  ~
~
                      #                            6
6 w
          - w    f-- -rw,c.   .c- .-      ,r-         e           v.,- -.-,  ,4-,r.         --  -,--.--.+------e--                 - --                    ,-v
f--
-rw,c.
.c-
,r-e v.,-
,4-,r.
-,--.--.+------e--
,-v


F-30017, gey, g I
F-30017, gey, g I
l l
l l
Table 6.2                                                     ;
Table 6.2 REACTIVITY UNCERTAINTIES DUE TO MANUFACTUIUNG TOLERANCES (Limiting Reactivity Cases)
REACTIVITY UNCERTAINTIES DUE TO                                                         l MANUFACTUIUNG TOLERANCES (Limiting Reactivity Cases)
Region 1 Quantity Nominal Value Tolerance g
Region 1 Quantity                               Nominal Value                 Tolerance                 g                 l Boron loading                           0.0269 g/cm2
Boron loading 0.0269 g/cm
* 0.0039 g/cm 2
* 0.0039 g/cm
* 0.0041 Boraflex width                         7.500 inches
* 0.0041 2
2 Boraflex width 7.500 inches
* 1/16 inches
* 1/16 inches
* 0.0011             I Water Gap                               1.20 inches
* 0.0011 Water Gap 1.20 inches
* 0.088 inches
* 0.088 inches
* 0.0097 Cell Box I.D.                           9.00 inches
* 0.0097 Cell Box I.D.
* 0.088 inches               0.0020 SS thickness                             0.060/0.020
9.00 inches
* 0.006 inches               0.0002 Statistical combination of                                                                     0.0108 tolerance uncertainties Fuel enrichment                       @ 2.08% U-235
* 0.088 inches 0.0020 SS thickness 0.060/0.020
* 0.05% U-235                 0.0055             l Fuel density                           10.208 g/cm     2
* 0.006 inches 0.0002 Statistical combination of 0.0108 tolerance uncertainties Fuel enrichment
* 0.20 g/cm 2 0.0019             l Region 2 Ouantity                               Nominal Value                 Tolerance                 Ak Baron loading                         0.0184 g/cm2
@ 2.08% U-235
* 0.05% U-235 0.0055 Fuel density 10.208 g/cm
* 0.20 g/cm 0.0019 2
2 Region 2 Ouantity Nominal Value Tolerance Ak 2
Baron loading 0.0184 g/cm
* 0.0034 g/cm
* 0.0034 g/cm
* 0.0088 Boraflex width                         7.600 inches                 1/16 inches             0.0014 Min. Pitch                             9.17 inches                 0.120 inches
* 0.0088 Boraflex width 7.600 inches 1/16 inches 0.0014 Min. Pitch 9.17 inches 0.120 inches
* 0.0069 SS thickness                           0.060/0.0020
* 0.0069 SS thickness 0.060/0.0020
* 0.008 inches               0.0004 Statistical combination of
* 0.008 inches 0.0004 Statistical combination of
* 0.0113 tolerance uncertainties Fuel enrichment                       @ 2.04% U-235
* 0.0113 tolerance uncertainties Fuel enrichment
@ 2.04% U-235
* 0.05% U-235
* 0.05% U-235
* 0.0073 Fuel density                           10.208 g/cm 2                  0.20 g/cm 2            0.0009
* 0.0073 2
2 Fuel density 10.208 g/cm 0.20 g/cm 0.0009
* Most conservative values used (fresh fuel).
* Most conservative values used (fresh fuel).
Holtee Report HI-982056 m                               -.
Holtee Report HI-982056.
m


l s
l s
F-28-0017, Rev. C Table 6.3                                             l RE ACTIVITY  
F-28-0017, Rev. C Table 6.3 RE ACTIVITY  


==SUMMARY==
==SUMMARY==
 
REGION 1 (checkerboard w/5%E fuel)
REGION 1 (checkerboard w/5%E fuel) l Enrishment Chkbd         2.08           3.0             4.0       5.0                   )
Enrishment Chkbd 2.08 3.0 4.0 5.0 w!5*4 TentP-4*C 4*C 4C 4*C B"f"?
w!5*4 TentP-             4*C           4*C             4C         4*C B"f"?                 0           11.2           .20.2       30.3 ht% Dikgu CASNt04 Case         F1-ENR       F1 B30           F1-B40     F1-B50 Reference k-inf.     0.7877       0.7847           0.7902     0.7853 KENp/             0.1068       0.1068           0.1068     0.1068 CAShtO Corr.
0 11.2
Yac'"-       0.0014         0.0014
.20.2 30.3 ht% Dikgu CASNt04 Case F1-ENR F1 B30 F1-B40 F1-B50 Reference k-inf.
* 0.0014       0.0014                 l in corr.
0.7877 0.7847 0.7902 0.7853 KENp/
0.1068 0.1068 0.1068 0.1068 CAShtO Corr.
Yac'"-
0.0014 0.0014
* 0.0014 0.0014 in corr.
KsO5 statistics
KsO5 statistics
* 0.0007         0.0007
* 0.0007 0.0007
* 0.0007     0.0007 Niechanical
* 0.0007 0.0007 Niechanical
* 0.0108         0.0108           0.0108
* 0.0108 0.0108 0.0108
* 0.0108 Tolerances 0.0058       0.0058
* 0.0108 Tolerances EtjhmeN 0.0058 0.0058
* 0.0058       0.0058
* 0.0058 0.0058 Depletion Uncert.
                        ,EtjhmeN Depletion Uncert.         0           0.0041           0.0066     0.0087 T tai unun
0 0.0041 0.0066 0.0087 T tai unun
* 0.0124         0.0130         *0.0140       0.0151 Reactivio         0.8945
* 0.0124 0.0130
* 0.8915           0.8970     0.8921 0.0124           0.0130           0.0140     0.0I51 N'"i"*m           0.9069       0.9045           0.9110     0.9072 Reactivity
*0.0140 0.0151 Reactivio 0.8945
                      ">5m "             0.9079       0.9055           0.9120     0.9082
* 0.8915 0.8970 0.8921 0.0124 0.0130 0.0140 0.0I51 N'"i"*m 0.9069 0.9045 0.9110 0.9072 Reactivity
                      "''0 " oS5         0.9095         0.9071           0.9136     0.9098 w/is m os5         0.9115       0.9091           0.9156     0.9118
">5m "
                      "'2 0* o "         0.9138       0.9114           0.9179     0.9141 KENO-CASMO correction includes temperature correction to 4'C, the KENO bias, and the reactivity facts for checkerboarding with 5% fuel.
0.9079 0.9055 0.9120 0.9082
"''0 " oS5 0.9095 0.9071 0.9136 0.9098 w/is m os5 0.9115 0.9091 0.9156 0.9118
"'2 0* o "
0.9138 0.9114 0.9179 0.9141 KENO-CASMO correction includes temperature correction to 4'C, the KENO bias, and the reactivity facts for checkerboarding with 5% fuel.
Conservative values for fresh fuel used.
Conservative values for fresh fuel used.
Holtec Report HI-982056 9
Holtec Report HI-982056 -
e
9 e


F-284017. Rev. O Table 6.4 REACTIYlTY SU3131ARY REGION 2 (Fully Loaded)
F-284017. Rev. O Table 6.4 REACTIYlTY SU3131ARY REGION 2 (Fully Loaded)
Enrichment           1.63   2.04         2.31         3.20       4.07       5.20 Temp-               4*C     4C           4C           4*C       4*C         4*C sumup.               0       8           15             25         35         45 MWDA.gu Reference k.inf   0.9128   0.9114     0.8861         0.8977     0.8976     0.9095 KENO / CASMO     0.0049   0.0049     0.0049         0.0049     0.0049     0.0049 Corr.
Enrichment 1.63 2.04 2.31 3.20 4.07 5.20 Temp-4*C 4C 4C 4*C 4*C 4*C sumup.
y,n","; 0.0013   0.0013
0 8
* 0.0013         0.0013     0.0013
15 25 35 45 MWDA.gu Reference k.inf 0.9128 0.9114 0.8861 0.8977 0.8976 0.9095 KENO / CASMO 0.0049 0.0049 0.0049 0.0049 0.0049 0.0049 Corr.
* 0.0013 Mechanical   0.0120
y,n",";
0.0013 0.0013
* 0.0013 0.0013 0.0013
* 0.0013 Mechanical 0.0120
* 0.0113
* 0.0113
* 0.0106         0.0098   0.0091   *0.0083 Tolerances Enrichment   0.0095     0.0074
* 0.0106 0.0098 0.0091
* 0.0062         0.0036
*0.0083 Tolerances Enrichment 0.0095 0.0074
* 0.0026       0.0029
* 0.0062 0.0036
              & Dens Tol De nI j a     0     0.0039     0.0069         0.0106     0.0135     0.0153 Totai uncert     0.0154     0.0141     0.0141
* 0.0026 0.0029
& Dens Tol De I j a 0
0.0039 0.0069 0.0106 0.0135 0.0153 n
Totai uncert 0.0154 0.0141 0.0141
* 0.0149
* 0.0149
* 0.0165     0.0177 Reactivity       0.9177 0.9163       0.8910       0.9026     0.9025     0.9144
* 0.0165 0.0177 Reactivity 0.9177 0.9163 0.8910 0.9026 0.9025 0.9144
                        *0.0154     0.0141     0.0141         0.0149
*0.0154 0.0141 0.0141 0.0149
* 0.0165     0.0177 Muimum           0.9331   0.9304     0.9051         0.9175   0.9190     0.9321 Reactivity w/5% ion         0,9354   0.9327     0.9074         0.9198     0.9213     0.9344
* 0.0165 0.0177 Muimum 0.9331 0.9304 0.9051 0.9175 0.9190 0.9321 Reactivity w/5% ion 0,9354 0.9327 0.9074 0.9198 0.9213 0.9344
        "'IO% 3o5$       0.9367   0.9340     0.9087         0.9211     0.9226     0.9357 wrisn ioss       o,9395   0.9278     0.9115         0.9239     0.9254     0.9385 w/20% io"         0.9410   0.9383     0.9130         0.9254     0.9269     0.9400 Holtec Report Hl 982056 l                          .
"'IO% 3o5$
0.9367 0.9340 0.9087 0.9211 0.9226 0.9357 wrisn ioss o,9395 0.9278 0.9115 0.9239 0.9254 0.9385 w/20% io" 0.9410 0.9383 0.9130 0.9254 0.9269 0.9400 Holtec Report Hl 982056..
l l
l l
l


                                                                                                  \
\\
    '                                                                                              \
F ".84017. Rev. C
F ".84017. Rev. C Table 6.5 l
\\
REACTIVITY  
Table 6.5 REACTIVITY  


==SUMMARY==
==SUMMARY==
 
REGION 2 (3 of 4 Loading) l
l REGION 2 (3 of 4 Loading) l l
((i[*f,"t 1.63 2.04 2.31 3.20 4.07 5.20 y
((i[*f,"ty          1.63     2.04       2.31         3.20       4.07         5.20 1
T'mp-4*C 4'C 4C 4C 4"C 4*C B3,""g 0
T'mp-4*C       4'C         4C           4C         4"C           4*C     1 B
8 15 25 35 45 C^suo4 cas' F2 ENR F2-B204 F2-B231 F2-B320 F2-B407 F2-B520 In'[''"ek-0.9128 0.9114 0.8861 0.8977 0.8976 0.9095
3,""g                 0         8           15           25         35           45 C^suo4 cas'       F2 ENR   F2-B204     F2-B231       F2-B320   F2-B407       F2-B520 In'[''"ek-         0.9128     0.9114     0.8861       0.8977   0.8976       0.9095
[Q0lg c,,,.
[Q0lg c,,,.       -0.0994   -0.0994     -0.0994       -0.0994   -0.0994       -0.0994
-0.0994
{"['";   i 0.0013     0.0013   i 0.0013         0.0013     0.0013
-0.0994
* 0.0013   l KENO $a 0.0007
-0.0994
* 0.0007       0.0007       0.0007     0.0007
-0.0994
* 0.0007 Statistics Mechanical Tolerances 0.0120     0.0113
-0.0994
-0.0994
{"['";
i 0.0013 0.0013 i 0.0013 0.0013 0.0013
* 0.0013 KENO $a 0.0007
* 0.0007 0.0007 0.0007 0.0007
* 0.0007 Statistics Mechanical 0.0120 0.0113
* 0.0106
* 0.0106
* 0.0098
* 0.0098
* 0.0091         0.0083 EQ;,",      i 0.0095     0.0074     0.0062       0.0036
* 0.0091 0.0083 Tolerances EQ;,"
* 0.0026         0.0029 De letion       0       0.0039     0.0069
i 0.0095 0.0074 0.0062 0.0036
* 0.0106     0.0135       0.0153 Total uncen 0.0154     0.0141     0.0141
* 0.0026 0.0029 De letion 0
* 0.0149     0.0165     *0.0177 Reactivity 0.8134   0.8120     0.7867       0.7983     0.7982       0.8101 0.0154
0.0039 0.0069
* 0.0141       0.0141
* 0.0106 0.0135 0.0153 Total uncen 0.0154 0.0141 0.0141
* 0.0149     0.0165
* 0.0149 0.0165
* 0.0177 M*=m               0.8288 Reactivity 0.8261     0.8008       0.8132     0.8147       0.8278 w/5% io"           0.8306     0.8279     0.8026       0.8150     0.8165       0.8296
*0.0177 Reactivity 0.8134 0.8120 0.7867 0.7983 0.7982 0.8101 0.0154
        */10% 'o"         0.8327     0.8300     0.8047       0.8171     0.8186       0.8317
* 0.0141 0.0141
        *'l 5% 'on         0.8347     0.8320     0.8067       0.8191     0.8206       0.8337
* 0.0149 0.0165
        "'E I"$           0.8367     0.8340     0.8087       0.S211     0.8226       0.8357 l
* 0.0177 M*=m 0.8288 0.8261 0.8008 0.8132 0.8147 0.8278 Reactivity w/5% io" 0.8306 0.8279 0.8026 0.8150 0.8165 0.8296
l     Holtec Report HI-982056 O
*/10% 'o" 0.8327 0.8300 0.8047 0.8171 0.8186 0.8317
*'l 5% 'on 0.8347 0.8320 0.8067 0.8191 0.8206 0.8337
"'E I"$
0.8367 0.8340 0.8087 0.S211 0.8226 0.8357 l
l Holtec Report HI-982056 -
O


F-9&4017, Rey, g .
F-9&4017, Rey, g.
Table 6.6 REACTIVITY EFFECTS OF ABNORMAI, AND ACCIDENT CONDITIONS                                                 ,
Table 6.6 REACTIVITY EFFECTS OF ABNORMAI, AND ACCIDENT CONDITIONS Acciden:/ Abnormal Conditions Reactivity Effect Tempeiature increase Negative Void (Boiling)
Acciden:/ Abnormal Conditions                                             Reactivity Effect Tempeiature increase                                                           Negative Void (Boiling)                                                                 Negative
Negative
                ~ Assembly dropped on top of rack                                             Negligible Seismic movement                                                             Negligible Misplacement of a fuel assembly                           Worst Case Requires minimum 350 ppm soluble boron I
~ Assembly dropped on top of rack Negligible Seismic movement Negligible Misplacement of a fuel assembly Worst Case Requires minimum 350 ppm soluble boron l
                                                                                                                                                ,  l l
l i
i Holtec Repon HI-982056 r
Holtec Repon HI-982056 r e
e
p
                                                              -. ,                ,        p     ,                      --.m.- r     -- ,  -
--.m.-
r


F-08 OO17, Rey, c Table 6.7 EFFECT OF TEMPERATURE AND VOID ON CALCULATED REACTIVITY OF STORAGE RACK Case                                               Incremental Reactivity Change, ak Region 1*                                                 Region 2 4*C (39'F)                                                                                               Reference 20*C (68'F)~ -                              -
F-08 OO17, Rey, c Table 6.7 EFFECT OF TEMPERATURE AND VOID ON CALCULATED REACTIVITY OF STORAGE RACK Case Incremental Reactivity Change, ak Region 1*
0.0011/-0.0014                                               -0.0011 40*C ( 104*F)                               -0.0035/-0.0042                                                 -0.0041 80*C ( 176*F)                               -
Region 2 4*C (39'F)
0.0103/-0.0120                                                 -0.0086             -
Reference 20*C (68'F)~ -
l              120*C (248'F)                               -0.0192/-0.0226                                                 -0.0151 120'C + 10% void                           -  0.0442/-0.0504                                                 -0.0342
0.0011/-0.0014
* Region 1 uses fuel of 5% enrichment burned to 30 MWD /KgU in a checkerboard arrangement with unburned fuel of 5% enrichment. The two values in this column are the temperature effects at 30 MWD /KgU and for unburned fuel, both of which show a negative coeffient of reactivity.
-0.0011 40*C ( 104*F)
-0.0035/-0.0042
-0.0041 80*C ( 176*F) 0.0103/-0.0120
-0.0086 l
120*C (248'F)
-0.0192/-0.0226
-0.0151 120'C + 10% void 0.0442/-0.0504
-0.0342 Region 1 uses fuel of 5% enrichment burned to 30 MWD /KgU in a checkerboard arrangement with unburned fuel of 5% enrichment. The two values in this column are the temperature effects at 30 MWD /KgU and for unburned fuel, both of which show a negative coeffient of reactivity.
i Holtec Report HI 982056 21 -
i Holtec Report HI 982056 21 -
et O
et O
e s
e
-me r--r a -.,
w s
yi--
r-5-
y-mer
--ww-re w -


F-98-0017. Rev. O
F-98-0017. Rev. O
  ._..}._.-._______         ____        7.50 i 0.063" BORAFLEX                           ,_,_ ,_,_,_,_,_,_,,,_,
._..}._.-._______
i I                                             IN 0.120" GAP                                                           i i                                                                                                                                     ;
7.50 i 0.063" BORAFLEX i
i j                         0.085           0.007" THK .0269 0.0039 gmB-10/cm 2 t                                                                                                                      I             .
I IN 0.120" GAP i
p - m - - - mmy
i i
      !         : !  000000000000000l                                                                           '
2 j
                                                                                                                              !              l l O00000000000000 1
0.085 0.007" THK.0269 0.0039 gmB-10/cm I
I                                                                                                  !                  l i         l O00009000000000                                                                       l                 i             l l         l 000000000009000i                                                                          -
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.VOT TO SC.41.E I
Fig. 4.1 REGION 1 FUEL STORAGE CELL
+
:P i
:P i
l Appendix A to Chapter 5                     l of the Holtec Report, HI-98056
Appendix A to Chapter 5 of the Holtec Report, HI-98056
                  " Benchmark Calculations" Provided to FPC as PROPRIETARY.
" Benchmark Calculations" Provided to FPC as PROPRIETARY.
Therefore not included; will be provided or can be viewed on-site upon request.}}
Therefore not included; will be provided or can be viewed on-site upon request.}}

Latest revision as of 21:22, 10 December 2024

Rev 1 to Holtec Rept HI-982056, Reanalysis of Crystal River Pool B Spent Fuel Storage Racks with Boraflex Degradation
ML20155F977
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 10/20/1998
From: Sarah Turner
HOLTEC INTERNATIONAL
To:
Shared Package
ML20155F952 List:
References
CON-80855 F-98-0017-R00, F-98-17-R, HI-982056, HI-982056-R01, HI-982056-R1, NUDOCS 9811060170
Download: ML20155F977 (29)
v • d • e


Text

.___._...

F-28 Ou17, g,y, g R EA N A _YS S 0 7

- E C RYS A R V E R 300_ 3 S 3 Es" TU E _ S"0 RAG E RAC 5m "

0.9079 0.9055 0.9120 0.9082

"0 " oS5 0.9095 0.9071 0.9136 0.9098 w/is m os5 0.9115 0.9091 0.9156 0.9118

"'2 0* o "

0.9138 0.9114 0.9179 0.9141 KENO-CASMO correction includes temperature correction to 4'C, the KENO bias, and the reactivity facts for checkerboarding with 5% fuel.

Conservative values for fresh fuel used.

Holtec Report HI-982056 -

9 e

F-284017. Rev. O Table 6.4 REACTIYlTY SU3131ARY REGION 2 (Fully Loaded)

Enrichment 1.63 2.04 2.31 3.20 4.07 5.20 Temp-4*C 4C 4C 4*C 4*C 4*C sumup.

0 8

15 25 35 45 MWDA.gu Reference k.inf 0.9128 0.9114 0.8861 0.8977 0.8976 0.9095 KENO / CASMO 0.0049 0.0049 0.0049 0.0049 0.0049 0.0049 Corr.

y,n",";

0.0013 0.0013

  • 0.0013 0.0013 0.0013
  • 0.0013 Mechanical 0.0120
  • 0.0113
  • 0.0106 0.0098 0.0091
  • 0.0083 Tolerances Enrichment 0.0095 0.0074
  • 0.0062 0.0036
  • 0.0026 0.0029

& Dens Tol De I j a 0

0.0039 0.0069 0.0106 0.0135 0.0153 n

Totai uncert 0.0154 0.0141 0.0141

  • 0.0149
  • 0.0165 0.0177 Reactivity 0.9177 0.9163 0.8910 0.9026 0.9025 0.9144
  • 0.0154 0.0141 0.0141 0.0149
  • 0.0165 0.0177 Muimum 0.9331 0.9304 0.9051 0.9175 0.9190 0.9321 Reactivity w/5% ion 0,9354 0.9327 0.9074 0.9198 0.9213 0.9344

"'IO% 3o5$

0.9367 0.9340 0.9087 0.9211 0.9226 0.9357 wrisn ioss o,9395 0.9278 0.9115 0.9239 0.9254 0.9385 w/20% io" 0.9410 0.9383 0.9130 0.9254 0.9269 0.9400 Holtec Report Hl 982056..

l l

l

\\

F ".84017. Rev. C

\\

Table 6.5 REACTIVITY

SUMMARY

REGION 2 (3 of 4 Loading) l

((i[*f,"t 1.63 2.04 2.31 3.20 4.07 5.20 y

T'mp-4*C 4'C 4C 4C 4"C 4*C B3,""g 0

8 15 25 35 45 C^suo4 cas' F2 ENR F2-B204 F2-B231 F2-B320 F2-B407 F2-B520 In'["ek-0.9128 0.9114 0.8861 0.8977 0.8976 0.9095

[Q0lg c,,,.

-0.0994

-0.0994

-0.0994

-0.0994

-0.0994

-0.0994

{"['";

i 0.0013 0.0013 i 0.0013 0.0013 0.0013

  • 0.0013 KENO $a 0.0007
  • 0.0007 0.0007 0.0007 0.0007
  • 0.0007 Statistics Mechanical 0.0120 0.0113
  • 0.0106
  • 0.0098
  • 0.0091 0.0083 Tolerances EQ;,"

i 0.0095 0.0074 0.0062 0.0036

  • 0.0026 0.0029 De letion 0

0.0039 0.0069

  • 0.0106 0.0135 0.0153 Total uncen 0.0154 0.0141 0.0141
  • 0.0149 0.0165
  • 0.0177 Reactivity 0.8134 0.8120 0.7867 0.7983 0.7982 0.8101 0.0154
  • 0.0141 0.0141
  • 0.0149 0.0165
  • 0.0177 M*=m 0.8288 0.8261 0.8008 0.8132 0.8147 0.8278 Reactivity w/5% io" 0.8306 0.8279 0.8026 0.8150 0.8165 0.8296
  • /10% 'o" 0.8327 0.8300 0.8047 0.8171 0.8186 0.8317
  • 'l 5% 'on 0.8347 0.8320 0.8067 0.8191 0.8206 0.8337

"'E I"$

0.8367 0.8340 0.8087 0.S211 0.8226 0.8357 l

l Holtec Report HI-982056 -

O

F-9&4017, Rey, g.

Table 6.6 REACTIVITY EFFECTS OF ABNORMAI, AND ACCIDENT CONDITIONS Acciden:/ Abnormal Conditions Reactivity Effect Tempeiature increase Negative Void (Boiling)

Negative

~ Assembly dropped on top of rack Negligible Seismic movement Negligible Misplacement of a fuel assembly Worst Case Requires minimum 350 ppm soluble boron l

l i

Holtec Repon HI-982056 r e

p

--.m.-

r

F-08 OO17, Rey, c Table 6.7 EFFECT OF TEMPERATURE AND VOID ON CALCULATED REACTIVITY OF STORAGE RACK Case Incremental Reactivity Change, ak Region 1*

Region 2 4*C (39'F)

Reference 20*C (68'F)~ -

0.0011/-0.0014

-0.0011 40*C ( 104*F)

-0.0035/-0.0042

-0.0041 80*C ( 176*F) 0.0103/-0.0120

-0.0086 l

120*C (248'F)

-0.0192/-0.0226

-0.0151 120'C + 10% void 0.0442/-0.0504

-0.0342 Region 1 uses fuel of 5% enrichment burned to 30 MWD /KgU in a checkerboard arrangement with unburned fuel of 5% enrichment. The two values in this column are the temperature effects at 30 MWD /KgU and for unburned fuel, both of which show a negative coeffient of reactivity.

i Holtec Report HI 982056 21 -

et O

e

-me r--r a -.,

w s

yi--

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y-mer

--ww-re w -

F-98-0017. Rev. O

._..}._.-._______

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I IN 0.120" GAP i

i i

2 j

0.085 0.007" THK.0269 0.0039 gmB-10/cm I

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l

.VOT TO SC.41.E I

Fig. 4.1 REGION 1 FUEL STORAGE CELL

+

P i

Appendix A to Chapter 5 of the Holtec Report, HI-98056

" Benchmark Calculations" Provided to FPC as PROPRIETARY.

Therefore not included; will be provided or can be viewed on-site upon request.

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