ML20107H021
Text
,:c
,m-Ge9MJ-tsAeAs 9;
t v Y
. ; ch e?,
h ft'l
\\4 Jersey (Central Power & l.ight. Company MADISON AVENUE Al PUNCH !) OWL ROAD
- Monf uGTOWN. N. J.070(
...,.,2 n!.......
A+:
- cene,a!
i.,.
eut,i.e ui.u.n co,oo.ai.on
- September 19, 1975 Mr. Karif it.- Goller, Assistant Director
-for Operaling React ors:
id visiotr of-React or I.icensing lini t ed St ates Nuclear Regulatory Commission liash i ny, ton, 1). C. 20555' fleur Mr.- Galler:
Subject:
Oyst er Creek Nuclear Cencrating Station Docket ? o.
50-219 Spent l'uel Pool Modi fica't i on Plan
.lersey Cent ral Power i 1.inht Company plans to i,erease the st orage capadity of the spent fuel st orage pool at ' the Oyster Creek tinclear Generating St at ion t o ameliorat e a ponsible shortage of spent for t storage capaci ty.
~
This will he done by. replacing the present st orage racG wi th a compact ed fuel rimh ' des ign.
The design concept and criteria for this. modification are atLached.
~
This. desinn is'.in pronress, and its scheduled complet ion date is t he end o f Novet..be r.
1975.
Preparation of informat ion for subm'i t tal to the i;nC for licensinn approval for this modi fication has coneonit ant ly been underway.
On Septenber lo, 1975, th6 NRC gave notice of it s decisir,n to prepare a nenerie envi ronment al impact staten.ent 'on the handling and storage of qient light wat er power reactor fuels.
The Commission also stated t hat
. i nili viitua l licen'.ing review would cont inue "suh icet t n ecrtain condit ions",
and tjiat. any i'ndividual licensinn action intended to ameliorat e a possible shortinge df spent fuel st v ane'would be accompanied by an envi roivaental i ir.pa c t st at ement, or impact appraiv il.
This act ion has raised some (piestions for os ahoot t he. recpai remen t s n.zeenary for prompt licensing action by ti,e NRC for one modi fi cat i on.
in. t he re fore, solicit your cot:went s on the attached design concept.nni sin any other inforuation needed for expedit icus ;ieensing a.:ti.'.
by you.
Unr corrent schechile is for instalIation of some of the coupacted
.fise t s t orage racks duriin; t he 1976 refueling outage (i.e., beginning in April 1975) an i the remainder during the 1977 outage (April, 1977).
To treet r
i 9604240014 960213 m
'PDR w.
o t
J
~ #
H r. (.o l l e r Septembe r !!), !!!75 I
this ;cheihile, your connu nt s are ner d :d by October 21, l'.175.
Should you have any einestionr., please contael Mr. T. J. Madden of our (;cneration liepartuunt staff.
l Thank you for your cooperation.-
Very truly yours,
'l
')('g}l'/t.. i.,
't :i.; -
Ivan IU F i n ffock, J.f r.
Vice President es I
e t
e 9
m
)
4 OYSTER CREEK NUCI. EAR GENERATING STATION SPENT FN L POUI,!!ODIFICATION PLAN The present spent fuel storage capacity at the Oyster Creek Nuclear Generating Station is 840 fuel assemblics. The planned increase, which is discussed below, will provide for a total storage of 1,S40 to 1,760 assemblies.
1.
New Spent Fuel Rack Design The BWR compacted spent fuel rack which Jersey Central Power 5 Light Company plan's to use at the Oyster Creek Nuclear Generating Station to increase spent fuel storage capacity is a modular box structure with spent fuel arranged in slabs (rows of 4 elements each).
The gap between slabs is determined by the material placed in the gap and its arrangement.
Using an all stainless steel construction with no' additional neutron absorber added, a 28-cell spent fuel rack can be provided.
This design will replace the existing 20-element rack presently installed in the spent fuel pool.
The stainless steel boxes or " flux traps" between rows of fuel elements are open at both ends allowing them to fill with fuel pool water.
The stainless steel and water provide the necessary neutron absorption.
Arrangement for this design is shown in Figure 1.
If all existing spent fuel racks'and control rod racks are replaced by the 2S-cc11 rack, an additional 700 spent fuel storage spaces are gained.
If additional spent fuel storage capacity is required, an alternate design is also being considered. The alternate design utilizes the same fuel arrangement as the previously discussed design; however, the rack structural naterial will be aluminum and the removable neutron absorber boxes will be filled with a slab of borated polyethylene. This design allows a closer' i
spacing of spent Tuei rows, increasing storage capacity of the rack to 32 cells.
Ar raanement of the poison fuel rack is shown in Figure 2.
This rack des ig'1 would yield 920 additional storage spaces if all existing spent fuel racb and cont rol rod racks are replaced by the new rack designs.
It is Jersey Central Power 6 Light Company's intention to use either,of the above designs or a combination of both to assure the required spent fuel storage capacity and also to allow unloading of a full reactor core. The racks will be mounted on a support base which will be bolted to the fuel pool floor using the existing tie down bolts. Tentatively,.cach support j
base will accommodate five compacted spent fuel racks; however, should j
the need arise, the support base could be expanded to allow additional racks to be mounted. This would yield a potential to store spent fuel j
in all available areas in the pool, e.g.,
" wall-to-wall".
The racks will be structurally designed to r.cet seismic Categery I require-ments as defined in NRC Regulatory Guide 1.29, August 1973.
In addition, the rack design will meet the requirements of ANSI Standard N16.1-1969,
" Nuclear Crit icality Sa fety in Operations with Fissionable blaterials Outside Reactors"; Safety Guide 13. " Fuel Storage Facility Design Basis";
M
)
^
OYSTER CREEK NUCLF.AR GENERATING STATION
' SPENT FUEL P001-MODIFICATION PLAN l' AGE 2 Safety Guide 25, " Assumptions Used for Evaluating the Potential Radio-logical Consequences 'of a Fuel llandling Accident in the Fuel liandling and Storage Facility for Boiling and Pressurized Water Reactors"; and the applicable parts of ANSI NIS.2.
Completion of the fuel rack design, including :.ssociated procurement-specifientions, is scheduled for the end of November,1975.
It is anticipated that four to six new spent fuel racks can be fabricated by
~ the spring of 1976 in an effort to support the next Oyster Creek refuel-ing outage.
- A preliminary structural review of the Oyster Creek spent fuel pool indicates that there'is' sufficient margin in the design to adequately support the
' additional spent fuel capacity.
Criticality Deslen The primary computer programs which are utilized in the criticality analysis model are the LEOPARD
- and PDQ-?** programs. These programs were derived from or developed under the Naval Reactors Progran and are extensively used iri the' industry for the design and analysis o.f light water reactors. The specific nuclear analysis model used has also been independently te.sted and benchmarked against a series of critical experiments which span the range of design parameters characteristic of the fuel bundles and storag'c racks. The design will meet the applicable parts of ANSI N18.2.
III. Spent Fuel Pool Cooling Capacity Analyses are presently, underway to insure that the cooling capacity of the spent fuel pool is adequate for the heat loads expected for the modified desigt..
- R. F. Bai ry, "LI:0 PARD -- A Spectrum Dependent Non-Spatial Depiction Code for 1101-709.l", WCAP-3269-26, ' Sept., 1963.
- W. R. Cadwell, "PDQ-7 -- Reference Manual," WAPD-TM-678, January,1967.
I i
4 j
=
. ~ _.
i
- o 0
)l
- 3.,
f-8 1
e
.. - ~
y-p g. r- -- *
-~
4
{
l D
t O
I LL.
l l
_. :...6.!.
~],'.
r e u u.._.._ _. : - - 2,,,,, n __,,,,,
..;s.y.
i t
?.-- "'-EY,~5,."~'_: 9
-(=M-c'.t
- - d.
3 s
l 1 l d
j,
(
i
,I
. )'y N'
e
\\.
. r.:. v.r u,, sn.... -..-,
,l
- - ll o
- I 4.s
.l
-l
,)
.L u __
l>
k
. p:
p.
____.._...a-._.
q_._.
(
v., u i
U i_. _ __.____.__ _ _
~
,*.J
,"~..~.5 *m~
8 g
a j,'
k./ )
b ij lI
/
t0 s
_i-
.._ a.- -..
N L. i t
3._.....
.,)
- e w
,u_
l i
- g g y.= : -.= 3.:--
m.-=-_---~..._
-_7 i
i.
e i
g; i
4I
[
i i
g I
d' l. __.
', <.. _ _ _ li......
J,
r Uj t a g--
- m... _...
.. _. a N
x
.1 v3
.,p....
l e.'
T..'~ :
r.
f r d N, l
l m
l
.Il N" O.I l
l i
i
-. p.
t......
_..&w
......a....
s s
g
~....
.s_.
t I*
~79 F f".*'".T 9" T".1 e ~1 * **'t
....y""9,** 4 e*e.er wi_9 s_? Se e a; t* g.a.w... 1,,
f I
a I
am e.
s,
)
3,.-
d
,,,=,w -
,r_
8
~
N i
L e
8 n
1-o.-._
.r
-=
u.
g.-
. _... - ~ ~ =l,l. -
-..J, i
]
1 i
l' l
Y 6
2, I
i.
i
>s m
{
-.- _ i Q
7__.
c
.-..,q
}
f t
, s-g.
D
}
N 1
e
)
.a 6..__._
.. i.:.=. =.,=
~>
Q 1-
.I....___.
..__..} !.-
~
N d
g k
qs.
s iy f
V'
$U U
'l
]
I i
k O
d _ m....._g (3
NL c
e
);
0
,_......__._.____.:.m.__-
(
i
,A j
s.,
1 O
,.. y n
t I
lu.e.
I I
n 1
s-
)
4
}
N
- (
j g
{
s
- (::._._. _. t.. _........s.
i
~.
ll._..._-
s 4.!
h __..=.
- =-
\\
i
-J
- )._.= 3l
/
i
- j i
-G T
i l
b.,
t --
.l
.,)
ILt t
~ ~ '
1
...__;,.._=_--
I -
y
'U-O'.
s L
s, s
s
__....._ l
u..
U)
)
,. _ ~,
i l
l l
s.3 q
~l QN 3
}
l i
- s.,
f l ')
)
ym...
s.
-_... j
~~
l
- 3.. g.
t
. r -
, i..
I g
t
),
I
.h
[
... f;..
n,b _...
.O i.
..l
)
j%
8
==v '
.g.
.. O b' l, '
2 a
4
.. ~ -,
m.-
l gR V
(
{
.d * )
& s
,erSey Central Power & Light Company MADISON AVENUE AT PUNCH BOWL ROAD
- MORRISTOWN, N. J. 07960
- 201-539-6111 es ase or ras ge{, Public Utihties Corporatiori General sesvan September 19, 1975 E,....
e,-
Mr. Karl R. Coller, Assistant Director for Operating Reactors f
Division of Reactor Licensing United States Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Goller:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Spent Fuel Pool Modification Plan
'l Jersey Central Power 6 Light Company plans to increase the storage capacity of the spent fuel storage pool at the Oyster Creek Nuclear Generating Station to ameliorate a possible shortage of spent fuel storage capacity.
This will be done by replacing the present storage racks with a compacted fuel rack design.
The design concept and criteria for this modification are attached.
This design is in progress, and its scheduled cor;1etion date is the end of November,1975.
Preparation of information for submittal to the NRC for licensing approval for this modification has concomitantly been underway. On September 16, 1975, the NRC gave notice of its decision to prepare a generic bnvironmental impact statement on the handling and storage of spent fight water power reactor fuels.. The -Commission also stated that individual licensing reviews would' continue " subject to certain conditions",
and that any individual licensing action intended to ameliorate a possible shortage of spent fuel storage would be accompanied by an environmental impact statement or impact appraisal. This action has raised some questions for us about the requirements necessary for prompt licensing action by the NRC for our modification. We,therefore, solicit your comments on the attached design concept and on any other information needed for expeditious licensing action
/-)
by you.
Our current schedule is for installation of some of the compacted fuel storage racks during the 1976 refueling outage (i.e..beginning in April,1975) and the remainder during the 1977 outage (April,1977).
To meet 4
i g "m -
%o</-2#t'nav 2ep yg
J
(,
)
~
Mr. Goller September 19, 1975 this schedule, your comments are needed by October 24, 1975.
Should.you have any questions, please contact Mr. T. J. Madden of our Generation Department st ff.
Thank you for your cooperation.
Very truly yours, Ush.
I uk./
Ivan R. Finf ek, ' r.
Vice President es 4
8 4
1 h'
..u t t. O, 0 07
. :r/ 3 K.h'C 0,F P2USS:.4, pf, e
6 q
l e
e
~
4 6
4 e
e e
j g
e 9
e i
.