ML19225C893
| ML19225C893 | |
| Person / Time | |
|---|---|
| Site: | 07002623 |
| Issue date: | 05/10/1979 |
| From: | Parker W Duke Power Co |
| To: | Dircks W, Rouse L Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML19225C889 | List: |
| References | |
| NUDOCS 7908030197 | |
| Download: ML19225C893 (4) | |
Text
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Srca= 8.c ou cm o 373-'053 May 10, 1979 p m m cc:c ureNDE.Nci Mr. William J. Dircks, Director Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission p
Washington, D. C.
20555 gg]
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Attention:
Mr. Leland C. Rouse, Acting Chief SN n i 1973 " [
Fuel Reprocessing and Recycle Branch
', 4 4/
Subject:
McGuire Nuclear Station gs Amendment to SNML-1773 4
.,s' Docket No. 70-2623 ru
Dear Mr. Dircks:
As requested 'oy Mr. 3. S. Spitalny of your staff, in a telephone convecsation on May 8, l'979, please find attached our resportse to NRC questions related to the shipment of spen: fuel from Oconee Nuclear Station to McGuire Nuclear Station.
s Very truly yoursl' l
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' William O. Parker, Jr N LJ3/:ch Attachment n
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2 II.)
Vf MAY2 DTED CORRESTTDENCE A
RESPONSES r0 NRC QUESTIONS g
h, 0F MA7 S, 1979 g6 l.
Is PIE equipment located in the Uni: 1 and 2 and/or Uni: 3 spent fuel pool (s)? Hov many fuel assembly spaces are taken up by :his ec,uipment?
If additioncl fuel assembly spaces are being taken up by non-fuel material, provide the number of addi:icnal spaces used and wha: they are being used for.
Will PIE equip =ent be left in :he spent fuel pool?
Can PIE ~ quipment be readily removed free the pool? Will ?II equipment e
be left in the pool if full core discharge capability is lost?
Resconse
.It is considered that the information requested by this questica is not relevan: in this proceeding in tha: current projectiens of the loss of full core discharge capability cre based on the total nunber of fuel assembly spaces located in the spent fuel pcols, i.e.,
for Uni: 1 and 2, 336 spaces and for Unit 3, 474 spaces, for a :otal of 810 spaces at Oconee Nuclear Station.
However, in order to clarify previcus discussions en spent fuel pool spaces which are utiliced for non-fuei =a:erial, and in recognitica of the additional expense which cculd be incurred if this raterial had to be removed, the following infor=atica is provided.
Non-fuel material storage is no
- aken into considera:icn for a.
estimating loss of full core discharge capability.
b.
There is presently no PIE equipment located in the Uni: 1 and 2 er
~ '
Unit 3 spent fuel pools.
c.
PIE equipment is normally installed in the Uni 1 and 2 pool, however, due to preparations for reracking :his equipment has been recoved.
The equipment will be reinstalled after completion of reracking in order to allow centinued Duke par:icipation with the Departmen: cf Energy and Sabccck and Wilecx in evaluating fuel assembly design and burnup.
d.
Twelve :o fcurteen rack spaces are :aken up by the ?II equi; en:
under the current ccafiguratica.
After rerackin;, censidering the closer ccnfiguratica of racks,
. is an:icipated : hat 27 te 35 racks will be utilized.
Additional fuel assembly rack spaces arc being c:i iced for other e.
non-fuel material such as irradia:ed ccepenents, s:ar:up sources, crifice rod cans, etc.
There are, in addi:ian, spaces shich due
- o physical restraints, such as pipin; in the pcci, ::rnc: be utiliced for spen fuel assembly s: crc;e but can be used fer storage of CCn-fuel materials.
Since ncn-fuel T;:eria. is s:cred 7 R 4hllU
')
,90so304 Q
on an as-needed basis, the aumber of spaces utili:ed for non-fuel material s to rage is va riab',c.
Previous estimates have indicatet that with PIE equipment installed and cons tdering the present configuc-ation of spaces in the Unit I and 2 and Unit 3 pools. approximately 47 to 51 spaces would be utili:ed for non-fuel material storage.
It should also be noted that other areas cculd provide storage under abnormal conditions, such as the spent fuel casks, upenders and fuel elevators..However, this tituation is highly undesira'le c
because storage in this manner would preclude use of this equiprent and would require further analysis and approval from the.'!RC.
Taking these facts into consideration, the use of S10 spaces is a close approximation of the spaces which could be made available for fuel assembly storage.
f.
Removal of the PIE equipment from the Unit I and 2 spent fuel pool costs approximately $1SO,J00.
This expense was shared equally by Duke Power and Babcock and Wilcox, cach pay tne $90,000.
Re.aova l required approximately three weeks.
g.
If a full core discharge became necessary at Oconee and the spaces required for the discharge were not available due to the presence of non-fuel materials being stored in the spent fuel pools, then these i ter..: would be removed to the extent necessary to allow the cperation to be completed.
2.
are the Oconee units on an 18-month refueling cycle?
If not, will they be placed on an 18-month refueling cycle? At what time?
Resconse For Oconee Unit 1, the next refueling is scheduled for approximately December, 1979.
This refueling will commence a transition cycle of 15 months.
The next and subsequent cycles are planned to be 13 month cycles.
For oconee Unit 2, the next refueling is scheduled for approximately Ja nua ry-Fe b rua :j, 1930.
This refueling will coa =ence a transitten cycle of 15 months.
The next and subsequent cycles for Unit 2 are planned tu be 13-month cycles.
Oconce Unit 3 is scheduled to remain on an annual refueling cycle.
A decision has not yet been made to place Oconee 3 on an 13-m: nth fuel cycle.
3.
Will the full core discharge capabit.'.y to
- he Lui'..i wen - tact pou!
be lost during this re fuci tng?
Resconse Cuke calculates the loss of full core rescrse by sta-;;n rataer than :n an individual pool basis.
If we were :: calculate f ar 1:ss en an d00 13sR O
individual pool basis, Unit 3 -e ibJ have lost full core discharge capability in June, 1973.
- .t th
- s time, there are 133 assemblies in the Unit 1, 2 pool and with the Unit 3 refuel;ng tnere are '63 assemblies in the Unit 3 spent fuel pool.
With a total capacity of 47a spaces in the Oconee 3 pool, only 11 " empty" spots remain.
However, on a station basis, we have 310 total storage locations.
If we remove 177 from this for a " station FCR," we have a " net" capacity of 633.
Thus, on a statica basis, we have not yet lost FCR because the 601 assemblies present in the spent fuel pools are less than the 633 " net" capacity at Oconee.
M emm 408 136