ML20198P353
| ML20198P353 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Oyster Creek |
| Issue date: | 08/30/1984 |
| From: | Scinto J NRC |
| To: | Lombardo J NRC |
| Shared Package | |
| ML20151H203 | List:
|
| References | |
| FOIA-86-26 NUDOCS 8606060292 | |
| Download: ML20198P353 (6) | |
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Note To Jim Lombardo 8/30/84 Oyster Creek:
I still have problems with the environmental part of this package We seem to have two different Environmental Assessments. One a 9 page assessment which provides a lot of information, but does not include the specific pieces required by 51.30 (The need discussion is different froin the proposed register notice EA; the 9 page EA does not discuss 102(2)(e)oruseofresources and does mention other agencies consulted). The second EA is a much smaller discussion for publication in the Register which mentions all the factors called for by 51.30 but provides little discussion of environmental impact.
Using two confusing EA's is not acceptable to me. You can fix the 9 4
page EA to cover the missing points and then all you need to publish is a finding of no significxact impact containing a brief summary of the N
EA's conclusion concerning environd ntal impact. Or you can incorporate the big EA by reference into the brief EA, by changing the Environmental Impacts discussion into an incorporation by reference of the nine page EA along with a brief discussion of what the nine page EA said.
09873 In either of these cases the nine page EA must be " issued" at the same time as the finding of no significant impact ssued.
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,k-msrEa CREsa Numa amEmrING sana PRWISIONAL OPERATING LICEtEE NO. DPR-16 (DOCITf NO. 50-219)
Applicant hereby requests the Comnission to change Provisional Operating License No. DPR-16 and' Appendix A, the Technical Specifications, of this License as follows:
- 1. Sections to be Changed Paragraph 2.B.(2) of the License. Section 5.3 of the Technical Specifications.
- 2. Extent of Garges To modify the provisions for receipt, possession and use of special nuclear material as reactor fuel, and to specify the appropriate storage requirements of reactor fuel.
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- 3. Changes Requested Replace paragraph 2.B(2) of the current Provisional Operating License DPR-16 with the attached paragraph 2.B(2). Ganje Appen31x A of the License as indicated in the attached Technical Specification pe es 5.3-1 and 5.3-2.
- 4. Discussion
%e oyster Creek spent fuel pool is currently licensed for the storage of 1800 spent fuel assemblies. In order to meet storage needs beyond 1985, it is our intent to increase the licensed storage capacity of the spent fuel pool to 2600 assemblies. % e increased capacity would meet anticipated storage requirements through 1992.
%e current storage capacity of the spent fuel pool is based on Amendment No. 78 of the Facility Description and Safety Analysis Report (EDSAR). Our review of Amendment No. 78 indicates that the proposed increase in storage capacity will inpact pool reactivity considerations, pool structural adequacy and the heat load in the pool. Amendment No. 79, dated
, of the FDSAR describes the proposed spent fuel pool modifications and represents the safety evaluation to support the modifications. Technical Specification Gange Request No.111 ensures that spent fuel is stored in conformance with Amendment No. 79 of the FDSAR.
%e proposed modification to paragraph 2.B(2) of the current Provisional Operating License changes the FDSAR reference to Amendment No. 79 of the FDSAR, thereby allowing the storage of 2600 fuel assemblies in the spent fuel pool.
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We have determined that the proposed modification to the spent fuel pool storage racks is acceptable because (1) the structural design is adequate, (2) the new storage racks will prealude criticality for the currently approved Oyster Creek fuel assemblies, (3) the spent fuel pool can be adequately cooled, (4) the modification will be completed i
without damage to stored fuel assemblies sufficient to cause l
criticality and (5) the quality of the human environment will not be We have, therefore, determined that (1) there significantly affected.
is reasonable assurance that the health and safety of the public will not be endangered by operation in the propose manner and (2) such activities will be conducted in compliance with the Comnission's regulations and the issuance of this amendment will not be inimical to the cmmon defense and security or to the health and safety of the public.
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,' s P10 POSED LICENSE CHANGE Pursuant to the Act and 10CFR Part 70, to receive, possess'and use at 2.B(2) any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Facility Description and Safety Analysis Report, as supplemented and amended as of e
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'5.3-1 1
5.3 AUXILIARY B20IPMENT 5.3.1 Fuel Storage A.
Normal storage for unirradiated fuel assemblies is in critically-safe new fuel storage racks in the reactor building storage vault; otherwise, fuel shall be stored in arrays which have a Keff less than 0.95 under optimum corditions of moderation or in NBC-approved shipping containers.
B.
We spent fuel shall be stored in the spent fuel storage facility which shall be designed to maintain fuel in a geometry providing a Koo less than or equal to 0.95.
C.
The fuel to be stored in spent fuel storage facility shall not exceed a maximum average planar enrichment of 3.01 w/o U-235.
D.
Loads greater than the weight of one fuel assembly shall not be moved over stored irradiated fuel in the spent fuel storage l
facility.
1 E.
The 30 ton spent fuel shipping cask shall not be lifted more than
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6 inches above the top plate' of the cask drop protection system.
Vertical limit switches shall be operable to assure the 6 inch vertical limit is met when the cask is above the top plate.
F.
We temperature of the water in the spent fuel storage pool, i
measured at or near the surface, shall not exceed 125'F.
G.
Prior to Cycle 11 operation,10.5 inches of insulation with a thermal conductivity of k=0.02 BrU/FtHr 'F shall be installed at the bottcm surface of the spent fuel pool slab.
1 H.
%e maximum amount of spent fuel assenblies stored in the spent fuel storage pool shall be 2600.
BASIS l
We specification of Koo less than or equal to 0.95 in the spent fuel' storage facility assures an ample margin from criticality. Criticality analysis was performed on the poison racks to insure that a Koo of 0.95 would not be exceeded. We basis for this analysis assumed an average planar lattice enrichment of 3.01 w/o U-235 and includes manufacturing tolerances.
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he effects of a dropped fuel bundle onto stored fuel in the spent fuel storage facility has been analyzed. % is analysis shows that the fuel bundle drop would not cause doses resulting from ruptured fuel pins that exceed 10 CFR 100 limits (1,2,3) and that dropped waste cans will not damage the pool liner.
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5.3-2
'lhe elevation limitation of the spent fuel shipping cask to no more than 6 inches above the top plate of the cask drop protection system prevents loss of the pool integrity resulting from postulated drop accident's. An analysis of the effects of a 100 ton cask drop from 6 inches has been done (4) j which showed that the pool structure is capable of sustaining the loads inposed during such a drop. Limit switches on the crane restrict the elevation of the cask to less than or equal to 6 inches when it is above the top plate.
Detailed structural analysis of the spent fuel pool was performed.using loads resulting from the dead weight of the structural elements, the building loads, hydrostatic loads from the pool water, the weight of fuel and racks stored in the pool, seismic loads, loads due to thermal gradients in the pool floor and walls, and dynamic load from the cask drop accident. %ermal gradients result in two loading conditions; normal operating and the accident conditions with the loss of spent fuel pool cooling. For the normal condition, the containment air tenperature was assumed to vary between 65'F and 110'F while the pool water tenperature varied between 85'F and 125'F. he
- aost severe loading from the normal operating thermal gradient results with containment air tenperature at 65'F and the water temperature at 125'F. Air 1
temperature measurements made during all phases of plant operation in the l
shutdown heat exchanger room, which is directly beneath part of the spent fuel pool floor slab, show that 65'F is the appropriate minha air tenperature.
The spent fuel pool water tenperature will alarm in the control room before r
j the water temperature reaches 120'F.
In order to ensure the section-capacity i
of the fuel pool floor, the tharmal gradient across the slab should not exceed 21'F (6). We installation of insulation at the bottom surface of the spent fuel pool will help control the thermal gradient across the pool floor and j
will ensure the integrity of the slab 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after a loss of fuel pool cooling.
l Results of the structural analysis show that the pool structure is i
structurally adequate for the loadings associated with the normal operation
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and the condition resultirg from the postulated cask drop accident (5). We floor framing was also found to be capable of withstanding the steady state 7
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thermal gradient conditions with the pool water tenperature at 150*F without exceeding ACI Code requirements. %e walls are also r-hle of operation at a steady state condition with the pool water tenperature at 140*F (5).
j Since the cooled fuel pool water returns at the bottom of the pool and i
the heated water is removed from the surface, the average of the surface tercperature and the fuel pool cooling return water is an appropriate estimate of the average bulk temperature, alternately the pool surface tenperature i
could be. conservatively used.
References l
1.
Amend:nent No. 78 to the FDSAR (Section 7) l 2.
Stpplement No.1 to Amendment No. 78 to the FDSAR (Question 12) 3.
Supplement No.1 to Amendment No. 78 of the FDSAR (Question 40) 4.
Supplement No.1 to Amendment No. 68 of the EDSAR.
l 5.
Revision No.1 to Addendum 2 to Supplement No.1 to Amendment No.
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78 of the FDSAR (Questions 5 and 10) l 6.
FDSAR Amendment No.79 i
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