ML20093N018
| ML20093N018 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/29/1984 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20093N023 | List: |
| References | |
| NUDOCS 8410310225 | |
| Download: ML20093N018 (4) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
k WASHINGTON, D. C. 20555 r
t GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER AND LIGHT COMPANY
~ OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 77 License No. DPR-16 1.
TheNuclearRegulatoryCommission(theCommission)hasfoundthat:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated August 28, 1984 and supplemented Septeraber 7,1984 complies with the standards and re as amended (the Act)quirements of the Atomic Energy Act of 1954, and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operatte in conformity with the application, the provisions of the Act, and the rules and regulations of the Consnission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all appitcable requirements i
have been satisfied.
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. E.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Provisional Operating License t
No. DPR-16 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as. revised through Amendment No. 77. are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATOR COMMISSION
~
John
. Zwolinski, Chief Opera ng Reactors Branch #5 Divisi n of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 29,1984 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 77 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 i
Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised page is identified by the captioned amendment num>er and contains vertical lines indicating the area of change.
Remove Page Replace Page
~ 5.3-1 5.3-1 1
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OFU 5i
.A.'X:LIARY i..: M D -
C. I..'
el St:ra;e A.
- Jor=al' storage fcr unirradiated uel assemblie,s is in critically-safe new fuel storage racks in the reactor building storage vault; otherwise, fuel sna11 De stored in arrays which have a Keff less than 0.95 under optimum conditions of moderation or in riRC-approved shipping containers.
B.
The spent fuel shall be stored in the spent fuel storage facility which shall be designed to maintain fuel in a geometry providing a p Koo less tilan or equal to 0.95.
C.
The maximum U-235 loading in grams of U-235 per axial centimeter of fuel shall not' exceed 15.6 gms U-235/cm.
I D.
Loads. greater than the weight of one fuel assembly shall not be moved
, over stored irradiated fuel in the spent (hel' storage facility..
E. ' The spent fuel' shipping cask shall not be lif ted more than six inches above the top plate of the cask drop protection system.
Vertical limit switches shall be operable to assure the six inch vertical limit is met whEn the cask.is above the top plate of the cask crop protection system.
F. ' The temperature of the water in the' spent fuel storage pool, measured 4
L at or near the surface, shall not exceed 1250F.,
BASIS d-r T'e specification of Koo n 0.95 and the mhx1mdm U-235_ loading ofy 15.6 g'm
^
h U-235/cm.per axial centimeter for fuel in the spent fuel storage faciTity
. assures an ample margin from criticality.
Conservative assumptiens and allowance for tolerances, void effects, calculational uncertainties, pool temperature effects, etc. have been considered i~n the derivation of these limits (1,2). Note that the 15.6 gm U-235/cm.is equivalent to a 3 w/o enrichment. (7)
The 15.6 gm U-235/ct.i is the limit of U.-235 at any plane through the assembly perpendicular to the length of the assembly.
It is to~ assure that possible non-uniform enrichments'along the length of fu,el rods cannot lead to a, critical condition.
The effects of a dropped fuel bundle onto stored fuel in the spent fuel
. storage faci.1,ity has been analyzed.
This analysis shows that the fuel bundle drop would not cause doses resulting from ruptured fuel pins that exceed h; CFR 100 lim.its (3, 4, 5; and tnat drcpped wa'ste cans will nc camage the pool liner.
The elevation limitation of the spent fuel shipping cask to no more than 6 inches above the top plate cf the cask drop protection system preven s loss of i
tne pool integrity resulting from postulated drop accidents.
An analysis of the effects of a 100 toh cask drop from 6 inches has been done (6) which snowed Inat the pool structure is capable of sustaining the loads imposed during such a drop.
t.imit switches on the crane restrict the elevation cf the cast tosE 6 inches when it is above the top plate.
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Amendment No. 72, 7f, 77
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