ML20151G275
| ML20151G275 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/11/1988 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20151G279 | List: |
| References | |
| DPR-16-A-121 NUDOCS 8804190314 | |
| Download: ML20151G275 (5) | |
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GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWEP t. LIGHT COMPANY 00CKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION APENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.121 License No. DPR-16 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.,
(the licensee), dated January 23, 1988, as supplemented March 16, 1988 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regula-tions set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
8804190314 000411 PDR ADOCK 05000219 p
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph ?.C.(2) of Provisional Operating License 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.121, 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 on issuance, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION F. Stolz, Dir or tr ject Directorate I-4 vision of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance: April 11, 1988 l
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ATTACHPENT T0_ LICENSE AMENDMENT NO 121 PROVISIONAL OPERATING LICENSE NO. DPR-16 00CKET N0.__50_21_9 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by anendrent number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain docunent completeress.
Remove Insert Fage 5.3-1 Page 5.3-1 Page 5.3-?
Page 5.3-2 4
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5.3 AUXILIARY EQUIPMENT 5.3.1 Puel Storage A.
2e fuel storage facilities are designed and shall be maintained with a K-effective equivalent to less than or equal to 0.95 including all calculational uncertainties.
B.
Loads greater than the weight of one fuel assetly shall not be moved over stored irradiated fuel in the spent fuel storage facility.
C.
We 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 drop protection system.
D.
2e te@erature of the water in the spent fuel storage pool, measured at or near the surface, shall not exceed 125'F.
E.
Se maxinum amount of spent fuel assenblies stored in the spent fuel storage pool shall be 2600.
BASIS ne specification of a K-effective less than or equal to 0.95 in fuel storage facilities assures an anple margin from criticality. This limit applies to unitradiated fuel in both the dry storage vault and the spent fuel racks as well as irradiated fuel in the spent fuel racks. Criticality analyses were performed on the poison racks to ensure that a K-effective of 0.95 would not be exceeded. The analyses took credit for burnable poisons in the fuel and included manufacturing tolerances and uncertainties as described in Section 9.1 of the FSAR. Calculational uncertainties described in 5.3.1.A are explicitly defined in Reference 7.
Any fuel stored in the fuel storage facilities shall be bounded by the analyses in these reference doctanentu.
Me effects of a dropped fuel bundle onto stored fuel in the spent fuel storage facility have been analyzed. This analysis shcus 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.
ne 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 accidents. An analysis of the effects of a 100 ton cask drop from 6 inches has been done (4) which OYSTER GEEK 5.3-1 Amendment No.: # g, g,121 l
showed that the pool structuro is capablo of sustaining thQ loads imposQd y o,..
during such a drop. Limit saitches on the crane restrict 2he 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 poc1, seismic loads, loads due to thermal gradients in the pool floor and the walls, and dynamic load from the cask drop accident.
Thermal 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 temperature was assumed to vary between 65'F and 110*F while the pool water temperature varied between 85'F and 12G'F.
The most severe loading from the normal operating thermal gradient results with containment air temperatures at 65'F and the water temperature at 125'F. Air temperature measurements made during all phases of plant operation in the shutdown heat exchanger room, which is directly beneath part of the spent fuel pool floor slab, show that 65'F is the appropriate minimum air temperature.
The spent fuel pool water temperature will alarm in the control room before the water temperature reaches 120*F.
Results of the structural analysis show that the pool structure is structurally adequate for the loadings associated with the normal operation and the condition resulting from the postulated cask drop accident (5) (6).
The floor framing was also found to be capable of withstanding the steady state thermal gradient conditions with the pool water temperature at 150*F without exceeding ACI Code requirements.
The walls are also capable of operation at a steady state condition with the pool water temperature at 140*F (5).
Since the cooled fuel pool water returns at the bottom of the pool and the heated water is removed from the surface, the average of the surface temperature and the fuel pool cooling return water is an appropriate estimate of the average bulk temperature; alternately the pool surface temperature could be conservatively used.
References 1.
Amendment No. 78 to FDSAR (Section 7) 2.
Supplement No.1 to Amendment No. 78 to the FDSAR (Question 12) 3.
Supplement No.1 to Amendment 78 of the FOSAR (Question 40) 4 Supplement No. I to Amendment 68 of the FDSAR 5.
Revision No.1 to Addendum 2 to Supplemnt No.1 to Amendment No. 78 of FOSAR (Questions 5 and 10) 6.
FDSAR Amendment No. 79 7.
Criticality Safety Analysis, Oyster Creek High Density Storage Racks With Increased Enrichment Fuel; Southern Science Report No. SS-166, Rev.1; May 1987 OYSTER CREEK 5.3-2 Amendment No. X, 74,121