ML20134G201
| ML20134G201 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/07/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20134G204 | List: |
| References | |
| DPR-16-A-187 NUDOCS 9611130086 | |
| Download: ML20134G201 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. enmaa at 49.....
GPU NUCLEAR CORPORATION l
800 JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 187 License No. DPR-16 i
1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amen'dment by GPU Nuclear Corporation, et al.
(the licensee) dated April 15, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended i
(the Act), and the Comission's rules and regulations set forth l
in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) 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 Commission's regulations and all applicable requirements have been satisfied.
9611130086 961107 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 2.C.(2) of Facility Operating License No. DPR-16 is hereby amended to read as-follows:
i (2)
Technical Snecifications i
The Technical Specifications contained in Appendices A and B, as 1
revised through Amendment No.187, are hereby incorporated in the i
license. GPU Nuclear Corporation shall. operate the facility in accordance with the Technical Specifications.
4 3.
This license amendment is effective as of the date of issuance, to be j
implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION' i
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F. Stolz, Dire or fect Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 7, 1996 i
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ATTACHMENT TO LICENSE AMENDMENT NO.187 FACILITY OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert 5.3-1 5.3-1 5.3-2 5.3-2
5.3 AUXILIARY EOUIPMENT 5.3.1 Fuel Storage A,
The fuel storage facilities are designed and shall be maintained with a K-effective equivalent i
to less than or equal to 0.95 including all calculational uncertainties.
B.
1.
Loads greater than the weight of one fuel assembly shall not be moved over stored i
irradiated fuel in the spent fuel storage facility, except as noted in 5.3.1.B.2.
2.
The shield plug and the associated lifting hardware may be moved over irradiated fuel assemblies that are in a dry shielded canister within the transfer cask in the cask l
drop protection system.
C.
The spent fuel shipping cask shall not be lifted 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.
l D.
The temperature of the water in the spent fuel storage pool. measured at or t. ear the surface.
shall not exceed 125 F.
E.
The maximum amount of spent fuel assemblies stored in the spent fuel storage pool shall be 2M5.
M S.!S The specification of a K-effective less then or equal to 0.95 in fuel stomge facilities assures an ample margin from criticality. This limit applies to unirradiated 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 FSAR Section 9.1.2.3.9. Any fuel stored in the fuel storage facilities shall be bounded by the analyses in these reference documents.
j The effects of a dropped fuel bundle onto stored fuel in the spent fuel storage facility has been analyzed.
This 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.
Administrative controls over crane movements, which include mechanical rail stops, serve to prevent travel of the crane outside the analyzed load path over the cask drop protection system. A safety factor greater than 10 with respect to ultimate strength, and redundant shield plug lift cables provide adequate margin for the shield plug lift. These features, combir'ed with operator training and required inspections, contribute to the determination that dropping the shield plug onto a loaded dry shielded canister in the spent fuel pool is not a credible event.
OYSTER CREEK 5.3-1 Amendment No.: 77,7#,77,171,179,187 i
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a The 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 showed that the pool structure is capable of sustaining the loads imposed 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 elemen", 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 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 125 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 temperatum. The spent fuel pool water temperature will alarm 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 (Sectio'n 7) 2.
Supplement No. I to Amendment No. 78 to the FDSAR (Question 12) 3.
Supplement No. I to Amendment 78 of the FDSAR (Question 40) 4.
Supplement No. I to Amendment 68 of the FDSAR 5.
Revision No. I to Addendum 2 to Supplement No. I to Amendment No. 78 of FDSAR (Questions 5 and 10) 6.
FDSAR Amendment No. 79 7
Deleted OYSTER CREEK 5.3-2 Amendment No. f1f, T77,187