ML17255A665
| ML17255A665 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/08/1984 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17255A667 | List: |
| References | |
| NUDOCS 8402100224 | |
| Download: ML17255A665 (6) | |
Text
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'n+**+4'NITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 POCHESTER GAS AND ELECTRIC CORPORATION DOCKET HO. 50-244 R.
E.
GINNA NUCLEAR POWER PLANT AYIENDICENT TO PROVISIONAL OPERATING LICENSE Amendment No.
6O License No.
DPR-18 1.
The Nuclear Regulatory Commission (the Commission) ha's found that:
A.
The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated February 23,
- 1983, as supplemented September 12,
- 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the co+eon 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.
8402100224 840208 PDR ADOCK 05000244 P
= PDR
'I 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 Provisional Operating License No.
DPR-18 is hereby amended to read.as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 60, are hereby incorporated in the license.
The licensee 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 REGULATORY COf1t'IISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 8, 1984 Dennis H. Crutc
- ield, ief Operating Reactors Branch 85 Division of Licensing
ATTACHMENT TO LICENSE ANENDHENT NO, 60 PROVISIONAL OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages contain the captioned amendment number and marginal lines which indicate the area of, change.
PAGES 5.3-1 5.3-2 5.4-1
5.3 Reactor Design Features 5;. 3. 1 Reactor Core The reactor core contains approximately 4 5 metric tons of uranium in the form of uranium dioxide pellets.
The pellets are e ncapsu la te d in 2 irca loy 4 tubing to form fuel rods.
1 7 9 ue 1 rods,
1 6 guide tubes a nd one instrumentation thimble are arranged in a 1 4 x 1 4 array to form a fuel assembly The reactor core is made up of 1 2 1 fuel
( 1 )
assemblies b.
The enrichment of reload fuel shall be no more than 3. 5 weight pe r cent U-2 3 5 for regions delivered prior to January 1,
1 9 8 4
( Reg ion s 1 - 1 5 ),
"4. 2 5 we ight pe r cent U-2 3 5 for regions delivered a fte Ja nu a ry 1, 1 9 8 4, or their equivalents in terms of reactivity.
co There are 29 full-length RCC assemblies in the I
reactor core.
Each RCC assembly contains 16 144 inch lengths of silver-indium-cadmium alloy clad with stainless steel which act as neutron absorbers when inserted into the core. (5) 5.3-1 Amendment No. 3p 6Q
Reactor Coolant S stem a.
The design of the reactor coolant system complies (3) with the code requirements.
b.
All piping, components and supporting structures of the reactor coolant system are designed to Class requirements, and have been designed to withstand:
i.
The design seismic ground acceleration, 0.08g, with stresses maintained within code allowable working stresses.
ii.
The maximum potential seismic ground accelera-tion, 0.2g, acting in the horizontal and vertical directions simultaneously with no loss of function.
c.
The nominal liquid volume of the reactor coolant
- system, at rated operating conditions, is 6236 cubic feet.
- 5. 3-2 Amendment He.
60
5.4 Fuel Stora e
S ecification
- 5. 4.1 The new and spent fuel pit structures are designed to withstand the anticipated earthquake loadings as Class I structures.
The spent fuel pit has a stainless steel liner to ensure against loss of water.
5.4.2 The new and spent fuel storage racks are designed so that it is impossible to insert assemblies in other than the prescribed locations.
The fuel is stored vertically in an array with sufficient center-to-center distance between assemblies to assure K ff ( 0.95 for (1) unirradiated fuel assemblies delivered prior to January 1,
1984 (Region 1-15) containing no more than 39.0 gms U-235 per axial cm, and (2) unirradiated fuel assemblies delivered after January 1,
1984.containing no more than 41.9 gms U-235 per axial cm.
Both cases assume un-borated water used in the pool.
5.4.3 The spent fuel storage pit is filled with borated water at a concentration to match that used in the reactor cavity and refueling canal during refueling operations whenever there is fuel in the pit.
Amendment No. gg, 60