ML20079M282
| ML20079M282 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/29/1991 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079M284 | List: |
| References | |
| NUDOCS 9111080125 | |
| Download: ML20079M282 (4) | |
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't, jt TOLEDO EDIS0N COMPANY CENTER 10R SERVICE COMPANY JNg THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Ainendment No.166 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric illuminating Company (the licensees) dated May 31, 199), as supplemented August 29 and October 15, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 common 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.
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. NPF-3 is hereby amended to read as follows:
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2 (a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.160, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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/Jon B. Hopkins, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
October 29, 1991 I
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ATTACHMENT TO LICENSE At4ENDf4ENT NO. 166 FAC11.lTY OPERAT1HG LICENSE NO NPF-?
DOCKET NO. 50-346 Replace the following page of the Appendix "A" Technical 'pecifications with the attached page. The revised page is identified by amendment nunber and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
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DAVIS-BESSE NUCLEAR POWER STATK)N LOW POPULATON ZONE FIGURE 5. I-2 DAVIS-BESSE, UNIT 1 5-3
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CESIGN FEATURES _
i DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building in designed and shall be maintained for a i
maximum internal pressure of 40 psig and a temperature of 264*F.
- 5. 3 REACTOR CORE FUEL ASSEMB_L_ljS
! $ 3.1 The reactor core shall contain 177 fuel assemblies.
Each assembly shall consist of a matrix of Zircaloy clad fuel rods with an initidl composition of e
natural or slightly enriched uranium dioxide (U02) as fuel material, with a maximum enrichment of 3.8 weight percent U-235.
Limited substitutions of stain-less steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those-fuel ~ designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all' fuel safety design bases, Each fuel rod-shall have a nominal active fuel length of 144 inche and shall contain a maximum total weight of 2500 grams uranium, i
CONTROL RODS 5.3.2 The reactor core shall contain 53 safety and regulating and 8 axial power shaping (APSR) control rods.
The safety and regulating control rods shall contain a no.ninal 134 inchet of absorber material.
The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium. -All control rods shall be-clad with stainless steel tubing.
The AP$Rs shall contain a nominal 63 inches of absorber material at their lover ends.
The absorber material for the APSRs shall be 100 percent inconel-600.
- 5. 4 REACTOR COOLANT SYSTEM DESIGN PRESSURE _AND TEMPERATURE 5.4.1 The reactor coolant systen is designed and shall be maintained:
a.
In accordance with the code requirements specified in Section 5.2 of the FSAR. with allowance for normal degradation pursuant to applicable Surveillance Requirements.
h.
For a pressure of-2500 psig, and
.c.
For a-temperature of 650'F, except for the pressurizer and.
pressurizer surge line which is 670'F.
7 DAVIS-BESSE, UNIT 1 5-4 Amendment No. JJ.J9,J73,J30,J3E,166 i
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