ML19274G116
| ML19274G116 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/01/1979 |
| From: | Gammill W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19274G117 | List: |
| References | |
| NUDOCS 7908290674 | |
| Download: ML19274G116 (7) | |
Text
UNITED STATES p
4 NUCLEAR REGULATORY COMMISSION g
j WASHINGTON, D. C. 20555
('
e S..... +o THE TOLEDO EDISON COMPANY i
AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR p0WER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No.19 License No. NPF 3 1.
The Nuclear. Regulatory Comission (the Comission) has found that:
A.
The application for amendment by The Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated December 19, 1977, as supplemented April 4,1978, June 22,1978, and May 4,1979, 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; 8.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Conrnission; 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 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 Coninission's regulations and all applicable requirements have been satisfied.
2008 250 7908200477T
2e 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.19, are hereby incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Spe,cifications.
.3.
This license amendment is effective as of the date of its issuance.-
FOR THE NUCLEAR REGULATORY COMMISSION LQ6%
William P. Gammill, Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: August 1,1979 2008 251 t
h e
ATTACHMENT TO LICENSE AMENDMENT NO.19 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overicaf pages are also provided to maintain document completeness.
Pages 5-4 i:l 2008 252 s
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DAVIS-BESSE NUCLEAR POWER STATON LOW POPULATON ZONE FIGURE 5. I-2 2008 253 DAVIS-BESSE, UNIT 1 5-3
DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 40 psig and a temperature of 264*F.
5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 177 fuel assemblies with each fuel assembly containing 208 fuel rods clad with Zircaloy -4.
Each fuel rod shall have a nominal active fuel length of 144 inches and contain a maximum total weight of 2500 grams uranium.
The initial core loading shall have a maximum enrichment of 3.0 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 3.3 weight percent U-235.
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 nominal 134 inches of absorber material.
l The APSR's shall contain a nominal 36 inches of absorber material at their lower ends. 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.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system 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.
b.
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.
2008 254 DAVIS-BESSE, UNIT 1 5-4 Amendment No. 7J,1 1
DESIGN FEATURES VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is of 525'F.
12,110 + 200 cubic feet at a nominal T,yg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5. 6.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
AX equivalent to less than or equal to 0.95 when flooded with ubofNedwater,whichincludesaconservativeallowanceof1%
delta k/k for calculation uncertainty.
b.
A rectangular array of stainless steel cells spaced 12 31/32 inches on centers in one direction and 13 3/16 inches on centers in the other direction.
Fuel assemblies stored in the spent fuel pool shall be placed in a stainless steel cell of 0.125 inches nominal thickness or in a failed fuel container.
5.6.1.2 The new fuel storage racks are designed and shall be maintained with:
a.
AK equivalent to less than or equal to 0.95 when flooded with unb8f$tedwater,whichincludesaccnservative allowance of 1%
delta k/k for uncertainties as described in Section 9.1 of the FSAR.
b.
A nominal 21 inch center-to-center distance between fuel assemblies placed in the storage racks.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below 9 feet above the top of the fuel storage racks.
2008 255 DAVIS-BESSE, UNIT 1 5-5 Amendment No.19
DESIGN FEATURES CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 735 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limit of Table 5.7-1, 2008 256 DAVIS-BESSE, UNIT 1 5-6 Amendment No. I 3