ML20205N029
| ML20205N029 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/12/1999 |
| From: | Peterson S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20205N033 | List: |
| References | |
| NUDOCS 9904160128 | |
| Download: ML20205N029 (4) | |
Text
e-a ntou pg 4
UNITED STATES d
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NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 205$5-0001
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TENNESSEE VALLEY AUTHORITY
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DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 234 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 27,1998, as supplemented by letter dated March 19,1999, 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 Le conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimiu.;io the common defense and security or to the health and safety of the public; and E.
The issuance of this amandment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have beer satisfied.
4 9904160128 990412 PDR ADOCK 05000328 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 pa agraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised
(
through Amendment No.
234, are hereby incorporated in the license. The l
licensee shall operate the facility in accordance with the Technical Specifications.
I 3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
6\\% k.
N Sheri R. Peterson, Chief, Section 2 Project Directorate ll l
Division of Licensing Project Management l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifica' ions i
l Date of issuance:
April 12, 1999 4
l
ATTACHMENT TO LICENSE AMENDMENT NO. 234 EACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment.
number and contain marginal lines indicating the area of change.
REMOVE INSERT 5-4 5-4 3
1
a DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies.
Each assembly shall consist of a matrix of zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material.
Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be R172 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 er analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting ccre regions.
Sequoyah is authorized to place a limited number of lead test assemblies into the reactor, as described in the Framatome Cogema Fuels Report BAW-2328, beginning with the Unit 2 Operating Cycle 10 core.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core rhall contain 53 full length and no part length control rod assemblies.
The full length control rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal values of absorber material chall 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 TEMPERATUR_E 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 the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650'F, except for the pressurizer which is 680*F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 12,612 2 100 cubic feet at a nominal T of 525'F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
SEQUOYAH - UNIT 2 5-4 Amendment No. )T, V7Y, ///, 234 I
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