ML20210C562
| ML20210C562 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/15/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20210C568 | List: |
| References | |
| NUDOCS 8609180369 | |
| Download: ML20210C562 (8) | |
Text
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50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 45 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-77 filed by the Tennessee Valley Authority (licensee), dated June 22, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; 8
The facility will operate in conformity with the license, as amended, 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 Comnission'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 regulattens and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
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. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 45 are hereby incorporated into the license.
The licensee shall operate the-facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGVLATORY COMMISSION
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3 B. J. Your.gblood, Director PWR Project Directorate _ #4 Divisten of PWR Licensing-A Attachment" Appendix A Technical Specification Changes Date of Issuance: september 15, 1986
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ATTACHMENT TO LICENSE AMENDMENT NO. 45 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET N0. 50-327 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change.
Amended Page 5-4 4
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5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 192 fuel asserablies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4. Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading l
shall have a maximum enrichment of 3.15 weight percent U-235.
Reload fue) shall be similar in physical design to the initial core loading and shall nave a maximum enrichment of 4.0 weight percent U-235.
CONTROL R0D ASSEMBLIES 5.3.2 The reactor core shall 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 shall be 80 percent silver, 15 percent indium and 5 percent cadmfum.
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 speciffid if: Section 5.2 of the FSAR, with allowance for normal degradatior. 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 + 100 cubic feet at a nominal T,yg of 525"F.
I 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
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SEQUOYAH - UNIT 1 5-4 Amendment No. 45 i
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TENNESSEE VALLEY AUTHORITY DOCKET NO.
50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 A"ENDMENT TO FACILITY OPERATING LICENSE Amendment.No. 37 License No. DPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found 'that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. DPR-79 filed by the Tennessee Valley Authority (licensee), dated June 20, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; I
B.
The facility will operate in confonnity with the license, as amended, the provisions of the Act, and the rules and regulations of the Cemission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the publTc, and (ii) that such activities will be conducted in cortpliance 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
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. (2) Technical Specifications The Technical Specifications contain'ed in Appendix A, as revised through Amendment No. 37 are hereby incorporated into the license. ~The licensee shall operate the facility in accordance with the Technical ' Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR' REGULATORY COMMISSION 6\\
B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A Attachment Appendix A Technical Specification Changes Date of Issuance: September-15, 1986 hWR-A PW WR-A P@f(/DPWR-A OGC_/,BJTH PW R-A PWR Muun ah/ rad JH nich cst'ahle
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ATTACHMENT TO LICENSE AMENDMENT NO. 37 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains vertical lines indicating the areas of change.
Amended Page 5-4
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor. core shall contain 193 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy -4.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core l
loading shall have a maximum enrichment of 3.15 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.0 weight percent U-235.
CONTROL ROD ASSEMBLIES
.5.3.2 The reactor core shall 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 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 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 i 100 cubic feet at a nominal T,yg of 525*F.
h5 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. 37 i
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