ML20072F269
| ML20072F269 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/14/1983 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072F272 | List: |
| References | |
| NUDOCS 8303230446 | |
| Download: ML20072F269 (8) | |
Text
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s TENNE 5SEE VALLEY AUTHORITY DOCKET No. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT _TO FACILITY OPERATING LICENSE Anendment No. 26 License No. DPR-77 1.
The Nuclear Regulatory Comnission (the Canmission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 1 3
(the facility) Facility Operating License No. OPR-77 filed by the Tennessee Valley Authority (licensee), dated August 16, 1982, complies with the standards and requiremenM of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; 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 cornmon defense and security or to the health and safety of the public; and E.
The issuance of this anendment is in accordance with 10 CFR Part 61 of the Commission's regulations and all applicable requirements have 1
been satisfied.
l 2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachment to this license amend-nent and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is herehy amended to read as follows:
(2) Technical Specif1 cations l
The Technical Specifications contained in Appendix A, as revised through haendment No. 26, are hereby incorporated into the license.
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. l The licensee shall operate the facility in accordance with the Technical Specifications.
1 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing i,
Attachment:
Appendix A Technical Specification Change Date of Issuance:
March 14, 1983 i.
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ATTACHMENT TO LICENSE AMENOMENT NO. 26 FACILITY OPERATING LICENSE NO. OPR-77 DOCKET NO. 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 area of change.
Amended Page,.
3/4 1-18 i
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REACTIVITY CONTROL SYSTEMS
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POSITION INDICATION SYSTEM-SHUTDOWN l
LIMITING CONDITION FOR OPERATION 7
3.1.3.3 The group demand position indicator shall be OPERABLE and capable of determining within i 2 steps, the demand position for each shutdown or control rod not fully inserted.
APPLICABILITY:
MODES 3*#, 4*# and 5*#.
ACTION:
With less than the above required grcup demand position indicator (s) OPERABLE, immediately open the reactor trip system breakers.
SURVEILLANCE REQUIREMENTS 4.1.3.3 Each of the above required group demand position indicator (s) shall be ' determined to be OPERABLE by movement of the associated control rod at least 10 steps in any one direction at least once per 31 days.
^With the reactor trip system breakers in the closed position.
- See Special Test Exception 3.10.5.
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SEQUOYAH - UNIT 1 3/4 1-18 Amendment No. 26
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TENNESSEE _ VALLEY AUTHORITY DOCKET fl0. 50-328 SEQUOYAH fluCLEAR PLANT, UtilT 2 Af1EftDMErlT TO FACILITY OPEPATIflG LICENSE Amendment No.15 License No. OPR-79 1.
The fluclear Regulatory Comnission (the Commission) has found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 2 (the facility) Facility Operating License No. OPR-79 filed by the Tennessee Valley Authority (licensee), dated August 16, 1982, 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:
B.
The facility will operate in confomity with the license, as amended, the provisions of the Act, and the rules and regulations of the Com-mission; C.
There is reasonable assurance (1) thai, 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 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.
l 2.
Accordingly, the license is hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachnents to this license amendment and paragraph 2.C.(2) of Facility Operating License fic. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment flo.15, are hereby incorporated into the license.
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2 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 Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing
Attachment:
Appendix A Technical Specif1 cation Change Date of Issuance: March o',,
1983 D..
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ATTACHMENT TO LICENSE AMENDHENT NO. 15 FACILITY OPERATING LICENSE NO. OPR-79 t
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 area of change.
Amended 4
Page 3/4 1-18 f
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NRC FORM 318 00@) NRCM ONO OFFICIAL RECORD COPY usom mi-meso
REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM-SHUTDOWN LIMITING CONDITION FOR OPERATION 1
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3.1.3.3 The group demand position indication shall be OPERABLE and capable of 1
determining within i 2 steps the demand position for each shutdown or control rod.not fully inserted.
APPLICABILITY:
MODES 3*#, 4*# and 5*#.
I ACTION:
With less than the above required group demand position indicator (s) OPERABLE, immediately open'the reactor trip system breakers.
1 i
SURVEILLANCE REQUIREMENTS i
I 4.1.3.3 Each of the above required group demand rod position indicator (s) shall be determined to be OPERABLE by movement of the associated control rod at 2
least 10' steps in any one direction at least once per 31 days.
- With the reactor trip system breakers in the closed position.
- See Special Test Exception 3.10.5.
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i SEQUOYAH - UNIT 2 3/4 1-18 Amendment No. 15 i
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