ML20127E357
| ML20127E357 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/12/1993 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127E361 | List: |
| References | |
| NUDOCS 9301190262 | |
| Download: ML20127E357 (8) | |
Text
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UNITED STATES l
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j W ASH.NGToN. D. C. 20555 s%,....j TENNESSEE VALLEY AUTHORIll DOCKET NO. 50-327 1EQUOYAH NUCLEAR PLANT. UNIT _1 AMENDMENT TO FACIllTY OPERATING LICENSE Amendment No. 166 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 2, 1992, complies with the standards and recuirements of the Atomic Energy Act of 1954, as amended (the Act),
anc 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 anu 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 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.
9301190262 930112 PDR ADOCK 05000327 P
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. OPR-77 is hereby
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amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 166, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
a 3.
This license amendment is effective as of its date of issuance, to be i
implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION bad
/Aic Frederick J. He don, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 12, 1993
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ATTACHMENT TO LICENSE AMENDMENT NO.166 E&qlllTY OPERATING LICENSE NO. DPR-77 DOCKET NO. 50-327 Revise the Appendix A Technical Specifications by removing the pages j
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.
BEMOVE INSERT 3/4 9-10 3/4 9-10 l
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T-REFUELING OPERATIONS -
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3/4.9.10 -WATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR-OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of the reactor pressure vessel flange.
APPLICABILITY:
a.
During CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts or, b.
During movement of irradiated fuel assemblies within containment.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all CORE ALTERATIONS and operations involving movement of irradiated fuel assemblies within containment.
SURVEILLANCE REQUIREMENTS 4.9.10 The water: level shall be determined to be at least:its-minimum required depth within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to the start of and at'least once per 24-hours _thereafter during CORE ALTERATIONS and movement of-irradiated fuel assemblies within containment.-
w SEQUOYAH - UNIT 1 3/4 9-10.
Amendment No. 166-
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4 TENNESSEE VALLEY AUlBORLIX DOCKET NO.50-32Q SE000VAH NUCLEAR fLANT. UNIT 2
@ENDMENT TO FAClllTY OPERATlHG LICENSE Amendment No.156 License No. OPR-79 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 2,1992, 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 confomity with the application, the provisions of the Act, and the rules and regulat1ons of the Comission; 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 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.
9 P
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. DPR-79 is hereby g_3 amended to read as follows:
(2) Technical Soecific Ai.gm The Technical Specifications contained in Appendices A and B, as revised through Amendment No.156, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION f
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F*ederick J. He don, Director P.'oject Directorate 11-4 Dhision of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 12, 1993 i
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n ATTACHMENT TO LICENSE AMENDMENT NO. 156 FACILITY 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.
RIBAYE JNSERT 3/4 9-12 3/4 9-12 l
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REFUELING OPERATIONS 3/4.9.10 WATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of the reactor pressure vessel flange.
APPLICABILITY:
a.
During CORE ALTERATIONS, except during latching and unlatching of control rod drive shafts or, b.
During movement of irradiated fuel assemblies within containment.
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all CORE ALTERATIONS and operations involving movement of irradiated fuel assemblies within containment.
SURVEILLANCE REQUIREMENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during CORE ALTERATIONS and movement of irradiated fuel assemblies within containment.
1 SEQUOYAH - UNIT 2 3/4 9-12 Amendment No. 156
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