ML20059L818
| ML20059L818 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/09/1993 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059L822 | List: |
| References | |
| NUDOCS 9311170429 | |
| Download: ML20059L818 (4) | |
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NUCLEAR REGULATORY COMMISSION
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UNITED STATES i
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WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 162 License No. DPR-79 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
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A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 8, 1993, 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 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 I
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.
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ADD K O P
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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 amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 162, are hereby incorporated in the iicense.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION w
L Frederick J. Hebd n, Director Project Directorate 11-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 9, 1993 e
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i ATTACHMENT TO LICENSE AMENDMENT NO.162 i
FACILITY OPERATING LICENSE NO. OPR-79
-i DOCKET NO. 50-328 Revise the Appendix A Technical Specifications by removing the pages 1
identified below and inserting the enclosed pages. The revised pages are i
identified by the captioned amendment number and contain marginal lines 1
indicating the area of change.
REMOVE INSERT I
Operating License, Page 11 Operating License, Page 11 9
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Primary Coolant Outside Containment (Section 22.2. III.D.l.1 Prior to exceeding 5 percent power Level, TVA is required to com-plete the leak tests on Unit 2, and results are to be submitted within 30 days from the completion of the testing.
(17)
Surveillance Interval Extension The performance interval for those surveillance requirements identified in the licensee's request for surveillance interval extension dated September 8,1993, shall be extended to April 15, 1994, to coincide with the Cycle 6 refueling outage. The extended interval shall not exceed a total of 25 months.
D.
Exemptions from certain requirements of Appendices G and J to 10 CFR Part 50 are described in the Office of Nuclear Reactor Regulation's Safety Evaluation i
Report, Supplements No. I and No. 5.
These exemptions are authorized by law and will not endanger life or property or the common defense and secur.ity and are otherwise in the public interest. Therefore, these exemptions are hereby granted.
The facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission.
A temporary exemption from General Design Criterion 57 found in Appendix A to 10 CFR part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluation Report, Supplement No. 5, Section 6.2.4.
This exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest. The exemption, there-fore, is hereby granted and shall remain in effect through the first refueling outage as discussed in Section 6.2.4 of Supplement 5 to the Safety Evaluation Report.
The granting of the exemption is authorized with the issuance of the Facility Operating License.
The facility will operate, to the extent autho-rized herein, in conformity with the application as amended, the provisions of the Act, and the regulations of the Commission.
Additional exemptions are listed in attachment 2.
E.
Physical Protection The Licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revision to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Safeguards Contingency Plan is incorporated into the Physical Security Plan.
The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Sequoyah Physical Security Plan,"
with revisions submitted through November 23, 1987; and "Sequoyah Security Personnel Training and Qualification Plan," with revisions submitted through April 16, 1987.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
Amendment No.
65, 162