ML20094D223

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Amend 204 to License DPR-79.Amend Modifies License Condition 2.C.(17) by Extending Required Surveillance Interval to 960518 for Surveillance Requirement 4.3.2.1.3 for Certain Specified ESF Response Time Tests
ML20094D223
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 10/30/1995
From: Hebdon F
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20094D230 List:
References
NUDOCS 9511030223
Download: ML20094D223 (3)


Text

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a p uro j

UNITED STATES B

NUCLEAR REGULATORY C'OMMISSION f

WASHINGTON, D.C. 2066&4001

.....,o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SE0V0YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 204 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 May 19, 1995, which was revised by letter dated September 11, 1995, 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 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.

1 9511030223 951030 PDR ADOCK 05000328 P

PDR

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2.

Accordingly, Paragraph 7.C.(17) of Facility Operating License No. DPR-79 is hereby amended to read as follows:

(17)

Surveillance Interval Extension The performance interval for the 36-month surveillance requirements in TS 4.3.2.1.3 shall be extended to May 18, 1996, j

to coincide with Cycle 7 refueling outage.

The extended interval thall not exceed a total of 50 months for the 36-month surveillances.

3.

This license amendment is effective as of its date of issuance, to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION s

/

,Frederick J. Hebdon, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Page 11 of License Date of Issuance: October 30, 1995

  • Page 11 is attached for convenience, for the composite license to reflect this change.

i '

1-s.

Primary Coolant Outside Containment (Section 22.2. III.D.1.1 Prior to exceeding 5 percent power Level, TVA is required to com-plete the leak tests on Unit 2, and results are to i' submitted within 30 days from the completion of the testing.

(17)

Surveillance Interval Extension The performance interval for the 36-month surveillance requirements in TS 4.3.2.1.3 shall be extended to May 18, 1996, to coincide with the Cycle 7 refueling outage. The extended interval shall not exceed a total of 50 months for the 36-month surveillances.

D.

Exemptions from certain r m orements of Appendices G and J to 10 CFR Part 50 are described in the Office of Nuclear Reactor Regulation's Safety Evaluation 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 security 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 l

the regulations of the Commission.

1 l

A temporary exemption from General Design Criterion 57 found in Appendix A to i

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 autti6r4 zed 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 F

outage as discussed in Section 6.2.4 of Supplement 5 to the Safety Evaluation s

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 Conumission-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.!,5 shall be implemented in accordance with the schedule set forth therein.

Amendment No. 65, 162, 170,204

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