ML20215D632

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Amends 48 & 40 to Licenses DPR-77 & 79,respectively,changing Tech Specs to Delete Requirement to Perform Airlock Door Seal Leakage Test by Pressure Decay Method for 15 Minutes
ML20215D632
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 10/02/1986
From: Youngblood B
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20215D635 List:
References
NUDOCS 8610140235
Download: ML20215D632 (8)
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 4

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 48 License No. DPR-77 1.

The Nuclear Regulatory Comission (the Comission) 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 May 25, 1984, and supplemented July 11, 1986, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amer.ded (the Act) and the Comission'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 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 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 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-77 is hereby amended to read as follows:

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4 (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 48 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 W\\

B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A Attachment" Appendix A Technical Specification Changes Date of Issuance: October 2, 1986

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ATTACHMENT TO LICENSE AMENDMENT N0. 48 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 a vertical line indicating the area of change.

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

After each opening, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying seal leakage less than or equal to 0.01 L, as determined by precision flow measurements when measured for at least two minutes with the volume between the door seals at a pressure greater than or equal to 6 psig, b.

By conducting an overall air lock leakage test at not less than Pa (12 psig) and by verifying the overall air lock leakage rate is within its limit:#

1.

At least once per six months, and 2.

Prior to establishing CONTAINMENT INTEGRITY if opened when CONTAINMENT INTEGRITY was not required when maintenance has been performed on the air lock that could affect the air lock sealing capability.*

c.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

c The provisions of Specification 4.0.2 are not applicable.

SEQUOYAH - UNIT 1 3/4 6-8 Amendment No. 48

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 40 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 May 25, 1984, and supplemented July 11, 1986, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter 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 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.

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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A 2-(2) Technical Specifications The Technical Specifications contained in Appendix A,' as revised' through Amendment No. 40 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

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ATTACHMENT TO LICENSE AMENDMENT N0. 40 FACILITY OPERATING LICENSE N0. 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 a vertical line indicating the area of change.

Amended Page 3/4 6-8 l

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CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.1.3 Each containment air lock shall be demonstrated OPERABLE:

a.

After each opening, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying seal leakage less than or equal to 0.01 L, as determined by precision flow measurements when measured for at least two minutes with the volume between the door seals at a pressure greater than or equal to 6 psig, b.

By conducting an overall air lock leakage test at not less than Pa (12 psig) and by verifying the overall air lock leakage rate is within its limit:#

1.

At least once per six months, and 2.

Prior to establishing CONTAINMENT INTEGRITY if opened when CONTAINMENT INTEGRITY was not required when maintenance has been performed on the air lock that could affect the air lock sealing capability.*

c.

At least once per 6 months by verifying that only one door in each air lock can be opened at a time.

  1. The provisions of Specification 4.0.2 are not applicable.

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1 SEQUOYAH - UNIT 2 3/4 6-8 Amendment No. 40

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