ML20077C315
| ML20077C315 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/22/1994 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077C320 | List: |
| References | |
| NUDOCS 9412010138 | |
| Download: ML20077C315 (8) | |
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.S UNITED STATES 5
NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555 4001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 191 License No. DPR-77 1.
The Nuclear Regulatory Commission (the Commission) has found th&t:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 9, 1994, 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 (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 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.
9412010138 941122 PDR ADOCK 05000327 P
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. 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-77 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.191, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is efrective as of its date of issuance, to be implemented within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
.l r-Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation whment:
Changes to the Technical Specifications Date of Issuance: November 22, 1994
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't ATTACHMENT TO LICENSE AMENDMENT NO.191 FACILITY OPERATING LICENSE NO. OPR-77 DOCKET NO. 50-327 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.
REMOVE INSERT 3/4 6-1 3/4 6-1 l
l l
I 4
3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILLTl: MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE0VIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
At least once per 31 days by verifying that all penetrations
- not a.
capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Table 3.6-2 of Specification 3.6.3.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
Perform required visual examinations and leakage rate testing at P, c.
in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions. The maximum allowable leakage rate, L is 0.25% of containment air weight per day at the calculated p, k containment ea pressure P,,12 psig.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the annulus or containment or the main steam valve vaults and are l
locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.
SEQUOYAH - UNIT 1 3/4 6-1 Amendment No. 12, 130, 176, 191 d
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DOCKET NO. 50-328 SE0VOYAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 133 License No. DPR-79 I
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated September 9, 1994, 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.
. 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 amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 183, are hereby incorporated in the license.
The licensee shall operate the facility in &ccordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION Frederick J. Hebd
, 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 22, 1994
ATTACHMENT TO LICENSE AMENDMENT NO. 183 FACILITY OPERATING LICENSE N0. DPR-79 DOCKET N0. 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 captiened amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 6-1 3/4 6-1
w s.
3/4.6 CONTAINMENT SYSTEMS 1
3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE RE0VIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:
a.
At least once per 31 days by verifying that all penetrations
- not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in-Table 3.6-2 of Specification 3.6.3.
b.
By verifying that each containment air lock is in compliance with the requirements of Specification 3.6.1.3.
c.
Perform required visual examinations and leakage rate testing at P,.
in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.
The maximum allowable leakage rate, L is 0.25% of containment air weight per day at the calculated p, k containment ea pressure P,,12 psig.
- Except valves, blind flanges, and deactivated automatic valves which are located inside the annulus or containment or the main' steam valve vaults and are l
locked, sealed or otherwise secured in the closed position. These penetrations shall be verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per.92 days.
.SEQUOYAH - UNIT 2 3/4 6-1 Amendment No. 117, 167, 183