ML19341C414
| ML19341C414 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/13/1981 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341C415 | List: |
| References | |
| NUDOCS 8103030380 | |
| Download: ML19341C414 (5) | |
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UNITED ST ATEs E
NUCLEAR REGULATORY COMMISSION n
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TENNESSEE VALLEY AUTHORITY j
DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE c
- Amendment No. 3 License No. DPR-77 1
1.
The Nuclear Regulatory Commission (the Commission) having 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 January 19, 1981 complies with the standards and requirements of the Atomic Energy Act of 1054, as amended (the Act) and the Commission's regulations as set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the license, as amended, 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 he 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 hereby amended by page changes to the Appendix A Technical Specifications as indicated in the attachments 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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2-(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 3, are hereby incorporated into the license.
i The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amended license is effective as of the date of issuance.
FDR THE NUCLEAR REGULATORY COMMISSION A. Schwencer, Chief 1
i Licensing Branch No. 2 i
Division of Licensing
Attachment:
Appendir. A Technical Specification Changes Date of Issuance:
Februa ryl3,1981 i
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ATTACHMENT TO LICEt4SE AMENDMENT NO. 3 FACILITY OPERATING LICENSE NO. DPR-77 DOCKET N0. 50-327 Replace the following pages of the Appendix "A' Technical Specifications with the enclosed pages. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain decument complete-ness.
Overleaf Amended Page Page 3/4 7-14 3/4 7-13 SEQUOYAH - UNIT 1 i
PLANT'SYSVEMS 3/4.7.4 ESSENTIAL RAW COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.1 At least two independent essential raw cooling water (ERCW) loops shall be OPERABLE.*
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
' With only one ERCW loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 />.
F SURVEILLANCE REQUIREMENTS 4.7.4.1 At least two ERCW loops shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manual, a.
power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
b.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve servicing safety related equipment actuates to its correct position on a Safety Injection test signal.
2.
Verifying that each ERCW pump starts automatically on a Safety Injection test signal.
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- Before Unit 2 operation (Unit 2 in either mode 1, 2, ~3, or 4), TVA shall be allowed to operate Unit I with 2A and IB ERCW headers' connected together. - This j
change shall be allowed for a one-time period of eight weeks while perforraing modifications to Component Cooling Water Heat Exchanger C.
'1 SEQUOYAH - UNIT 1 3/4 7-l'3 Amendment No. 3 I
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PLANT SYSTEMS AUXILIARY ESSENTIAL RAW COOLING WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.2 At least two independent auxiliary essential raw cooling water loops shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one auxiliary essential cooling water loop inoperable, restore the inoperable
. loop to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STAN08Y 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 SHUT 00WN within the followi,ng 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.4.2 At least two auxiliary essential service water loops shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve (manual, power operated or automatic) servicing safety related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.
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SEQUOYAH - UNIT 1 3/4 7-14 l
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