ML20002C626
| ML20002C626 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/22/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20002C627 | List: |
| References | |
| NUDOCS 8101100614 | |
| Download: ML20002C626 (4) | |
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9 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE(b0YAH NUCLEAR PLANT, UNIT 1 AMENDf4ENT TO FACILITY OPERATING LICENSE Amendment fio. 1 License No. UPR-77 1.
The Nuclear Regulatory Conunission (the Coninission) having found that:
A.
The application for amendment to the Sequoyah Nuclear Plant, Unit 1 (the facility) Facility Operating License No. OPR-77, filed by the Tennessee Valley Authority (licensee), dated Septen.ber 24, 1960, complies with the standards and requirements of the Atomic L..argy Act of 19b4, as amended (the Act) and the Conmission'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 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 con-ducted in compliance with the Conniission's regulations; D.
The issuance of this amendment will not be inimical to the conrnon 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 bl of the Conmission'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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. (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.1, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This amended license is effective as of September 23, 1980.
FOR T};E NUCLEAR REGULATORY COT.fsISSION 7
'lk'tWW A. Schwencer, Chief Licensing Branch No. 2
,Division of Licensing
Attachment:
Appendix A Technical Specification changes Date of Issuance:
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TABLE 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER FUNCTION 63-586 Boron Injection 63-587 Boron Injection 63-588 Boron InSction 63-589 Boron Injection 63-581 Boron Injection 63-560 Accumulator Discharge 63-561 Accumulator Discharge (y)63-562 Accumulator Discharge 63-563 Accumulator Discharge (1)63-622 Accumulator Discharge 63-623 Accumulator Discharge 63-624 Accumulator Discharge 63-625 Accumulator Discharge 63-551 Safety Injection (Cold Leg)63-553 Safety Injection (Cold Leg)63-557 Satety Injection (Cold Leg)63-555 Safety Injection (Cold Leg)63-632 Residual Heat Retroval (Cold Leg)(1)63-633 Residual Heat Renoval (Cold Leg)(y)63-634 Residual Heat Removal (Cold Leg)(1)63-635 Residual Heat Removal (Cold Leg)(1)63-641 Residual Heat Removal / Safety Injection (Hot Leg)63-644 Residual Heat Removal / Safety Injection (Hot Leg)63-558 Safety Injection (Hot Leg)63-559 Safety Injection (Hot Leg)63-543 Safety Injection (Hot Leg)63-545 Safety Injection (Hot Leg)63-547 Safety Injection (Hot Leg)63-549 Safety Injection (Hot Leg)63-640 Residual Heat Removal (Hot Leg)63-643 Residual Heat Removal (Hot Leg)87-558 Upper Head Injection 87-599 Upper Head Injection 87-560 Upper Head Injection 87-561 Upper Head Injection 87-562 Upper Head Injection 87-563 Upper Head Injection (1)(2)
FCV-74-1 Residual Heat Removal (1)(2)
FCV-74-2 Residual Heat Removal The valves must be tested prior to entering MODE 2.
The leakage limit for these valves is 3 GPM.
This value will be finalized within 30 days of issuance of this amendment.
SEQUOYAH - UNIT 1 3/4 4-15a 6
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REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:
a.
No PRESSURE BOUNDARY LEAKAGE, b.
1 GPM UNIDENTIFIED LEAKAGE, 1 GPM total primary-to-secondary leakage through all steam generators and 500 c.
gallons per day through any one steam generator, d.
10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, 40 GPM CONTROLLED LEAKAGE at a Reactor Coolant System e.
pressure of 2235 + 20 psig, f.
1 GPM leakage from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.*
APPLICABILITY:
MODES 1, 2, 3 and 4 ACTION:
With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY a.
within 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 tne following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
WitF. any Reactor Coolant System leakage greater than any one of the abcve limits, excluding PRESSURE BOUNDARY LEAKAGE, and leakage from Re4ctor Coolant System Pressure Isolation Valves, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 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 />.
With any Reactor Coolant System Pressure Isolation Valve leakage c.
greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, 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 REQUIREMENTS 4.4.6.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:
" Specific exceptions to the 1 GPM leakage limit and the MODE 3 and 4 applicability are listed on Table 3.4-1.
SEQUOYAH - UNIT 1 3/4 4-14
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