ML20078L487
| ML20078L487 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/30/1983 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078L494 | List: |
| References | |
| TASK-2.B.3, TASK-TM NUDOCS 8310210344 | |
| Download: ML20078L487 (2) | |
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 23 License No. DPR-79 1.
The Nuclear Regulatory Comission (the Commission) 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 June 16, 1983, complies with the standards and requirements 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 conformity with the license, as amended, the prwisions of the Act, and the rules and regulations of the Com-mission; 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 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 mm of the Commission's regulations and all applicable requirements have gg been satisfied.
D' O 88 2.
Accordingly, Facility Operating' License DPR-79 is hereby amended as follows:
am e
A.
Change paragraph 2.C.(16)g. to read as follows:
ex 00 00 g.
Post Ac.cident Sampling (Section 22.2 II.B.3) en Se At the first outage of sufficient duration, but no later than O(~h startup following the second refueling outage, TVA shall com-plete corrective actions needed to prwide the capability to promptly obtain and perform radioisotopic and chemical analyses of reactor coolant and containment atmosphere samples
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. B.
Change paragraph 2.C.(16)l.(2) to read as follows:
(2) At the first outage of sufficient duration, but no later than startup following the first refueling outage TVA shall install the following qualified monitoring instrumentation:
(a) Containment high range radiation monitor.
(b) Containment pressure monitor.
(c) Containment water level monitor.
(d) Containment hydrogen monitor.
C.
Add paragraph 2.C.(16)l.(3) to read as follows:
(3) At the first outage of sufficient duration, but no later than sta.' tup following the second refueling outage. TVA shall install a qualified integrated monitoring assembly which will accomplish particulate, iodine and noble gas monitoring.
D.
Change paragraph 2.C.(16)m.(2) to read as follows:
(2) At the first outage of sufficient duration, but no later than startup following the second refueling outage TVA shall install reactor vessel water level instrumentation which meets NRC requirements.
E.
Change paragraph 2.C.(16)q.(1) to read as follows:
(1) At the first outage of sufficient duration, but no later than startup following the second refueling outage TVA shall update the Technical Support Facilities to meet NRC requirements.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 6
[ N / j #,'T Darrell G. Eisenhut, Director Division of Licensing j l) g t
Office of Nuclear Reactor Regulation 4
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