ML20080A709
| ML20080A709 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-79-A-020, DPR-79-A-20) |
| Issue date: | 07/15/1983 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080A714 | List: |
| References | |
| NUDOCS 8307270297 | |
| Download: ML20080A709 (5) | |
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE hiendment No.20 License No. DPR-79 1.
The Nuclear Regulatory Commission (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 21, 1983, conplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission'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 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 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-79 is hereby amende1 to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 20, are hereby incorporated into the license.
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The licensee shall operate the facility in accordance dith the \\
Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 9
Elinor G. Adensam, Chief Licensing Branch No. 4 Division of Licensing Attac hnsnt:
Appendir A Technical Specification Change Date of Issuance: July 15, 1983 4
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g m ATTACHMENT TO LICENSE AMENDMENT NO. 20 FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 50-328 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Amended Page 3/4 1-19 3/4 3-54 I
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J TABLE 4.3-6 vig REMOTE SHUTDOWN MONITORING INSTRUMENTATION g
SURVEILLANCE REQUIREMENTS s
x CHANNEL CilANNEL ~
g INSTRUMENT CHECK CALIBRATION l
Z 4
1.
Source Range Nuclear Flux M
R.
g 2.
Reactor Trip Breaker Indication M
N.A.
3.
Reactor Coolant Temperature - llot Leg M
R 4.
Pressurizer Pressure M
R 4
5.
Pressurizer Level M.
R 6.
Steam Generator Pressure M
R y
7.
Steam Generator Level M
R u,
o l
8.
Full Length Control Rod Position Limit Switches M
R$
2 9.
RHR Flow Rate M-R f
10.
RHR Temperature M
R t
11.
Auxiliary Feedwater Flow Rate M
R l
12.
Pressurizer Relief Tank Pressure M
R.
13.
Containment-Pressure M
R
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- For cycle 1, this surveillance is to be completed before the next cooldown or by August 5, 1983, g
whichever is earlier.
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REA?'IVITY CONTR0'L SYSTEMS
- ROD DROP TIME LIMITING CONDITION FOR OPERATION
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3.1.3.4 -The individual full length (shutdown and control) rod drop time from the fully withdrawn position shall be less thin or equal to 2.2 seconds from beginning of decay of stationary gripper coil voltage to dashpot entry with:
T,yg greater than or equal to 541 F, and w.
b.
All reactor coolant pumps operating.
APPLICABILITY:
MODES I and 2.
ACTION:
a.
With the drop time of full length rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.
b.
With_theroddroptime2'withinlimitsbutdeterminedwith3 reactor coolant pumps operating, operation may proceed provided THERMAL
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POWER is restricted to less than or equal to 71% of RATED THERMAL POWER.
SURVEILLANCE REQUIREMENTS
[
4.1.3.4 The rod drop time of full: length rods shall be demonstrated through j
measurement prior to reactor criticality:
i a.
For all rods following each removal of the reactor vessel head, b.
For specifically affected individual rods following any maintenance on or modification to the control rod drive system which could affect the drop time of those specific rods, and c.
At least once per 18 months.*
"For cycle 1, this surveillance is to be completed before the next cooldown or by August 5,1983, whichever is earlier.
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SEQUOYAH - UNIT 2 3/4 1-19 Amendment No. 20
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