ML20028H130
| ML20028H130 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/01/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028H131 | List: |
| References | |
| NUDOCS 9010090242 | |
| Download: ML20028H130 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION i
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DOCKET NO. 50-328 SEQUOYAH NUCLEAR PLANT,ifNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE 5
i Amendment No.128 License No. DPP-79 1.
The Nuclear Regulatory Cornission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 8,1969 and the supplemental letter dated March 15, 1990 comply with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Consission'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 end regulations of the Cornission; 1
C.
There is reasonable assurance (1) that the activities authorized by this arendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Conmission'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 Cocnission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is arended by changes to the Technical Specificatiers 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 I
The Technical Specificaticns contained in A'pendices A and C, as a
revised through Amendment No.128 are herel.sy incorporated in the license. The licensee shall o the Technical Specifications. perate the facility in accordance with 3.
This license amendnent is effective as of its dete of issuance.
FOR TPE NUCLEAR REGULATORY COMMISSION e.* &w
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Frederick J. H& don, Director Project Directcrate 11-4 Divisier of Reactor Projects - I/II Office of Nuclear Reactor Regulation Attachrent:
Cbtr.ges to the Technical Specifications Date of Issuance: October 1,1990 I
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5 ATTACHMENT TO LICENSE AMENDMENT N0.128 i
FACILITY OPERATING LICENSE N0. DPR-79 DOCKET NO. 50-328 I
Revise the Appendix A Technical !pecifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the caption:d amendment number and contain marginal lines indicating the area of change, REMOVE INSERT I
3/4 5-6 3/4 5-6
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n EMERGENCY CORE COOLING SYSTEMS i
l SURVEILLANCE REQUIREMENTS (Continued)
Valve Number Valve Function Valve Position a.
FCV-63-1 RHR Suction from RWST open b.
FCV-63-22 SIS Discharge to Common Piping open b.
At least once per 31 days by:
1.
Verifying that the ECCS piping is full of water by venting the ECCS pump casings and accessible discharge piping high points, and 2.
Verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.
By a visual inspection which veriffes that no loose debris (rags, i
trash, clothing, etc.) is present in the containment which could be transported to the containment sump and cause restriction of the pump suctions during LOCA conditions.
Tb 4 visual inspection shall be performed:
1.
For all Ecessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established.
d.
At least once per 18 months by:
1.
DELETED.
2.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
e.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal and automatic switchover to containment sump test signal.
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SEQUOYAH - UNIT 2 3/4 5-6 L
Correction letter: 01/22/89 l'
Amendment No. 82, 128
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