ML20043A878
| ML20043A878 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/09/1990 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043A879 | List: |
| References | |
| NUDOCS 9005230234 | |
| Download: ML20043A878 (4) | |
Text
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jg UNITED STATES I
NUCLEAR REGULATORY COMMISSION a
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i TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-327 SE000YAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 139 i
License No. DPR-77 l
1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 8,1989 and the supplemental letter dated March 15, 1990 comply with the standards and re Atomic Energy Act of 1954, as amended (the Act)quirements of the
, and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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 issuince 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 of the Commission's regulations and all applicable requirements have been satisfied.
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9005230234 900509 ADOCK0500~g7 DR 1
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2.
Accordingly, the license is amended by changes to the 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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B. as revised through Amendment No.139, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
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FOR THE NUCLEAR REGULATORY COMMIS510N h
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Suzanne Black, Assistant ector for Projects
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l TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 9, 1990 l
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i ATTACHMENT TO LICENSE AMENDMENT NO.139 FACILITY OPERATING LICENSE NO. DPR-77 00CKET NO. 50-327 Revise the Appendix A Technical Specifications by removing-the pages t
identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT L
3/4 5-6 3/4 5-6 t
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EMERGEWCY CORE COOLING SYSTEMS (ECCS)
SURVEILLANCE REQUIREMENTS (Continued)
Valve Number Valve Function Valve Position I
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:
8' 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)
Jn the flow path that is not locked, sealed, or otnerwise secured in position, is in its correct position c.
By a visual inspection which verifies that no loose debris (rags, 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.
This visual inspection shall be performed:
1.
For all accessible 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.
SEQUOYAH - UNIT 1 3/4 5-6 Amendment No. 92, 139
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