ML20080P210
| ML20080P210 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 03/01/1995 |
| From: | Pickett D Office of Nuclear Reactor Regulation |
| To: | Illinois Power Co |
| Shared Package | |
| ML20080P213 | List: |
| References | |
| NPF-62-A-096 NUDOCS 9503070261 | |
| Download: ML20080P210 (4) | |
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- NUCLEAR REGULATORY COMMISSION Nr..[ }
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ILLINOIS POWER COMPANY. ET AL.
..; DOCKET NO.'50-461 l
M CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE:
6
. Amendment No. 96 -
License No. NPF-62 2 1..
'The Nuclear Regulatory Comission'(the Comission) has found that:
A.
The application for amendment by Illinois ' Power Company * '(IP),-and Soyland Power Cooperative, Inc. (the licensees). dated August 12, 1994, October: 14.-1994, and February 6, 1995,' complies with.the standards and requirements of the Atomic: Energy Act of;1954,.as L amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I;
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B.
The facility will operate in conformity with the-application, the
, provisions.of the.Act, and the rules and regulations.of the Comission; 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-conducted in compliance with the Comission'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 of the Commission's regulations and all applicable requirements have been satisfied.
f 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and.
paragraph 2.C.(2).of Facility Operating License No. NPF-62 is hereby amended to read as follows:
- Illinois Power Company is-authorized to act as agent for..Soyland Power Cooperative, Inc. and has exclusive responsibility and control over the physical-construction, operation and maintenance of the facility.
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Technical Specifications and Environmental Protection Plan i
The. Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B,. as revised through Amendment No. 96, are hereby incorporated into this license.
Illinois Power Company, shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license' amendment is effective as of-its date of issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION Q
V iM Douglas V. Pickett, Senior Project Manager Project Directorate III-3 Division of. Reactor Projects - III/IV Office of Nuclear Reactor Regulation Attachmenti Changes'to the Technical Specifications Y
Date of Issuance: March 1, 1995 t
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-: 4 ENT NO.96 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 Replace the following page-of the Appendix #A" Technical Specifications with the attached page.
The revised page is identified by. amendment number and contains a vertical lines indicating the area of change.
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Remove Paaes Insert Paaes 3.6-54 3.6-54 b
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y,. 9'.y Drywell-3.6.5.1J i
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V 13.6. CONTAINMENT. SYSTEMS-j I'
3.6.5.1 Drywell j
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- LCO. 3.6.5.1-
' The drywell shall be OPERABLE.
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~ APPLICABILITY:
MODES'1, 2, and 3.
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!$l ACTIONS CONDITION' REQUIRED ACTION COMPLETION TIME 6
A.
Drywell inoperable.
A.1 Restore drywell to I hour:
.i OPERABLE status.
2 B.
Required Action and B.1-Be in MODE 3.
12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
1 associated Completion
' Time not met.
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9 B.2
'Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> r
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SURVEILLANCE REQUIREMENTS
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SURVEILLANCE-FREQUENCY i
SR '3.6.5.1.1
NOTE-----------------------
- l Not required to'be performed until entry into MODE 2 on the first unit startup from the sixth refueling outage.
a Verify bypass leakage is less than or 18 months-equal to the bypass leakage limit, j
However,.during the first unit startup following bypass leakage testing performed in accordance with this SR, the i
acceptance criterion is's 10% of the 1
drywell. bypass leakage limit.
i (continued).
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CLINTON.
3.6-54 AmendmentNo.g,96-
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