ML20151X236

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Notice of Issuance of Amend 7 to License NPF-62.Amend Changes Tech Specs 3.6.1.8,3.6.2.7,4.6.1.8.2 & 4.6.2.7.4, Table 3.6.4-1 & Bases 3/4.6.2.7 & 3/4.6.1.8 Re Containment Bldg & Drywell Vent & Purge Sys
ML20151X236
Person / Time
Site: Clinton Constellation icon.png
Issue date: 08/09/1988
From: Olshan L
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20151X189 List:
References
NUDOCS 8808250286
Download: ML20151X236 (3)


Text

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J 7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION ILLIN0IS POWER COMPANY, ET AL.

DOCKET NO. 50-461 NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendvent No. 7 to Facility Operating License No. NPF-62 issued to the Illinois Power Company * (IP), Soyland Power Cooperative, Inc. and Western Illinois Power Cooperative, Inc., (the licensees), for operation of the Clinton Power Station, Unit 1, located in DeWitt County, Illinois.

This amendment consists of three changes to Technical Specification Sections 3.6.1.8, 3.6.2.7. 4.6.1.8.2, and 4.6.2.7.4, Table 3.6.4-1, and Bases 3/4.6.2.7 and 3/4.6.1.8 concerning the containment building and drywell vent and purge systems. The first change consists of those changes required to delete the OPERABILITY and surveillance requirements associated with 50' stops installed for the VR/VQ system containment isolation valves on the basis that

  • Illinois Power Company is authorized to act as agent for Soyland Power Cooperative Inc. and Western Illinois Power Cooperative Inc. and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

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7590-01 the 50' stops will now be considered to be a part of the pennanent design for these valves. The second change inserts footnotes into the Limiting Conditions for Operation and applicable surveillance requirements associated with Specifications 3.6.1.8 and 3.6.2.7 to exclude the time when valves are opened for perfonning stroke-time testing from the cumulative system operation time limited by the Limiting Conditions for Operation. The third change extends the application of Note "(a)" in Table 3.6.4-1 of the Technical Specifications to include specific VR/VQ containment isolation valves which need to be opened while conducting certain local leak "ate tests.

The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendment.

Notice of Consideration of Issuance of Amendment and Opportunity for Hearing in connection with this action was published in the FEDERAL REGISTER on February 18,1988(53FR4919). No request for a hearing or petition for leave to intervene was filed following this notice.

The Comission has prepared an Environmental Assessment related to the action and has detennined not to prepare an environmental impact statement.

Based upon the Environmental Assessment, the Commission has concluded that the issuance of this amendment will not have a significant effect on the quality of the human environment.

l 7590-01 3

Forfurtherdetailswithrespecttotheactionsee(1)theapplication for amendment dated October 30,1967,(2) Amendment No. 7 to License No. NPF-62, and (3) Environmental Assessment and Finding of No Significant Impact. All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, N.W.; and at Yespasian Warner Public Library, 120 West Johnson Street, Clinton, Illinois 61727. Acopyofitems(2)and (3) may be obtained upon request addressed to the U.S. Nuclear Regulatory Comission, Washington, D. C.

20555, Attention: Director, Division of Reactor Projects.

Dated at Rockville, Maryland this 9th day of August 1988.

FOR THE NUCLEAR REGULATORY COM11SSIGN h{k st Leonard N. 01shan, Acting Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects l

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