ML20203N087
| ML20203N087 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 09/09/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Nebraska Public Power District (NPPD) |
| Shared Package | |
| ML20203N088 | List: |
| References | |
| DPR-46-A-101, TAC 61866 NUDOCS 8609230135 | |
| Download: ML20203N087 (4) | |
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UNITED STATES 8
g NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20655 NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.101 License No. DPR-46 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Nebraska Public Power District (thelicensee)datedJune 24, 1986, complies with the standards and a
requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission'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 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 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the licensee is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
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ADOCK 05000298 PDR
. (2) Technical Specification The Technical Specifications contained in Appendices A and B, as revised through Amendment No.101, 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.
FOR THE NUCLEAR REGULATORY COMMISSION Os mA Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: September 9, 1986 i
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ATTACHMENT TO LICENSE AMENDMENT NO.101 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298
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Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indiciated by marginal lines.
Pages 226
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4.3 PROCEDURE'S AND PROGRAMS 6.3.1 Introduction l
Station personnel shall be provided detailed written procedures to be-used for operation and maintenance of system components and systems that could have an effect on nuclear safety.
6.3.2 Procedures Written procedures and instructions including applicable check off lists shall be established, implemented, and maintained for the following:
A.
Normal startup, operation, shutdown and fuel handling operations of the station including all systems and components involving nuclear safety.
B.
Actions to be taken to correct specific and foreseen potential or actual malfunctions of safety related systems or components including responses to alarms, primary system leaks and abnormal reactivity changes.
C.
Emergency conditions involving possible or actual releases of radio-active materials.
D.
Implementing procedures of the Security Plan and the' Emergency Plan.
E.
Implementing procedures for the fire protection program.
F.
Administrative procedures for shift overtime.
6.3.3 Maintenance and Test Procedures The following maintenance and test procedures will be provided to satisfy routine inspection, preventive maintenance programs, and operating license requirements.
A.
Routine testing of Engineered Safeguards and equipment as required by the facility License and the Technical Specifications.
B.
Routine testing of standby and redundant equipment.
C.
Preventive or corrective maintenance of plant equipment and systems that could have an effect on nuclear safety.
D.
Calibration and preventive maintenance of instrumentation that could affect the nuclear safety of the plant.
E.
Special testing of equipment for proposed changes to operational procedures or proposed system design changes.
6.3.4 Radiation Control Procedures Radiation control procedures shall be maintained and made available to all station persor.nel. These procedures shall show permissible radiation exposure, and shall be consistent with the requirements of 10 CFR 20.
-226-Amendments Nos. 82, 83,101
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