ML20080J151

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Amend 115 to License NPF-29,revises Requirement for Control Rod Testing to Increase Notch Testing Surveillance Interval for Partially Withdrawn Control Rods from Once Per 7 Days to Once Per 31 Days
ML20080J151
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 02/16/1995
From: Oconnor P
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20080J153 List:
References
NUDOCS 9502270133
Download: ML20080J151 (4)


Text

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cp nov 8t UNITED STATES

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NUCLEAR REGULATORY COMMISSION t

WASHINGTON, D.C. 2056Hm01 5

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ENTERGY OPERATIONS. INC.

i SYSTEM ENERGY RESOURCES. INC.

SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION MISSISSIPPI POWER AND LIGHT COMPANY DOCKET N0. 50-416 GRAND GULF NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 115 License No. NPF-29 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated April 21, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i

C.

There is reasonable assurance (i) that the activities authorized by j

this amendment can be conducted without endangering the health and J

safety of the public, and (ii) that such activities will be i

conducted in compliance with the Commission'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 Commission's regulations and all applicable requirements have been satisfied.

9502270133 950216 PDR ADOCK 05000416 p

PDR c.

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6 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. NPF-29 is hereby amended to read as follows:

l (2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised i

through Amendment No.115, are hereby incorporated into this license.

Entergy Operations, Inc. shall operate the facility in l

accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h

Paul W. O'Connor, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: February 16, 1995 i

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i ATTACHMENT TO LICENSE AMENDMENT NO.115 l

FACILITY QPERATING LICENSE NO. NPF-29 P

l DOCKET NO. 50-416 t

Replace the following page of the Appendix A Technical Specifications with the attached page. The revised-page is identified by amendment number and contains vertical lines indicating the area of change.

i REMOVE PAGE INSERT PAGE 3/4 1-4a 3/4 1-4a I

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REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) l l

4.1.3.1.2 When above the low power setpoint of the RPCS, all withdrawn I

control rods not required to have their directional control valves disarmed electrically or hydraulically shall be demon:,trated OPERABLE by moving each control rod at least one notch-a.

At least once per 7 days' for each fully withdrawn control. rod, and at least once per 31 days" for each partially withdrawn control rod, and t

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when any control rod is immo..:ble as a result of excessive friction or mechanical interference.

4.1.3.1.3 All control rods shall be demonstrated OPERABLE by performance of Surveillance Requirements 4.1.3.2, 4.1.3.3, 4.1.3.4 and 4.1.3.5.

l Not required to be performed until 7 days (for fully withdrawn) or 31 days (for partially withdrawn) after the control rod is withdrawn and I

THERMAL POWER is greater than the low power setpoint.

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I GRAND GULF-UNIT 1 3/4 1-4a Amendment No. 2h 115 i

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