ML20217G677
| ML20217G677 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 10/08/1997 |
| From: | Wigginton D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20217G680 | List: |
| References | |
| NUDOCS 9710140144 | |
| Download: ML20217G677 (5) | |
Text
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UNITE') STATES ye o
NUCLEAR RESULATCRY GCMMISSIZN D
I WASHINGTON, D.C. MeeHo01
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ENTERGY GULF STATES. INC. **
CAJUN ELECTRIC POWER COOPERATIVE AND ENTERGY OPERAT!ONS. INC.
DOCKET NO. 50-458 RIVER BEND STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.99 i
License No. NPF-47 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Entergy Gulf States, Inc.* (the licensee) dated August 5,1997, as supplemented by letter dated August 15, 1997, 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; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, ano the rules and regulations of the Commission; 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 Commission's regulations; D.
The issuance of this license amendment will not be inimical to the common defense and security er to the health and safety of the public; and
- Entergy Operation, Inc. is authorized to act as agent for Entergy Gulf States, Inc., which has been authorized to act as agent for Cajun Electric Power Cooperative, and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
- Entergy Gulf States, Inc., which owns a 70 percent undivided interest in River Bend, has merged with a wholly owned subsidiary of Entergy Corporation.
Entergy Gulf States, Inc. was the surviving company in the merger.
9710140144 97100s PDR ADOCK 05000458 P
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. 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.
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-47 is hereby amended to read as follows:
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 99 and the Environmental Protection Plan contained in Appendix B, art hereby incorporated in the license.
EDI shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A
David L.
inton, 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:
October 8, 1997
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ATTACHMENT TO LICENSE AMENDMENT NO. 99 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 l
i Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain marginal liner indicating the areas of change.
REMOVE JNSERT 2.0-1 2.0-1 5.0-19 5.0-19 i
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-2.0 SAFETY LIMITS (SLs) 2.1 SLs 4
2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
l THERMAL POWER shall be s 25% RTP.
2.1.1.2 With the reactor steam dome pressure h 785 psig and core flow h 10% rated core flow:
l
- MCPR shall be 21.13 for two recirculation loop operation or h 1.14 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be s 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed:
2.2.1 Within I hour, notify the NRC Operations Center, in accordance with 10 CFR 50.72.
2.2.2 Within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods, 2.2.3 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the plant manager and the c.orporate executive responsible for overall plant nuclear safety.
(continued)
- Values applicable to Cycle 8 operation only.
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RIVER BEND 2.0-1 Amendment No. Mr96#9
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1 Reporting Requirements 5.6 5.6' Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 1)
NEDE-240ll o-A, ' General Electric Standard Application for Reactor Fuel' (latest approved version);*
l c.
The core operating limits shall be determined such that all a)plicable limits (e.g., fuel thermal mechanical limits, core t1ermal hydraulic limits Emergency Core Cooling Systems I;ECCS) limits, nuclear limits such as SDM, transient analysis I'mits, and accident analysis limits) of the safety analysis are met, d.
The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
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- For Cycle 8, specific documents were approved in the Safety Evaluation dated October 6,1997, to support License Amendment No.99 l
RIVER BEND 5.0-19 Amendment No. &FrS6P9 9
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