ML20206D551
| ML20206D551 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 04/27/1999 |
| From: | Gramm R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206D556 | List: |
| References | |
| NUDOCS 9905040148 | |
| Download: ML20206D551 (5) | |
Text
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i UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30666 0001
'+9.....,o ENTERGY GULF STATES. INC. "
AND ENTERGY OPERATIONS. INC.
POCKET NO. 50-458 RIVER BEND STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 105 License No. NPF-47 1.
The Nuclear Regulatcry Commission (the Commission) has found that:
A.
The application for amendment by Entergy Gulf States, Inc.* (the licensee) dated December 16,1998, 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, and 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 or to the health and safety of the public; and
- EOl is authorized to act as agent for Entergy Gulf States, Inc, and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
"Entergy Gulf States, Inc., has merged with a wholly owned subsidiary of Entergy Corporation.
Entergy Gulf States, Inc. was the surviving company in the merger.
9905040148 990427 PDR ADOCK 05000458 P
E
. 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.105 and the Environmental Protection Pian contained in Appendix B, are hereby incorporated in the license. EOl 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 to be implemented prior to l
the startup following refueling outage 8.
FOR THE NUCLEAR REGULATORY COMMISSION A hh Robert A. Gramm, Chief, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: April 27, 1999
ATTACHMENT TO LICENSE AMENDMENT NO 105 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove lastt!
2.0-1 2.0-1 5.0-19 5.0-19
SLs 2.0 2.0' SAFETY LIMITS (SLs) 2.1 SLs 2.1. ~t Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be s 252 RTP.
2.1.1.2 With the reactor steam dame pressure a 785 psig and core flow a 10% rated core flow:
l HCPR shall be a 1.12 for two recirculation loop operation or a 1.13 for single recirculation loop operation.
l 2.1.1.3 Reactor vessel water level shall be greater than the top 1
of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL l
Reactor steam dome pressure shall be s 1325 psig.
2.2 SL Violations l
l With any SL violation, the following actions shall be completed:
i 2.2.1 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, 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 corporate executive responsible for overall plant nuclear safety.
(continued)
RIVER BEND 2.0-1 Amendment No. 01.06.00. 105
l' 9
Reporting Requirements 5.6 5.6 Reporting Requirements i
l
-5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 1)
NEDE-24011-P-A " General Electric Standard Applie.ation
- /
Reactor Fuel" (latest approved version);
l l
(
2)
NEDC-32489P (April 1996). "T-Factor Setdown Elimination Analysis for River Bend Station" (for power and flow dependent limits methodology only as evaluated and aporoved by Safety Evaluation and License Amendment 100 datea October 10, 1997).
c.
The core operatus limits shall be determined such that all j
applicable limits (e.g., fuel thermal mechanical limits, core l
thermal hydraulic limits. Emergency Core Cooling Systems (ECCS) l limits, nuclear limits such as SDM transient analysis limits, and accident analysis linits) of the safety analysis are met.
j d.
The COLR, including any midcycle revisions or supplements, shall l
be provided upon issuance for each reload cycle to the NRC.
l l
. RIVER BEND _
5.0-19 Amendment No. M.%.M.EO,105 J
u..