ML20210Q912
| ML20210Q912 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/26/1997 |
| From: | Wigginton D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210Q918 | List: |
| References | |
| NUDOCS 9709020205 | |
| Download: ML20210Q912 (7) | |
Text
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ENTERGY GULF STATES. INC. **
CAJUN ELECTRIC POWER COOPERATIVE AND ENTERGY OPERATIONS. INC.
DOCKET NO. 50 453 RIVER BEND STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 98 Licensa No NPF-47
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1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Gulf Ctates, Inc.* (the licensee) dated November 6,1996, as supplemented by letter dated July 31, 1997, complies with the standards and 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, as amended, the provisions of the Act, and the rules and regulations of the Comission; There is reasonable assurance:
(i that the activitus authorized by this amendment can be conducted)without endangering the health C.
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 license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and
- E01 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.
9709020205 970826 PDR ADOCK 05000458 P
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 Technica1' Specifications contained in Appendix A, as revised through Amendment No. 98 and the Environmental Pr'tection Plan o
contained in Appendix B, are hereby incorporated in the license.
E01 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 m
v DavfdL.
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: August 26, 1997
I-ATTACHMENT TO LICENSE AMENDMENT NO. 98 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following ) ages of the Appendix A Technical Specifications with the attached pages.
Tie revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT 11 11 3.6-18 3.6-18 3.6-27 3.6-27 3.6-28 3.6-28 l
TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.6.4 Relief and Low-Low Set (LLS) Instrumentation...... 3.3-66 3.3.7.1 Control Room Fresh Air (CRFA) System Instrumentation 3.3 68 3.3.8.1 Loss of Power (LOP) Instrumentation 3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring..................... 3.3-75 3.4 REACTOR COOLANT SYSTEN (RCS)................ 3.4-1 3.4.1 Recirculation Loops Operating 3.4-1 3.4.2 Flow Control Valves (FCVs)............... 3.4-6 3.4-8 3.4.3 Jet Pumps 3.4.4 Safety / Relief Valves (S/pVs).............. 3.4-10 3.4-12 3.4.5 RCS Operational LEAKAGE 3.4.6 RCS Pressure Isolation Valve (PIV) Leakage....... 3.4-14 3.4.7 RCS Leakage Detection Instrumentation 3.4-17 3.4-20 3.4.8 RCS Specific Activity 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System--Hot Shutdown................ 3.4-22 3.4.10 Residual Heat Removal (RHR) Shutdown Cooling System--Cold Shutdown 3.4-25 3.4.11 RCS Pressure and Temperature (P/T) Limits 3.4-27 3.4.12 Reactor Steam Dome Pressure 3.4-33 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5-1 3.5-1 3.5.1 ECCS--0)erating 3.5.2 ECCS -- 51utdown.....................
3.5-6 3.5-10 3.5.3 RCIC System 3.6 CONTAINMENT SYSTEMS 3.6-1 3.6.1.1 Primary Containment-Operating 3.6-1 3.6.1.2 Primary Containment Air Locks 3.6-3 3.6.1.3 Primary Containment Isolation Valves (PC Vs)......
3.6-9 3.6.1.4 Prim:ry Containment Pressure.............. 3.6-21 3.6.1.5 Primary Containment Air Temperature 3.6-22 3.6.1.6 Low-Low Set (LLS) Valves................ 3.6-23 3.6.1.7 Primary Containment Unit Coolers............ 3.6-25 3.6.1.8 Deleted 3.6-27 l
3.6.1.9 Main Stean-Positive Leakage Control System (MS-PLCS).. 3.6-29 3.6.1.10 Primary Containment-Shutdown..........,,.. 3.6-31 3.6.2.1 Suppression Pool Average Temperatore.....,.... 3.6-33 3.6.2.2 Suppression Pool Water Level.............. 3.6-36 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool 3.6-37 Cooling 3.6.3.1 Primary Containment Hydrogen Recombiners........ 3.6-39 3.6.3.2 Primary Containment and Drywell Hydrogen Igniters 3.6-41 (continued)
RIVER BEND 11 Revision No. 9,1
~.
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.8 Verify in-leakage rate of s 340 scfh for 18 months each of the following valve groups when l
tested at 11.5 psid for MS-PLCS valves.
l a.
Division I MS-PLCS valves, b.
Division !! MS-PLCS valves.
--NOTE--------------------
Only required to be met in MODES 1, 2, and 3.
Verify the combined leakage rate for all In accordance secondary containment bypass leakage with the l
paths is s 170,000 cc/hr when pressurized Primary to it Pa.
Containment Leakage Rate Testing Program (continued)
RIVER BEND 3.6-18 Amendment No. BhB4,98
PVLCS 3.6.1.8 I'l, 3.6-CCNT' JNMENT $YSTEMS 3.6.1.8 Deleted RIVER BEND 3.6-27 Amendment No. 81,98-I'E'
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PVLc5 3.6.1.8 THIS PAGE INTENTIONALLY LEFT BLANK 1
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4 4
RIVER BEND 3.6-28 Amendment No. 81,98 wW v e%
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