ML20072T962

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Corrected Amend 74 to License NPF-47,correcting Editorial Error Made to TS Page 3/4 3-42 Re Effective Date of License
ML20072T962
Person / Time
Site: River Bend Entergy icon.png
Issue date: 08/02/1994
From: Beckner W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20072T968 List:
References
NUDOCS 9409160051
Download: ML20072T962 (3)


Text

,

pa af og g <,) P.AE UNITED STATES a

i, NUCLEAR REGULATORY COMMISSION g

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WASHINGTON, D.C. 20555-0001

  • ...+

i GULF STATES UTILITIES COMPANY **

CAJUN ELECTRIC POWER COOPERATIVE AND ENTERGY OPERATIONS. INC, DOCKET N0, 50-458

~

RIVER BEND STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l

i Amendment No. 74 License No. NPF-47 1.

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

A.

The application for amendment by Gulf States Utilities * (the licensee) dated January 14, 1994, as supplemented July 15, 1994, 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

  • E01 is authorized to act as agent for Gulf States Utilities Company, which j

has been authorized to act as agent for Cajun Electric Power Cooperative, i

and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility,

    • Gulf States Utilities Company, which owns a 70 percent undivided interest in River Bend, has merged with a wholly owned subsidiary of Entergy Corporation. Gulf States Utilities Company was the surviving company in the merger.

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f 9409160051 940910 PDR ADOCK 05000458 t

p PDR l

. 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. 74 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

l E01 shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective 60 days from the date of issuance.

l FOR THE NUCLEAR REGULATORY COMMISSION g jl D. L A William D. Beckner, Director 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 2, 1994 l

l

TABLE 4.3.3.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCIIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED A. DIVISION I TRIP SYSTEM

1. RHR-A (LPCI MODE) AND LPCS SYSTEM a.

Reactor Vessel Water level -

Low Low Low Level 1 S

Q R(*)

1, 2, 3, 4*,

5*

R" 1, 2, 3 U

b.

Drywell Pressure - High S

Q c.

LPCS Pump Discharge Flow-low S

Q R""

1, 2, 3, 4*,

5*

d.

Reactor Vessel Pressure-Low S

Q R "' '

1, 2, 3, 4*, 5*

(LPCS/LPCI Injection Valve Permissive) e.

LPCI Pump A Start Time Delay Relay NA Q

Q "' '

1, 2, 3, 4*, 5*

f.

LPCI Pump A Discharge Flow-Low S Q

R 1, 2, 3, 4*,

5*

g.

LPCS Pump Start Time Delay NA Q

Q 1, 2, 3, 4*,

5*

Relay h.

Manual Initiation NA R*'

NA 1, 2, 3, 4*, 5*

2. AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "A"#

a.

Reactor Vessel Water Level -

UR" 1, 2, 3 Low Low Low Level 1 S

Q b.

Drywell Pressure-High S

Q R "' '

1, 2, 3 c.

ADS Timer NA Q

Q 1, 2, 3 d.

Reactor Vessel Water level -

Low Level 3 S

Q R

1, 2, 3 i

e.

LPCS Pump Discharge R"

1, 2, 3 l

U Pressure-High S

Q f.

LPCI Pump A Discharge Pressure-High S

Q R "

1, 2, 3 g.

ADS Drywell Pressure Bypass NA Q

Q 1, 2, 3 Timer h.

ADS Manual Inhibit Switch NA Q

NA 1, 2, 3 l

1.

Manual Initiation NA R

NA 1, 2, 3 RIVER BEND - UNIT 1 3/4 3-41 Amendment No. 9 73r74 7

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