ML20211D662
| ML20211D662 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 05/30/1986 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20211D666 | List: |
| References | |
| NUDOCS 8606130032 | |
| Download: ML20211D662 (5) | |
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UNITED STATES g
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p, NUCLEAR REGULATORY COMMISSION yj WASHINGTON, D. C. 20555
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GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.1 License No. NPF-47 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for amendment filed by Gulf States Utilities Company, dated May 15, 1986 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's 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 regulations of the Commission; C.
There is reasonable assurance:
(1) 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 amendment will not be inimical to the comnon defense and security or to the health and safety of the publict ahd i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 s
of the _ Commission's regulations and all applicable requirements' have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-t cations 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 Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.1 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. GSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
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This license amendment became effective May 16, 1986.
FOR THE NUCLEAR REGULATORY COMMISSION
+A Walter R. Butler, Director BWR Project Directorate No. 4 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 30,1986 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 1 FACILITY OPERATING LICENSE NO. NPF-47 DOCKET NO. 50-458 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains a vertical line indicating the area of change. Overleaf page provided to maintain document completeness.*
REMOVE INSERT 3/4 3-19 3/4 3-19*
3/4 3-20 3/4 3-20
TABLE 3.3.2-2 g
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS E
ALLOWABLE g
TRIP FUNCT'10N TRIP SETPOINT VALUE E
1.
PRIMARY CONTAI MENT ISOLATION
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a.
5 Low Low, Level 2
>-43 inches *
>-47 inches
-4 w
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Drywell Pressure - High 5 1.68 psig 5 1.88 psig c.
Containment Purge Isolation Radiation - High i 1.3 R/hr i 1.57 R/hr 2.
MAIN STEAM LINE ISOLATION I
a.
l Low Low Low, Level 1
>-143 inches *
>-147 inches b.
Main Steam Line Radiation - High 5 3.0 x full power background 1 3.6 x full power background y
c.
Main Steam Line Pressure - Low
> 849 psig
> 837 psig d.
Main Steam Line Flow - High 5 173** psid 5 178** psid e.
Condenser Vacuum - Low
> 8.5 inches Hg.
> 7.6 inches Hg.
vacuum vacuum i
f.
Main Steam Line Tunnel Temperature - High 5 135'F
$ 142.5'F g.
Main Steam Line Tunnel A Temperature - High 5 51*F
$ 55*F I
TABLE 3.3.2-2 (Continued) 9 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS en z
ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE 2.
MAIN STEAM LINE ISOLATION (Cont'd) ei'i h.
Main Steam Line Area Temperature - High (Turbine Building)
- 1. Main Steam Tunnel Area (El. 95')
< 142*F
< 145.3*F
- 2. Main Steam Tunnel Area (El. 114')
7 142 F 7 145.3 F
- 3. Main Steam Line Turbine Shield Wall 7 108*F 7 111.3 F I
- 4. MSL Moisture Separator and Reheater i126*F 3130*F Area 3.
SECONDARY CONTAINMENT ISOLATION R
a.
Low Low Level 2
> - 43 inches *
> - 47 inches g
b.
Drywell Pressure - High 5 1.68 psig 5 1.88 psig c.
Fuel Building Ventilation Exhaust Radiation - High 1RMS*RESA
< 1.82 x 103 pCi/sec
< 2.18 x 103 pCi/sec 1RMS*RESB
?5.88x104 pCi/cc i7.05x104 pCi/cc d.
Reactor Building Annulus Ventilation Exhaust Radiation - High 5 4.32 x 10 5 pCi/cc 5 5.19 x 10 5 pCi/cc 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High 5 55 gpm 5 62.1 gpm g
g b.
A Flow Timer 5 45 seconds 1 47 seconds R
c.
Equipment Area Temperature - High
'i
- 1. Heat Exchanger Room
< 98.5 F
< 101.5"F
- 2. Pump Rooms A & B 7 165 F 7 169.5*F zP
- 3. Valve Nest Room i 110 F 7 114.5*F
- 4. Demineralizer Rooms 1 and 2 7 110"F 7 114.5*F
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- 5. Receiving Tank Room 5110*F i114.5F
.