ML20195B536
| ML20195B536 | |
| Person / Time | |
|---|---|
| Site: | River Bend  (NPF-47-A-024, NPF-47-A-24) |
| Issue date: | 06/03/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20195B539 | List: |
| References | |
| NUDOCS 8806210446 | |
| Download: ML20195B536 (7) | |
Text
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION o
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WASHING TON, D. C. 20655 c
%,..... f GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. NPF-47 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Gulf States Utilities Company (the licensee) dated June 5, 1987 as modified May 13, 1988, compliec with the standards and requirements cf 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; 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 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 E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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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 Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. ?4 and the Environmental Protection Plar-contained in Appendix B, are hereby incorporated in the license. GSU shall opecate the facility in accordance with the Technical Specifications and the Elvironmental Protection Plan.
3.
The license amendment is effective as of its date cf issuance.
FOR THE NUCLEAR REGULATOPY COMiilSSION
- f. 67IW w
Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuarce: June 3, 1988
ATTACHMENT TO LICENSE AMEN 0 MENT NO. 24 FACILITY CPERATING LICENSE N0 NPF-47 DOCKET NO. 50-458 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. Overleaf page provided to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 3-19 3/4 3-19 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 i
l 4
TABLE 3.3.2-2 l
5 ISOLATION ACTUATT6ETR5TIMEliTATION SETPOINTS i
- 5; 1
=
Altom8LE
}
g TRIP FUNCTION TRIP SETPOINT VALUE 5
1.
PRIMARY CONTAllMENT ISOLATION
[
a.
3 Low Low, level 2
>-43 inches *
>-47 inches w
b.
Dryvell Pressure - High 5 1.68 psig i 1.88 psig c.
Containment Purge Isolation Radiation - High 1 1.3 R/hr i 1.57 R/hr 2.
MAIN STEAM LINE ISOLATION i
a.
j Low Low Low. Level 1
>-143 inches *
>-147 inches s
i
[
b.
Main Steam Line Radiation - High i 3.0 x full power background
< 3.6 x full power background a
e c.
Main Steam Line Pressure - Low
> 849 psig
> 837 psig i
l d.
Main Steam Line Flow - High i
1.
Line A
< 146 psid
< 151 psid j
2.
Line 8 7 156 psid i 161 psid i
3.
Line C 7 153 psid i 158 psid 4.
Line D 7 164 psid
-1 169,psid s
t e.
Condenser Vacuum - Low
~
> 8.5 inches Hg.
> 7.6 inches Hg.
vacuum vacuum l
E f.
Main Steam Line Tunnel
.i m
j y
Temperature - High 5 141*F 1148.5*F m
- i g.
Main Steam Line Tunnel j
g a Temperature - High 1 57'F 161 *F
\\
i 2
)
i l
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS as ALLOWABLE E
TRIP FUNCTION TRIP SETPOINT VALUE 7
2.
MAIN STEAM LINE ISOLATION (Cont'd) c h.
Main Steam Line Area h
Temperature - High (Turbine Building)
- 1. Main Steam Tunnel Area (E1. 95')
< 142 F
< 145.3 F
- 2. Main Steam Tunnel Area (El. 114')
7 142 F 7 145.3*F 1
- 3. Main Steam Line Turbine Shield Wall i 108 F 7 111.3 F-
- 4. MSL Moisture Separator and Reheater 3126F 3130F-Area 3.
SECONDARY CONTAINMENT ISOLATION i
a.
{
Low Low Level 2
> - 43 inches *
> - 47 inches 4
y b.
Drywell Pressure - High 5 1.68 psig 1 1.88 psig E$
c.
Fuel Building Ventilation j
Exhaust Radiation - High 1RMS*RESA
< 1.82 x 103 pCi/sec
< 2.18 x 103 pCi/sec 1RMS*RESB 35.88x104 pCi/cc 37.05x104 pCi/cc d.
Reactor Building Annulus Ventilation Exhaust Radiation - High 1 4.32 x 10 5 pCi/cc
$ 5.19 x 10 5 pCi/cc 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION E
a.
A Flow - High 5 55 gpm i 62.1 gpm g
-g b.
A Flow Timer
$ 45 seconds i 47 seconds 5
c.
Equipment Area Temperature - High 4
1.
Heat Exchartger Room
< 104.5 F
< 107.5 F I-z
^
2.
Pump Rooms A & B i 165 F 7 169.5*F x
3.
Valve Nest Roos 7 110 F i 114.5*F 4.
Demineralizer Rooms 1 and 2 7 110 F 7 114.5 F
~
f
' 5.
Receiving Tank Room 3110F 3114.5F
)
TABLE 3.3.2-2 (Continued) 2 ISOLATION ACTUATION INSTRUNENTATION SETPOINTS 9
oo E ~ TRIP FUiCTION ALLOWA8LE TRIP SETPOINT VALUE 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION (Cont'd) d.
Equipment Area a Temperature - High E
1.
Heat Exchanger Room
< 39'F
< 42.5'F i
Q 2.
Pump Rooms A and B 578'F 582*F p
3.
Valve Nest Room
< 46*F
< 49.5'F 4.
Demineralizer Rooms 1 and 2 7 46*F 7 49.5'F 5.
Receiving Tank Room 546*F 7 49.5'F i
i j
e.
j Low Low Level 2 1 - 43 inches
- 1 - 47 inches
]
f.
Main Steam Line Tunnel j
Ambient Temperature - High
$ I41 *F
< 148.5 3F R
g.
Main Steam Line Tunnel a Temperature - High 57 *F
< 61 *F w4 h.
SLCS Initiation NA NA i
l S.
REAC10R CORI JSCLATION COOLING SYSTEM ISOLATION a.
RCIC Steam Line Flow - High 1 127" H O 5 135.5" H O 2
i 2
j b.
RCIC Steam Line Flow - High Timer 1 3 seconds 5 13 seconds 1
j c.
RCIC Steam Supply' Pressure - Low 1 60 psig 1 55 psig d.
RCIC Turbine Exhaust Diaphragm
}
Presisure - High 5 10 psig 5 20 psig i
N l
g e.
RCIC Equipment Room Ambient j
g Temperature - High 1 132*F
< 186.4*F z
f.
RCIC Equipment Room a Temperature -
j High
' -< %*F
< 99'F U
1
=
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS as ALLOWABLE E TRIP FUNCTION TRIP SETPOINT VALUE 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Cont'd)
E g.
Main Steam Line Tunnel Ambient U
Temperature - High 1 141 F i 148.5 F w
h.
Main Steam Line Tunnel A Temperature - High 5 57 F i 61 F i.
Main Steam Line Tunnel Temperature Timer 0 seconds NA j.
RHR Equipment Room Ambient Temperature - High 5 117 F
$ 121.1 F k.
RHR Equipment Room
[
A Temperature - High
$ 29 F
$ 33.6 F m
j 1.
RHR/RCIC Steam Line Flow - High
$ 60.7" H 0**
i 64.2" H 0**
2 2
m.
Drywell Pressure - High 5 1.68 psig
$ 1.88 psig n.
Manual Initiation NA NA 6.
RHR SYSTEM ISOLATION a.
RHR Equipment Area Ambient Temperature - High 5 117 F 5 121.1 F E
b.
RHR Equipment Area A Temperature -
l High 5 29 F
$ 33.6 F e
z c.
Low Level 3 1 9.7 inches
- 1 8.7 inches D
d.
g Low Low Low Level 1 1 - 143 inches
- 1 - 147 inches 1---
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