ML20151B933
| ML20151B933 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 04/05/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151B938 | List: |
| References | |
| NUDOCS 8804120035 | |
| Download: ML20151B933 (7) | |
Text
,
6 UNITED STATES b
g NUCLEAR REGULATORY COMMISSION O
.j WASHINGTON, D. C. 20655
\\...../
GULF STATES UTILITIES COMPANY D_0CKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 19 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 18, 1987, as supplemented March 11, 1988.
complies with the standards and requirements of the Atomic Energy Act of,1954, as amended (the Act), and the Comission's rules and regula-tions 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 tht mies and regulations of the Comission; 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comen 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.
P
l 2.
Accordingly, the license is amei.ded 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 TheTechnicalppecificationscontainedinAppendixA,asrevisedthrough Amendment No.
3 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.
3.
The license amendment is effective as f its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jose
. 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 Issuance: April r,1938
.m
. =..
ATTACHMENT TO LICENSE AMENDMENT NO.19 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 PAGES INSERT PAGES 3/4 3-20 3/4 3-2D 3/4 3-21 3/4 3-21 3/4 3-22 3/4 3-22 i
l l
1
TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS
=
<m=
ALLOWABLE
=
TRIP FUNCTION TRIP SE1 POINT VALUE
~
E 1.
PRIMARY CONTAINMENT ISOLATION a.
Low Low, level 2 1-43 inches
- l-47 inches z
N b.
Drywell Pressure - High 1 1.68 psig 5 1.88 psig c.
Containment Purge Isolation Radiation - High 1 1.3 R/hr 1 1.57 R/hr 2.
MAIN STEAM LINE ISOLATION a.
Low Low Low, Level 1 1-143 inches
- 1-147 inches
,s
[
b.
Main Steam Line Radiation - High 5 3.0 x full power background 5 3.6 x full power 4
background e
c.
Main Steam Line Pressure - Low 1 849 psig 1 837 psig d.
Main Steam Line Flow - High 1.
Line A
< 146 psid
< 151 psid 2.
Line B i 156 psid 7 161 psid 3.
Line C 7 153 psid I 158 psid 4.
Line 0 5164psid i169,psid 1 7.6 inches Hg.
e.
Condenser Vacuus - Low
~
1 8.5 inches Hg.
vacuum vacuum E
f.
Main Steam Line Tunnel my Temperature - High 5 135'F
$ 142.5'F m
g.
Main Steam Line Tunnel g
a Temperature - High 1 51*F
$ 55'F U
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATIGN TNSTRUMENTATION SETPOINTS l
ALLOWABLE
<=
E TRIP FUNCTION TRIP SETPOINT VALUE 7
2.
MAIN STEAM LINE ISOLATION (Cont'd) c 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 7 102*F 7 106*F
- 4. MSL Moisture Separator and Reheater 5126*F
{130*F Area l
3.
SECONDARY CONTAINMENT ISOLATION w
a.
1 Low Low Level 2 1 - 43 inches *
> - 47 inches b.
Drywell Pressure - High 1 1.68 psig i 1.88 psig "4
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
{7.05x104 pCi/cc d.
Reactor Building Annulus Ventilation Exhaust Radiation - High 1 4.32 x 10 5 pCi/cc 1 5.19 x 10 5 pCi/cc 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High 1 55 gpa i 62.1 gpm 3
b.
A Flow Timer i 45 seconds 1 47 seconds g
Equipment Area Temperature - High E
c.
E 1.
Heat Exchanger Room
< 104.5 F
< 107.5*F l
2.
Pump Rooms A & B 7 165*F 7 169.5*F 5
3.
Valve Nest Room i 110*F 7 114.5*F 4.
Demineralizer Rooms 1 and 2 7 110*F i 114.5*F 5.
Receiving Tank Room 3110*F 5114.5'F
~
3 O
TABLE 3.3.2-2 (Continued)
E9 ISOLATION ACTUATION INSTRUNENTATION SETPOINTS co9 TRIP FUNCTION ALLOWABLE TRIP SETPOINT 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION (Cont'd)
VALUE l
d.
Equipment Area a Temperature - High l
E 1.
Heat Exchanger Room
< 39'F
< 42.5 F l
Z 2.
Pump Rooms A and B 7 78 F 7 82*F g
3.
Valve Nest Room 7 46*F 7 49.5'F 4.
Demineralizer Rooms 1 and 2 7 46*F 7 49.5*F l
5.
Receiving Tank Room 546*F 349.5*F e.
Low Low Level 2 1 - 43 inches
- 1 - 47 inches f.
Main Steam Line Tunnel Ambient Temperature - High 5 135*F
< 142.5*F R
g.
Main Steam Line Tunnel A Temperature - High
_ 51*F w
_ 55*F 4
h.
SLCS Initiation MA w
NA I
5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION RCIC Steam Line Flow - High 1 127" H 0**
1 135.5" H 0**
a.
2 2
b.
RCIC Steam Line Flow - High Timer 1 3 seconds
< 13 seconds c.
RCIC Steam Supply Pressure - Low 1 60 psig
> 55 psig d.
RCIC Turbine Exhaust Diaphragm Pressure - High
< 10 psig
< 20 psig g
e.
RCIC Equipment Room Ambient E
Temperature - High E
5 182 F
$ 186.4 F f.
RCIC Equipment Room A Temperature -
< 96*F
,5 High
< 99'F M
a
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS "a
ALLOWABLE m
z TRIP FUNCTION TRIP SETPOINT VALUE 7
5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATI6it (Cont'd)
E g.
Main Steam Line Tunnel Ambient U
Temperature - High 5 135"F
$ 142.5*F w
h.
Main Steam Line Tunnel A Temperature - High 5 51*F
$ 55'F i.
Main Steam Line Tunnel Temperature Timer 0 seconds NA j.
RHR Equipment Room Ambient Temperature - High i 117'F i 121.1*F-w k.
RHR Equipment Room a Temperature - High 1 29'F 1 33.6*F 1.
RHR/RCIC Steam Line Flow - High i 60.7" H O
$ 64.2" H O 2
2 Drywell Presture - High 1 1.68 psig 5 1.88 psig m.
n.
Manual Initiation NA NA 6.
RHR SYSTEM ISOLATION a.
RHR Equionent Area Ambient Temoerature - High
< 117'F
< 121.1*F g
m5 b.
RHR Equipment Area A Temperature -
y High 1 29*F i 33.6*F
--e z
c.
Low Level 3
> 9.7 inches
- 1 8.7 inches m
d.
Low Low Low Level 1 1 - 143 inches
- 1 - 147 inches
- - -.