ML20203G476
| ML20203G476 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 02/16/1999 |
| From: | Skay D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203G482 | List: |
| References | |
| NUDOCS 9902190320 | |
| Download: ML20203G476 (14) | |
Text
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UNITED STATES g
g NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20061 4 001
'+,.....,o COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 1.ASALLE COUNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.115 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated November 9,1998, 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; B.
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 (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 set forth in 10 CFR Chapter I; i
D.
The issuance of this amendment will not be inimical to the common defense and i
security or to the health and safety of the pub!ic; and 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 enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby amended to read as follows:
d 9902190320 990216 PDR ADOCK 05000374 p
~
,___....._.........m.
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 115, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented prior to restart from L2R07.
FOR THE NUCLEAR REGULATORY COMMISSION c:'kA'G) /g/'[
f'
\\
Donna M. Skay, Project Mans [
Project Directorate lil-2 Division of Reactor Project's - lil/IV Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of issuance: February 16, 1999
)
e r
l ATTACHMENT TO LICENSE AMENDMENT NO.
115 i
FACILITY OPERATING LICENSE NO. NPF-18 DOCKET NO. 50-374 l
Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and contain a verticalline l
indicating the area of change.
REMOVE INSERT 3/4 3-12 3/4 3-12 3/4 3-12a 3/4 3-13 3/4 3-13 3/4 3-15 3/4 3-15 3/4 3-15a 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 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
I I
i i
1
TABLE 3.3.2-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION I
VALVE' GROUPS MINIMUM OPERABLE APPLICABLE OPERATED BY CHANNELS PER OPERATIONAL TRIP FUNCTION SIGNAL TRIP SYSTEM (b)
CONDITION ACTION-3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
a Flow - High 5
1
- 1. 2. 3 22 b.
Heat Exchanger Area 5
1/ heat
- 1. 2. 3 22 Temperature - High exchanger c.
Heat Exchanger Area 5
1/ heat
- 1. 2. 3 22 4
Ventilation aT - High exchanger d.
SLCS Initiation 5'"
NA
- 1. 2. 3 22 e.
Reactor Vessel Water Level - Low Low. Level 2 5
2
- 1. 2. 3 22 f.
Pump and Valve Area Temperature - High 5
1/ area
- 1. 2. 3 22 g.
Pump and Valve Area Ventilation AT - High 5
1/ area-
- 1. 2. 3 22 t
l h.
Holdup Pipe Area Temperature - High 5
1
- 1. 2. 3 22 1.
Holdup Pipe Area Ventilation AT - High S
1 1, 2. 3 22 j.
Filter /Demineralizer Valve Room Area Temperature - High 5
1
- 1. 2. 3 22 k.
Filter /Demineralizer Valve Room Area Ventilation AT - High 5
1
- 1. 2. 3 22 1.
Pump Suction Flow - High 5
1
- 1. 2. 3 22 LA SALLE - UNIT 2 3/4 3-12 Amendment No.115
s
(
i.
TABLE 3.3.2-1 (Continued) j ISOLATION ACTUATION INSTRUMENTATION VALVE GROUPS MINIMUM OPERABLE APPLICABLE OPERATED BY CHANNELS PER OPERATIONAL TRIP FUNCTION SIGNAL TRIP SYSTEM (b)
CONDITION ACTION 4.
-REAGTOR CORE ISOLATION COOLING SYSTEM ISOLATION i
a.
RCIC Steam Line Flow - High 8
1 1, 2. 3 22 I
RCIC Steam Su) ply b.
Pressure
_ow
- 8. 9
2
- 1. 2. 3 22 1
l c.
RCIC Turbine Exhaust Diaphragm Pressure --High 8
2
- 1. 2. 3 22 RCIC Equi $ e Room d.
nt Tempera High 8
1
- 1. 2. 3 22 j
e.
RCIC Steam Line Tunnel i
Temperature - High 8
1
- 1. 2. 3 22 f.
RCIC Steam Line Tunnel a Temperature - High 8
1
- 1. 2. 3 22 g.
Drywell Pressure - High 9
2
- 1. 2. 3 22 h.
RCIC Equipment Room A Temperature - High 8
1
- 1. 2. 3 22 i
t i
LA SALLE - UNIT 2 3/4 3-12a Amendment No.115 l
{
i
s i
TABLE 3.3.2-1 (Continued) i l
ISOLATION ACTUATION INSTRUMENTATION i
VALVE GROUPS MINIMUM OPERABLE APPLICABLE TRIP FUNCTION
~
OPERATED BY CHANNELS PER OPERATIONAL SIGNAL TRIP SYSTEM (b)
CONDITION _
-ACTION
. 5.
DELETED l
6.
RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION I
a.
Reactor Vessel Water Level - Low. Level 3 6
2
- 1. 2. 3 25 b.
Reactor Vessel (RHR Cut-in Permissive)
I Pressure - High 6
1
- 1. 2. 3 25 5
c.
RHR Pump Suction Flow - High 6 1
- 1. 2. 3 25 B.
MANUAL INITIATION
(.
i 1.
Inboard Valves.
1.2.5.6.7 1/ group
- 1. 2. 3 26 I
8 2.
Outboard Valves l
1/ group
- 1. 2. 3 26 4"y,g,5.6 1/
- 1. 2, 3 and **.i 26 3.
Inboard Valves 4 "
1/ group
- 1. 2. 3 and **.f 26 4.
Outboard Valves 1/ group 1,2,3 26 valve 5.
Inboard Valves
- 3. 8. 9 1
6.
Outboard Valves 3,38, 9 1/ valve
- 1. 2, 3 26 7.
Outboard Valve 8
1/ group
- 1. 2. 3 26 t
i a
e r
LA SALLE - UNIT 2 3/4 3-13 Amendment No.115 1
s TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS l
ALLOWABLE l
TRIP FUNCTION TRIP SETPOINT VALUE L
A.
AUTOMATIC INITIATION i
1.
PRIMARY CONTAINMENT ISOLATION a.
Low. Level 3 2 12.5 inches
- 2 11.0 inches
- 2)
Low low. Level 2.
2 -50 inches
- 2 -57 inches
- 3)
Low Low Low. Level 1 2 -129 inches
- 2 -136 inches
- b.
Drywell Pressure - High s 1.69 psig s 1.89 psig I
c.
DELETED l
2)
Pressure - Low a 854 psig a 834 psig i
3)
Flow - High s 111 psid s 116 psid i
d.
DELETED I
e.
Main Steam Line Tunnel l
l a Temperature - High s 65'F s 70*F 6
f.
Condenser Vacuum - Low
> 7 inches Hg vacuum
> 5.5 inches Hg vacuum 2.
SECONDARY CONTAINMENT ISOLATION i
a.
Reactor Building Vent Exhaust Plenum Radiation - High s 10 mr/h s 15 mr/h b.
Drywell Pressure - High s 1.69 psig s 1.89 psig c.
Reactor Vessel Water Level - Low Low. Level 2 2 -50 inches
- 2 -57 inches
- d.
Fuel Pool Vent Exhaust Radiation - High s 10 mr/h s 15 mr/h j
3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
AFlow - High s 70 gpm s 87.5 gpm b.
Heat Exchanger Area Temperature
- High s 149'F s 156.8*F l
c.
Heat Exchanger Area Ventilation AT - High s 33*F s 40.3*F d.
SLCS Initiation N.A.
N.A.
e.
Low Low. Level 2 2 -50 inches
- 2 -57 inches
- LA SALLE - UNIT 2 3/4 3-15 Amendment No.115
1; L
' TABLE 3.3.2-2.
1 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS ALLOWABLE-i TRIP FUNCTION TRIP SETPOINT VALUE t
r f.
Pump and Valve Area Temperature - High s 201 F s 209"F l
1 g.
Pump and Valve Area Ventilation AT - High s 86*F s 92.5*F h.
Holdup Pipe Area
~
Temperature - High s 201*F s 209"F i
1.
Holdup Pipe Area Ventilation aT - High s 86*F s 92.5'F J.
Filter /Demineralizer Valve Room Area Temperature - High s 201*F s 209"F i
k.
Filter /Demineralizer Valve Room 1
Area Ventilation AT - High s 86*F
.s 92.5*F l
1 1.
Pump Suction Flow - High s 560 gpm s 610 gpm-I i
I l
i Y
i i
}
l h
[
LA SALLE - UNIT 2 3/4 3-15a Amendment No.115 i
i
n,,
s.
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS
[
. TRIP FUNCTION
-TRIP SETPOINT VALUE-
' ALLOWABLE j'
4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION la.
RCIC Steam Line Flow - High E 290% of rated flow. 178" H O s 295% of rated flow.' 185" H O
~
2 2
b.
RCIC Steam Su ply Pressure - Low 2 57 psig a 53 psig c.
RCIC Turbine Exhaust Diaphragm Pressure - High s 10.0 psig s 20.0 psig d.
- RCIC Equipment Room Temperature - High s 200*F s 206*F e.
.RCIC Steam Line Tunnel i
Temperature - High s 200 F s:206*F~
i f.
RCIC Steam Line Tunnel i
a Temperature - High s 117*F s 123*F
.g.
Drywell Pressure - High s 1.69 psig s 1.89 psig h.
RCIC Equipment Room.
AT Temperature - High s 120 F s 126 F
- 5.
DELETED
}
I I
l-4 LA SALLE - UNIT 2 3/4 3-16 Amendment No.115 L
=
m-
-..--..o
TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SETPOINTS
. ALLOWABLE
' TRIP FUNCTION TRIP SETPOINT
.VALUE 6.
RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION a.
Reactor Vessel. Water Level -
Low. Level 3 2 12.5 inches
- 2 11.0 inches
- 1 b.
Reactor Vessel (RHR Cut-in Permissive)
Pressure - High s 135 psig**
s 145 psig**-
c.
.RHR Pump Suction F1ow - High s 180" H O s 186" H,0
~
2 i
B.
MANUAL INITIATION N.A.
N.A.
1.
Inboard Valves 2.
Outboard Valves 3.
Inticard Valves 4.
Cutboard Valves 5.
Inboard Valves 6.
Outboard Valves 7.
Outboard Valve
- See Bases Figure B 3/4 3-1.
- Corrected for cold water head with reactor vessel flooded.
N.A. - Not Applicable'.
LA SALLE - UNIT 2 3/4 3-17 Amendment No.115 I
a
TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION BLS_P_QNSE TIME (Seconds)#
A.
AUTOMATIC INITIATI0f(
1.
PRIMARY CONTAINMENT ISOL ATION a.
Low. Level 3 N/A 2)
Low Low. Level 2 N/A 3)
Low Low Low. Level 1 s 1. 0*' "
b.
Drywell Pressure - High N/A c.
DELETED 2)
Pressure - Low s 2.0*** ""
3)
Flow - High s 0.5
- d.
DELETED e.
Condenser Vacuum - Low N/A f.
Main Steam Line Tunnel ATemperature - liigh N/A 2.
SECONDARY CONTAINMENT ISOLATION N/A a.
Reactor Building Vent Exhaust Plenum Radiation - High b.
Drywell Pressure - High c.
Reactor Vessel Water Level - Low. Level 2 d.
Fuel Pool Vent Exhaust Radiation - High 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION N/A a.
aFlow - High b.
Heat Exchanger Area Temperature - High c.
Heat Exchanger Area Ventilation AT-High d.
SLCS Initiation e.
Reactor Vessel Water Level - Low Low. Level 2 f.
Pump and Valve Area Temperature - High g.
Pump and Valve Area Ventilation AT - High h.
Holdup Pipe Area Temperature - High i..
Holdup Pipe Area Ventilation AT - High LA SALLE - UNIT 2 3/4 3-18 Amendment No.115
TABlF 3.3.2-3 (Continued)
A ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
j.
Filter /Demineralizer Valve Room Area Tempera..Jre - High k.
Filter /Demineralizer Valve Room Area Ventilation AT - High 1.
Pump Suction Flow - High 4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION N/A a.
RCIC Steam Line Flow - High b.
RCIC Steam Su) ply Pressure - Low c.
RCIC Turbine Exhaust Diaphragm Pressure - High d.
RCIC Equipment Room Temperature - High e.
RCIC Steam Line Tunnel Temperature - High f.
RCIC Steam Line Tunnel ATemperature - High g.
Drywell Pressure - High h.
RCIC Equipment Room ATemperature - High 5.
DELETED 6.
RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION N/A a.
Reactor Vessel Water Level - Low. Level 3 b.
Reactor Vessel (RHR Cut-In Permissive) Pressure - High c.
RHR Pump Suction Flow - High B.
MANUAL INITIATION N/A 1.
Inboard Valves 2.
Outboard Valves 3.
Inboard Valves 4.
Outboard Valves 5.
Inboard Valves 6.
Outboard Valves 7.
Outboard Valve TABLE NOTATIONS Isolation system instrumentation response time for MSIVs only.
No diesel generator delays assumed.
Isolation system instrumentation response time specified for the Trip Function l
actuating the MSIVs shall be added to MSIV isolation time to obtain ISOLATION l
SYSTEM RESPONSE TIME for each valve.
(
Sensor is eliminated from response time testing for the MSIV actuation logic circuits.
Response time testing and conformance to the administrative limits for the remaining channel including trip unit and relay logic are required.
i LA SALLE - UNIT 2 3/4 3-19 Amendment No.115
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE0VIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH i
TRIP FUNCTION-CHECK TEST CALIBRATION SURVEILLANCE REQUIRED f.
Pump and Valve Area Temperature - High NA Q
Q
- 1. 2. 3 g.
Pump and Valve Area Ventilation AT - High NA 0
0
- 1. 2. 3 h.
Holdup Pipe Area Temperature - High NA 0
0
- 1. 2. 3 i.
Holdup Pipe Area Ventilation aT - High NA 0
0
- 1. 2. 3 j.
Filter /Demineralizer Valve Room Area Temperature - High NA Q
Q.
- 1. 2. 3 k.
Filter /Demineralizer Valve Room Area Ventilation AT - High NA 0
0
- 1. 2. 3 1.
Pump Suction Flow - High S
0 R'
- 1. 2. 3 i
4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION l
l a.
RCIC Steam Line Flow - High NA 0
Q l 2. 3 l
b.
RCIC Steam Supply Pressure -
l Lmt NA Q
Q l 2. 3 c.
RCIC Turbine Exhaust Diaphragm Pressure - High NA Q
Q l 2. 3 d.
RCIC Equipment Room Temperature - High NA 0
Q l 2. 3 i
e.
RCIC Steam Line Tunnel
. Temperature - High NA Q
Q l 2. 3 f.
RCIC Steam Line Tunnel a Temperature - High NA Q
Q l 2. 3 g.
Drywell Pressure - High NA 0
Q l 2. 3 h.
RCIC Equipment Room i
a Temperature - High NA Q
Q 1 2. 3 5.
DELETED LA SALLE - UNIT 2 3/4 3-21 Amendment No.115
t l'
l TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS-CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH-TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE RE0 VIREO 6.
RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION-a.
Low Level 3 S
Q R.
- 1. 2. 3 b.
Reactor Vessel (RHR Cut-in Permissive) i Pressure-High NA 0
0
- 1. 2. 3 c.
RHR Pump Suction Flow-High NA Q
Q
- l. 2. 3 1
B.
MANUAL INITIATION l
1.
Inboard Valves NA R
NA
- 1. 2. 3
[
2.
Outboard Valves-NA R
NA
- 1. 2. 3 3.
Inboard Valves NA R
NA
- 1. 2. 3 and **.#
4.
Outboard Valves NA R
NA 1, 2.- 3 and **,#-
5.
Inboard Valves NA R
NA
- 1. 2. 3 6.
Outboard Valves NA R
NA
- 1. 2. 3 7.
Outboard Valve NA R
NA 1, 2. 3 i
i l
Not required when all turbine stop valves are not full open.
When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
i Ouring CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
r LA SALLE - UNIT 2 3/4 3 22 Amendment No.115 l
r