ML20206K342
| ML20206K342 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  (NPF-018) |
| Issue date: | 04/14/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20206K345 | List: |
| References | |
| NPF-18-A-031 NUDOCS 8704160330 | |
| Download: ML20206K342 (6) | |
Text
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'o UNITED STATES 8
N NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 20555 e'.'....,o COMMONWEALTH EDISON COMPANY DOCKET N0. 50-374 LA SALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 31 License No. NPF-18 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated February 26, 1987, 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; D.
The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-18 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Pian The Technical Specifications contained in Appendix A, as revised through Amendment No.
, and the Environmental Protection Plan contained in Appendix B are hereby incterporated in the license. The licensee shall j
operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8704160330 870414 PDR ADOCK 05000374 P
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This amendment is effective upon startup following the first refueling outage.
FOR THE NUCLEAR REGULATORY COMMISSION l k$
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Daniel R. Muller, Director i
Project Directorate III-2 Division of Reactor Projects
Enclosure:
Changes to the Technical Specifications t
Date of Issuance: April 14, 1987 I
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ENCLOSURE TO LICENSE AMENDMENT NO. 31 FACILITY OPERATING LICENSE NO. NPF-18 4
DOCKET NO. 50-374-Replace the following pages of the Appendix A Technical. Specifications with q
the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4 3-26 3/4 3-26 3/4 3-30(a) 3/4 3-30(a) 3/4 3-34 3/4.3-34 i
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TABLE 3.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION E
MINIMUM OPERABLE APPLICABLE CHANNELS PER TRIP OPERATIONAL c
3 TRIP FUNCTION FUNCTION (a)
CONDITIONS ACTION C.
DIVISION 3 TRIP SYSTEM 1.
HPCS SYSTEM a.
Reactor Vessel Water Level - Low, Low, Level 2 4
1, 2, 3, 4*, 5*
35 b.
Drywell Pressure - High 4(c) 1, 2, 3 35 c.
Reactor Vessel Water Level-High, Level 8 2(d) 1, 2, 3, 4*, 5*
32 d.
Condensate Storage Tank Level-Lew 2(d) 1, 2, 3, 4*, 5*
36 e.
Suppression Pool Water Level-High 2
1, 2, 3, 4*, 5*
36 w
f.
Pump Discharge Pressure-High (Bypass) 1 1, 2, 3, 4*, 5*
31 A
g.
HPCS System Flow Rate-Low (Permissive) 1 1, 2, 3, 4*, 5*
31 w
h.
Manual Initiation 1/ division 1, 2, 3, 4*, 5*
34 D.
LOSS OF POWER MINIMUM TOTAL NO.
INSTRU-OPERABLE APPLICABLE OF INSTRU-MENTS TO INSTRU-OPERATIONAL MENTS TRIP MENTS(a)
CONDITIONS ACTION 1.
4.16 kV Emergency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4**, 5**
37 (Loss of Voltage) 2.
4.16 kV Emergency Bus Undervoltage 2/ bus 2/ bus 2/ bus 1, 2, 3, 4**, 5**
37 (Degraded Voltage) l TABLE NOTATION E
(a) A channel / instrument may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during periods of required e
E surveillance without placing the trip system / channel / instrument in the tripped condition provided at least 3
one other OPERABLE channel / instrument in the same trip system is monitoring that parameter.
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(b) Also actuates the associated division diesel generator.
(c) Provides signal to close HPCS pump discharge valve only on 2-out-of-2 logic.
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(d) Provides signal to HPCS pump suction valves only, Applicable when the system is required to be OPERABLE per Specification 3.5.2 or 3.5.3.
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Required when ESF equipment is required to be OPLRABLE.
Not required to be OPERABLE when reactor steam dome pressure is < 122 psig.
5; TABLE 3.3.3-2 (Continued) u,
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EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS A
ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE g
- 1 D.
LOSS OF POWER (Continued)
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2.
4.16 kV Emergency Bus Undervoltage (Degraded Voltage) a.
4.16 kV Basis 4
- 1) Divisions 1, 2 and 3 3814 i 76 volts with 3814 i 76 volts with l 10 1 1 seconds time 10 i 1 seconds time delay delay with LOCA signal with LOCA signal 4
Or or 5 1 0.5 minutes time 5 1 0.5 minutes time delay delay without LOCA without LOCA signal g
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signal l
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g TABLE 4.3.3.1-1 (Continued) h EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR W'iICH c
z.E TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED w
N C.
DIVISION 3 TRIP SYSTEM 1.
HPCS SYSTEM a.
Low Low, Level 2 NA M
R 1, 2, 3, 4*, 5*
b.
Drywell Pressure-High NA M
Q 1, 2, 3 c.
Reactor Vessel Water Level-High Level 8 NA M
R 1, 2, 3, 4*, 5*
d.
Condensate Storage Tank Level -
R Low NA M
Q 1, 2, 3, 4*, 5*
e.
Suppressior. Pool Water y
Level - High NA M
Q 1, 2, 3, 4*, 5*
g f.
Pump Discharge Pressure-High NA M
Q 1, 2, 3, 4*, 5*
g.
HPCS System Flow Rate-Low NA M
Q 1, 2, 3, 4*, 5*
h.
Manual Initiation NA R
NA 1, 2, 3, 4*, 5*
D.
LOSS OF POWER 1.
4.16 kV Emergency Bus Under-NA NA R
1, 2, 3, 4**, 5**
voltage (Loss of Voltage) 2.
4.16 kV Emergency Bus Under-NA NA R
1, 2, 3, 4**, 5**
voltage (Degraded Voltage) y TABLE NOTATIONS M
g.
- Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 122 psig.
E
- When the system is required to be OPERABLE after being manually realigned, as applicable, per
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Specification 3.5.2.
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