ML20141P104
| ML20141P104 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/13/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141P105 | List: |
| References | |
| NUDOCS 8603190007 | |
| Download: ML20141P104 (4) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION G
j WASHINGTON, D. C. 20555 COMMONWEALTH EDIS0N COMPANY DOCKET N0. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 36 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Comission or the NRC) having found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated January 9, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 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 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 the Facility Operating License No. NPF-11 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. 36, 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.
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. 3.
This amendment is effective as of date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b-ot
&w Elinor G. Adensam, Director BWR Project Directorate No. 3 Division of BWR Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance: 'A."
i! 1+t I.
l ENCLOSURE TO LICENSE AMENDMENT NO. 36 3
FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 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.
REMOVE INSERT 3/4 3-18 3/4 3-18 i
i 1
i I
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TABLE 3.3.2-3 ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TRIP FUNCTION RESPONSE TIME (Seconds)#
A.
AUTOMATIC INITIATION 1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3 NA 4
12.g<13(,)na 2)
Low Low, Level 2 b.
Drywell Pressure - High
< 13 c.
Main Steam Line Ib) 1)
Radiation - High
< 1.0*/< 13(a)**
2)
Pressure - Low 7 1.0*R 13(a)**
3)
Flow - High 7 0.5*R 13(a)a*
d.
Main Steam Line Tunnel Temperature - High NA 4
e.
Condenser Vacuum - Low NA f.
Main Steam Line Tunnel a Temperature - High NA 2.
SECONDARY CONTAINMENT ISOLATION Reactor Building (gnt Exhaust Plenum a.
Radiation - High
< 13(,)
b.
Drywell Pressure - High 7 13((a).
a Reactor Vessel Water Level - Low, Level 7 13
)
c.
FuelPoolVentExhaustRadiation-High(g) 513(a) i d.
3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
A Flow - High
< 13(a)##
b.
Heat Exchanger Area Temperature - High RA Heat Exchanger Area Ventilation AT-High NA c.
d.
SLCS Initiation NA Reactor Vessel Water Level - Low Low, Level 2 1 13(a) e.
4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION RCIC Steam Line Flow - High
< 13(a)###
a.
b.
RCIC Steam Supply Pressure - Low 513(a)
RCIC Turbine Exhaust Diaphragm Pressure - High NA c.
d.
RCIC Equipment Room Temperature - High NA RCIC Steam Line Tunnel Temperature - High NA e.
f.
RCIC Steam Line Tunnel a Temperature - High NA i
g.
Drywell Pressure - High NA h.
RCIC Equipment Room a Temperature - High NA 5.
RHR SYSTEM STEAM CONDENSING MODE ISOLATION RHR Equipment Area a Temperature - High NA a.
b.
RHR Area Cooler Temperature - High NA c.
RHR Heat Exchanger Steam Supply Flow High NA LA SALLE - UNIT 1 3/4 3-18 Amendment No. 36
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