ML20062L194
| ML20062L194 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/10/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20062L197 | List: |
| References | |
| NUDOCS 9312290227 | |
| Download: ML20062L194 (8) | |
Text
. _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _
enauqjo UNITED STATES g
. [
( j'a j NUCLEAR REGULATORY COMMISSION g
WASHlfwGTON, D. C. 20555 g
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[QMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE COUNTY STATION. UNIT 1 AMENDMENT TO FACILITY OPEPATING LICENSE Amendment No. 92 License No. NPF-11 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 29, 1993, 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 i
provisions of the Act, and the regulations of the Commission; i
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 i
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 Specifications as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-ll is hereby amended to read as follows:
l l
l 9312290227 931210 PDR ADOCK 05000373 p
. (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
92, 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 amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION fL f.
OV James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 10, 1993
ATTACHMENT TO LICENSE AMENDMENT NO. 92 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 6-34 3/4 6-34 i
f
TABLE 3.6.3-1 (Continued)
. 52 s?
PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER
-m 5
. 0ther Isolation Valves (Continued)
-d 7.
Post LOCA Hydroaen Control 1HG001A, B lHG002A, B 1HG005A, B 1HG006A, B I
8.
Standby Liauid Control System 1C41-F004A, B 1C41-F007 u31 9.
Reactor Recirculation Seal In.iection e3 VJ s
U 1833-F013A, B )
t U
IB33-F017A, B )
10.
Drywell Pneumatic System IIN018 11.
Reference Lea Backfill IC11-F422B ICll-F422D ICll-F422F 1Cll-F422G 1Cll-F423B IC11-F423D g
ICll-F423F g
IC11-F423G a
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION 5
ap WASHINGTON, D, C. 20555
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 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 October 29, 1993, 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; 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: (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 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 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:
I,
(2)
Iechnical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 76, 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 amendment is effective upon date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 14 f.
SV James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 10, 1993 i
l ATTACHMENT TO LICENSE AMENDMENT NO. 76 FACILITY OPERATING LICENSE NO. NPF-18 j
DOCKET NO. 50-374 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 t
3/4 6-37 3/4 6-37 i
r I
s b
t
TABLE 3.6.3-1 (Continued) h{
PRIMARY CONTAINMENT' ISOLATION VALVES
[{
VALVE FUNCTION AND NUMBER
[
Other Isolation Valves (Continued) 2-El 7.
Post LOCA Hydronen Control m
2HG001A, B 2HG002A, B 2HG005A, B 2HG006A, B~
8.
Standby Liauid Control System i
4 2C41-F004A, B 2C41-F007 u,
s s
[
9.
Reactor Recirculation' Seal In.iection 2B33-F013A, B(D 2B33-F017A, B(D
- 10. Drywell Pneumatic System 2IN018 11.
Reference Leo Backfill 2Cll-F4228 2Cll-F422D
-2Cll-F422F 2Cll-F422G f
i' 2C11-F423B 2Cll-F423D i
3, 8
E 5
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