ML20197A534
| ML20197A534 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  (NPF-11-A-123, NPF-18-A-108) |
| Issue date: | 02/17/1998 |
| From: | Skay D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20197A540 | List: |
| References | |
| NUDOCS 9803090279 | |
| Download: ML20197A534 (8) | |
Text
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NUCLEAR RE2VLATORY CEMMISSION WASHINGTON, D.C. IDe46-0001 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-373 LASALLE C_ OUNTY STATION. UNIT 1 (MENDMENT TO FACILITY OPERATING LICENSE Amendment No.123 License No. NPF 11 1.
The Vaclear Regulatory C.mmission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Co,npany (the licensee), dated October 15,1997, complies with the standards and :equirements 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 cf tne Act, and the regulations of the Commission; C.
Theio is reasonable assurance: (i) that the activities authorized by this anvendment 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 tha 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.
According% the license is amended by changes to the Tec,hnical Specifications as indicated in the enclosure to this license amendment and parayaph 2.C.(2) of the Facility Operating License No. WPF 11 is hereby amended to read as follows:
9803090274 900217 PDR ADOCK 05000373 p
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2 Technical See - fications and Environmental Protection Plan J
(2)
The Technical specifications contained in Appendix A, as revised through Amendment No. 123, 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 Environmerital Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented pric to startup from L1F35.
FOR THE NUCLEAR REGULATORY COMMISSION M
Donna M. Skay, Project anager Project Directorate 1112 Division of Reactor Projects lil/lV office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
February 17, 1998
. _ = -
ATTACHMENT TO LICENSE AMENDMENT NO. in 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 pa0e is identir.ed by ameadment number and contains a verticalline indicating the area of change, REMOVE lHSEBI 3/4 3-71 3/4 3-71 1
i TABSE 4.3."J.5-1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REOUIREMENTS l
CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.
Jteactor Vessel Pressure M
R i
2.
R 4
1 3.
Suppression M m=har Water Level M
R 1
4.
Suppression M m=har Water Temperature M
R 5.
Suppression Chamber Air Temperature M
R 6.
Primary Containment Presrurs M
R j
4 l
7.
Drywell Air Temperature M
R 8.
Drywell Oxygen Concentrstion M
R 9.
Drywell Nydrogen Concentration Analyzer and Monitor M
Q
- 10. Primary contaip=nnt Gross Gamma Radiation M
R
- 11. Safety /iitelief valve Position Indicators M
R
- 12. 23oble Gas Monitor, Main Stack M
R l
- 13. Moble Gas Monitor, Standby Gas Treatment System Stack M
R l
1 i
^
LA Y* - UNIT 1 3/4 3-71 Amendment No.
123
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t UNITED STATES s
NUCLEAR HE2ULATCRY CEMMISSIEN WAbVfMOToN, D.C. =^ aaat COMMONWEALTH EDISON COMPANY DOCKET No. 50 3N LASALLE COUNTY STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. NPF 18 t.
The Nucleat Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by the Commonwealth Edison Company (the licensee), dated October 15,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulatione 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 Comtrl ssion; 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, cnd (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 amundment is in acco-dance with 10 CFR Part 51 of the Com:nission'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:
l 2-(2)
Itchnical Soecificaiions and Environmental Protection Pian The Techn! cal Specifications contained in Appendix A, as revised through Amendmor.t No.
108, and the Environmental Protection Plan con'.alned in Appendix B, are hereby incorporated in the license. Tho licensee 7,htmil opera'e the facili'y in accordance with the Technical Specifications and list, Environmsnial Protection Plan.
3.
This license amendment is effective as of the date of its issuance ar.d shall t,0 Implemented prior to restart from L2R07.
FOR THE NUCLEAR REGULATORY COMMISSION Donna M. Skay, Projer:t Manager Project Directorate lll 2 Division of Reactor Projects -lil/lV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Techn!cel Specifications Date of issuance:
February 17, 1998
ATTACHMENT TO LICENSE AMENDMENT NO. 108 FACILITY OPERelt$ LICENSE NO. NPF-18 DOCKET NO. 50-374 i
\\
Replace the following paces of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
REMOVE
.UEERI 3/4 3 71 3/4 3-71
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i I
}
TABLE 4.3.7.5-I 4
&CCIDENT MONITORING INSTRUMENTATION E'IRVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUME3fT CHECK CALIBRATICE 4
1 1
1.
Reactor vessel Pressure M
R 1
I 2.
Reactor Vessel Water I4 vel M
R 1
3 3.
Suppression ^==har Water Level M
R 4.
Suppression Chamber Water Temperature M
R 5.
Suppressica Chanaber Air Temperature M
R l
6.
Primary Containment Pressure M
R i
7.
Drywell Air Temperature M
R
.l 8.
Drywell Oxygen Concentration M
R a
9.
Drywell Hydrogen Concentration Analyzer and Monitor M
Q l
- 10. Primary Conta' oent Gross Gaema Radiation M
R
- 11. Safety / Relief Valve Position Indicators M
R
- 12. moble Gas Monitor, Main Stack M
R I
- 13. 'doble Gas Monitor, Stam9hy Gas Treatment System Stack M
R r
i j
i 1
i i
LA urr.= - UNIT 2 3/4 3-71 Amendeent no.108 l
A
.