ML20148B066
| ML20148B066 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/16/1988 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co |
| Shared Package | |
| ML20148B070 | List: |
| References | |
| NPF-11-A-056, NPF-18-A-037 NUDOCS 8803210334 | |
| Download: ML20148B066 (8) | |
Text
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jo UNITED STATES g
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p, NUCLEAR REGULATORY COMMISSION E
WASHINGTO N, D. C. 20555 5
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COMMONWEALTH EDISON COMPANY DOCKE.T NO. 50-373 LASALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. NPF-11 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Comonwealth Edison Company (the licensee), dated November 9,1987, 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; B.
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 comon 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the enclosure to this license amendment and para-graph 2.C.(2)oftheFacilityOperatingLicenseNo.NPF-11ishereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 56, and the Env,ronmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specif1-cations and the Environmental Protection Plan.
8803210334 880316 DR ADDCK 0500 3
3.
This amendment is effective 45 days after the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Garrn Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance: March 16,1988 l
l l
e 6
ENCLOSURE TO LICENSE AMENDHENT N0. 56 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following page of the Appenoix "A" Technical Specifications with the enclosed page. The revised page is identif!ed by Amendment number and contains a vertical line indicating the area of change.
REMOVE INSERT 6-4 6-4 A
ADMINISTRATIVE CONTROLS review coverage under this function, (4) independently review and approve the findings and recommendations developed by personnel performing the review and investigative function, (5) approve and report in a timely manner all findings of non-compliance with NRC requirements to the Station Manager, Assis-tant Vice President and General Manager - Nuclear Stations, Manager of Quality Assurance, and the Vice Pre,ident - Nuclear Operations.
During periods when the Superintendent of Offsite Review and Investigative Function is unavailable, he shall designate this responsibility to an established alternate, who satisfies the formal training and experience for the Super-intendent of the Offsite Review and Investigate Function.
The responsibilities of the personnel performing this function are stated below.
The Offsite Review and Investigative Function shall review:
1)
The safety evaluations for (1) changes to procedures, equipment, or systems as described in the safety analysis report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.
Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of Quality Assurance.
2)
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR o0.59, 3)
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
4)
Proposed changes in Technical Specifications or NRC operating licenses.
5)
Noncompliance with NRC requirements, or of internal procedures, or instructions having nuclear safety significance.
6)
Significant operating abnormalities or deviation from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.
7)
All REPORTABLE EVENTS.
8)
All recognized indications of an unanticipated deficiency l
in some aspect of design or operation of safety-related structures, systems, or components.
9)
Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change.
- 10) Review and report findings and recomtrendations regarding all items referred by the Technical Staff Supervisor, Sta-tion Manager, Assistant Vice President and General Manager -
Nuclear Stations, and Manager of Quality Assurance.
LA SALLE - UNIT 1 6-4 Amendment No. 56
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UNITED STATES NUCLEAR REGULATORY COMMISSION 3
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- j WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-374 LASALLE COUNTY STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-18 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by the Comenwealth Edison Company (the licensee), dated November 9,1987, 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; B.
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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of l
the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the enclosure to this license amendment and para-graph 2.C.(2) of the Facility Operating License No. NPF-18 is hereby l
amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 37, 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 Specifi-cations and the Environmental Protection Plan.
3.
This amendrnent is effective 45 days after the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A
f t.
/d ?b<dA. -
Am Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Enclosure:
Changes to the Technical Specifications Date of Issuance: March 16,1988 M
4
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ENCLOSURE TO LICENSE AMENDMENT N0. 37
~
FACILITY OPERATING LICENSE NO. NPF-18 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 contain a vertical line indicating the area of change.
REMOVE INSERT 6-4 6-4 l
l
~
O ADMINISTRATION CONTROLS
~
Offsite Review and Investigative Function (Continued)
(5) approve and report in a timely manner all findings of non-compliance with NRC requirements to the Station Manager, Assis-tant Vice President and General Manager - Nuclear Stations, Manager of Quality Assurance, and the Vice President - Nuclear Operations.
During periods when the Superintendent of Offsite Review and Investigative Function is unavailable, he shall designate this responsibility to an established alternate, who satisfies the formal training and experience for the Superin-tendent of the Offsite Review and Investigate Function.
The responsibilities of the personnel performing this function are stated below.
The Offsite Review and Investigative Function shall review:
1)
The safety evaluations for (1) changes to procedures, equipment, or systems as described in the safety analysis report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.
Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of Quality Assurance.
2)
Proposed changes to proccdures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
3)
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
4)
Proposed changes in Technical Specifications or NRC operating licenses.
5)
Noncompliance with PRC requirements, or of internal procedures, or instructions having nuclear safety significe.nce.
6)
Significant operating abnormalities or deviation from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.
7)
All REPORTABLE EVENTS.
8)
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.
9)
Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change.
l
- 10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Assistant Vice President and General Manager -
Nuclear Stations, and Manager of Quality Assurance, l
LA SALLE - UNIT 2 6-4 Amendment No. 37 l
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