ML20214T462
| ML20214T462 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/02/1987 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20214T464 | List: |
| References | |
| NUDOCS 8706100280 | |
| Download: ML20214T462 (7) | |
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WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDFOOD STATION, UhIT 1 FACILITY OPEP.ATING LICENSE License No. NPF-70 1.
The Nuclear Regulatory Commission (the Comission or the NRC) has found that:
A.
The application for a license filed by Comonwealth Edison Company (the licensee) 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, and all required notifications to other agencies or bodies have been duly made; B.
Construction of Braidwood Station, Unit 1 (the facility) has been substantially completed in conformity with Construction Permit No.
i CPPR-132 and the application, as amended, the provisions of the Act and the regulations of the Comission; C.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Comission (except as exempted from compliance in Section 2.D.
below);
4 D.
There is reasonable assurance: (11 that the activities authorized by this operating license 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 furth in 10 CFR Chapter I (except as exempted from compliance in Sectton 2.D. below);
E.
Comonwealth Edison Company is technically qualified to engage in the activities authorized by this license in accordance with the Comission's regulations set forth in 10 CFR Chapter It i
F.
Comonwealth Edison Company has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Comission's regulations; I
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The issuance of this license will not be inimical to the common defense end security or to the health and safety of the public; H.
After weighing the environmental, economic, technical, and.other benefits of the facility against environmental and other costs and considering available alternatives, the issuance of Facility Operating License No. NPF-70, subject to the conditions for protection of the environment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied; and I.
The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70.
2.
Based on the foregoing findings regarding this facility, Facility Operating License No. NPF-70, which supercedes Facility Operating License No. NPF-59 issued en October 17, 1986, is hereby issued to Commonwealth Edison Company (the licensee) to read as follows:
A.
This license applies to Braidwood Station, Unit 1, a pressurized water reactor, and associated equipment (the facility) owned by Commonwealth Edison Company. The facility is located in north -
eastern Illinois, 3 miles southwest of the Kankakee River, 20 miles south-southwest of the town of Joliet, and 60 miles southwest of Chicago, Illinois. The facility is within Reed Township, Will County, Illinois and is described in the Byron /Braidwood Stations' Final Safety Analysis Report, as supplemented and amended, and in the Environmental Report, as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Comission hereby licenses:
(1) Commonwealth Edison Company (CECO), pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the above designated location in Will County, Illinois, in accordance with the procedures and limitations set forth in this license; (2) CECO, pursuant to the Act and 10 CFR Part.70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (3) CECO, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as requi red;
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' (4) CECO, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as reoufred any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) CECO, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject te all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level 4
The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thennal (100 percent rated power) in accordance with the conditions specified herein and other items identified in Attachment 1 to this license.
The items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license. Pending Commission approval, this license is restricted to power levels not in excess of five percent of rated power (170 megawatts thermal).
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Emergency Planning In the event that the NRC finds that the lack of progress in completion of the procedures in the Federal Emergency Management Agency's final rule, 44 CFR Part 350, is an indication that a major substantive problem exists in achieving or maintaining an adequate state of emeroency preparedness, the provisions of 10 CFR Section 50.54(s)(2) will apply.
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(4)
Initial Startup Test Prooram Any changes to the. Initial Test Program de' scribed in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.F9 shall be reported in accordance with 50.59(b) within one month of such change.
(5) Reoulatory Guide 1.97, Revision 2 Compliance The licensee shall submit the final report and a schedule for implementation within six months of NRC approval of the DCRDR.
D.
The facility requires an exemption from the requirements of Appendix J to 10 CFR Part 50, Paragraph III.D.2(b)(ii), the testing of containment air locks at times when containment integrity is not reouired (SER Section 6.2.6).
This exemption is authorized by. law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. This exemption is hereby granted.
The special circumstances regarding this exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. This exemption is granted pursuant to 10 CFR 90.12.
With this exemption, the. facility will operate, to the extent authorized herein, in confomity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission.
An exemption was previously granted pursuant to 10 CFR 70.24.~ The exemption was granted with NRC materials license No. SNM-1938, issued October 8,1985, and relieved the licensee from the reouirement of having a criticality alarm system.. Therefore, the licensee is exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.
E.
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report, as supplemented and amended, and as approved in the SER dated November 1983 and its supplements, sub,iect to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Comission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
F.
The licensee shall fully implement and maintain in effect all provisions of the physical security, guard training and qualifir.ation, and safeguards contingency plans previously approved by the Commission and all amendments and revisions to such plans made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Infomation protected under 10 CFR 73.21, are entitled:
"Braidwood Station Physical Security Plan, Security Personnel Training and Qualification Plan,* and Safeouards Contingency Plan *" with revisions submitted throuch May 27, 1986.
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i G.
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this i
license in the following manner:
initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency Notification System with written _ followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c),
and(e).
H.
The licensee shall have and maintain financial protection of such 1
type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
I.
This license is effective as of the ddte of issuance and shall expire at midnight on May 21
, 2026.
t FOR THE NUCLEAR REGULATORY COMMISSION s
I s
1 Thomas E. Murley, Director Nx Office of Nuclear Reactor Regulation x-Attachments:
1.
Work Items to be completed i
2.
Appendix A - Technical Specifications (NUREG-1261) 1 3.
Appendix B - Environmental Protection Plan 1
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- The Security Personnel Training and Qualification Plan and the Safeguards Contingency Plan are Appendices to the Security Plan.
As requested by CECO letter dated April 22, 1983, Revision 6 is to be considered "the initial formal submittal."
s
" G.
Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirments contained in Section 2.C of this license in the following manner:
initial notification shall be made within 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> to the NRC Operations Center via the Emergency l
Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c),
and fel.
H.
The licensee shall have and maintain financial protection of such type and in such amounts as the Comission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as l
arnended, to cover public liability claims.
T.
This license is effective as of the date of issuance and shall expire at midnight on
, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas E. Murley, Director Office cf Nuclear Reactor Regulation Attachments:
1.
Vork Items to be completed 2.
Appendir A - Technical Specifications (NUREG-12611 3.
Appendix P - Environmental Protection Plan PDf3)
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- The Security Persnnnel Training and Qualification Plan and the Safeguards Contingency Plan are Appendices to the Security Plan. As reouested by CECO letter dated April 22, 1983, Revision 6 is to be considered "the initial formal submittal."
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A ATTACPMENT 1 This attachment identifies specific iterns which must be completed to the Commission's satisfaction in accordance with the operational modes as identified below.
The preoperational testing exceptions identified in the Septenher 19, 1986, letter from Dennis Farrar to Harold R. Denton shall be completed in accordance i
with the scheduled commitments contained in that letter.
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