ML20235D792
| ML20235D792 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 07/02/1987 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235D795 | List: |
| References | |
| NUDOCS 8707100302 | |
| Download: ML20235D792 (6) | |
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COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT 1 FACILITY OPERATING LICENSE
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l License No. NPF-72 l
'1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for a license filed by Commonwealth Edison Company (the licensee) 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 Cnapter I, and all l
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 l
and the regulations of the Commission; l
C.
The facility will operate in conformity with the application, as dmended, the provisions of the Act, and the regulations of the
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Commission (except as exempted from compliance in Section 2.D.
below);.
D.
There is reasonable assurance: (1) 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 Commjssion's regulations set forth in 10 CFR Chapter I (except as exempted from compliance _in Section 2.D. below);
E.
Co5nonwealth Edison Company is. technically qualified to engage in the activities, authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F.
Commonwealth Edison Company has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; P
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G.
The issuance of this license will not be inimical to the common defense and 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-72, 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, the Partial-Initial Decisions issued May 13 and 19, 1987, as amended on May 22, 1987, by the Atomic Safety and Licensing Board in regard to this facility and pursuant to approval by the Nuclear Regulatory Commission at a meeting on June 30, 1987, Facility Operating License No. NPF-72, which supersedes FacilityOperatingLicenseNo.NPF-70issuedonMay)21,1987, 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 Commission hereby licenses:
(1) Commonwealth Edison Company (CECcr),' 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 Count.y, Illinois, in accordance with the procedures and limitations set forth in this license; (2) Ceco, pursuant to the Act and 10 CFR Rart 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;
i I (3) CECO, pursuant to the Act and 10 CFR Parts 30,'40 and 70, j
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 required; (4) CECO, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample snelysis or instrument calibration or associated with
'sicactive apparatus or components; and 200, pursuant to the Act and 10 CFR Parts 30, 40 and 70, j
a 'ossess, but not separate, such byproduct and special
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aar materials as may be produced by the operation of the.acility.
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 to 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) Naximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of 3411 megawatts thermal (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 I to this. license shall be completed as specifieo. is hereby incorporated into this license.
(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
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Protection Plan.
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(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 emergency preparedness, the provisions of 10 CFR Section50.54(s)(2)willapply.
(4) Initial Startup Test Program Any changes to the Initial Test Program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(5) Regulatory 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 required (SER Section6.2.6). 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 50.12.
With this exemption, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
Anexemptionwaspreviouslygrantedpursuantto1dCFR70.24. The exemption was granted with NRC materials license No. SNM-1938, issued October 8, 1985, and relieved the licensee from the requirement 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
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Final Safety Analysis Report, as supplemented and amended, and j
as approved in the SER dated November 1983'and its supplements, subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve end 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 qualification, 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 Information protected under 10 CFR 73.21, are entitled:
"Braidwood Station Physical Security Plan, Security Personnel Training and Qualification Plan,* and Safeguards Contingency Plan *" with revisions submitted through May 27, 1986..
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 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 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 date of issuance and shall expire at midnight on October 17, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION
$ h&--
Thomas E. Murley, Director Office of Nuclear Reactor Regulation Attachments:
1.
Work Items to be completed 2.
Appendix A - Technical Specifications (NUREE-1276) 3.
Appendix.B. - Environmental Protection Plan Date of Issuance: July 2, 1987
- 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."
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ATTACHMENT 1 This attachment identifies specific items which must be completed to the Commission's satisfaction in accordance with the operational modes as identified below.
The interim operation plan for the Auxiliary Building Ventilation (VA) System will be conducted in accordance with letters S. C. Hunsader to A. Bert Davis dated June 26, 1987, S. C. Hunsader to Thomas E. Murley dated June 23, 1987, S. C. Hunsader to Thomas E. Murley dated June 11, 1987, and A. D. Miosi to Harold R. Denton dated August 26, 1986.
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