ML20205Q524
| ML20205Q524 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/31/1987 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20205Q528 | List: |
| References | |
| DPR-62-A-135, DPR-71-A-105 NUDOCS 8704030554 | |
| Download: ML20205Q524 (6) | |
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. DPR-71 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated August 7,1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and 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 rules and regulations of the Comission; 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 Comission's regulations; 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 Comission's regulations and all applicable requirements have been satisfied.
l 2.
Accordingly, the license is amended by changes to paragraph 2.B.(4) of Facility Operating License No. DPR-71 as indicated in the attachment.
8704030554 870331 PDR ADOCK 05000324 P
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Page 3 of Facility Operating License No. DPR-71 Date of Issuance: March 31, 1987
. (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use in amounts as required any byproduct, source and
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A special nuclear material without restriction to chemical or physical 105 form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70 to possess, but not Amdt No i separate, such byproduct and special nuclear materials as may be 9
produced by the operation of Brunswick Steam Electric Plant, Unit Nos. I and 2, and H. B. Robinson Steam Electric Plant, Unit No. 2.
(6) The licensee may proceed with and is required to complete the
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modifications identified in Paragraphs 3.1.1 through 3.1.35 of the 23 NRC's Fire Protection Safety Evaluation Report on the Brunswick facility dated November 22, 1977 and supplements thereto. These modifications shall be completed by the dates identified in the Safety Evaluation Report or Table 3.1 in supplements thereto.
In addition, the licensee may proceed with and is required to complete the modifications identified in Section B.2.1 of Supplement I to the i
Fire Protection Safety Evaluation Report, and any future supplements.
I These modifications shall be completed by the dates identified in Table R.7,1 of the sunnlemont, C.
This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30 Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions o# 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 Amdt No 1
The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2436 megawatts thermal.
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.104 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDHENT TO FACILITY OPERATING LICENSE Amendment No.135 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Com.ission) has found thet:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated August 7, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and 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 rules and regulations of the Conmission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health 1
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by replacing paragraphs 2.B(4) and 2.B 5) of Facility Operating License No. DPR-62 with new paragraph 2.B and renumbering paragraphs 2.B(6) and 2.B(7) to be 2.B(5) and 2.8 as indicated in the attachment.
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller Director BWR Project Directorate #2 Division of BWR Licensing
Attachment:
Page 3 of Facility Operating License No. DPR-62 Date of Issuance: March 31, 1987 I
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i n (2) 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) 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 required; (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, Andt No possess and use in amounts as required any byproduct, source, and 135 special nuclear materials without restriction to chemical or physical fom, for sample analysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Part 30 and 70 to possess, but not Andt Nos separate, such byproduct and special nuclear materials as may be 34,135 produced by the operation of Brunswick Steam Electric Plant, Unit Nos. 1 and 2, and H. B. Robinson Steam Electric Plant, Unit No. 2.
(6) The licensee may proceed with and is required to complete.the Andt Nos modifications identified in Paragraphs 3.1.1 through 3.1.35 of the 47,135 NRC's Fire Protection Safety Evaluation Report on the Brunswick facility dated Noveanber 22, 1977 and supplements thereto. These i
modifications shall be completed by the dates identified in the i
Safety Evaluation Report or Table 3.1 in supplements thereto.
In.
I addition, the licensee may proceed with and. is required to complete the modifications identified in Section B.2.1 of Supplement 1 to the i
Fire Protection Safety Evaluation Report, and any future supplements.
These modifications shall be completed by the dates identified in Table B.2.1 of the supplement.
C.
This license shall be ' deemed to contain and is subject to the conditions specified in the following Comission regulations in 10 CFR Chapter I:
Part 20. Section 30.34 'of Part 30, Section 40.41 of Part 40, S2ctions 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; 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) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2436 megawatts (thermal).
I
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