ML20066K770

License DPR-19 to Operate Facility at steady-state Reactor Core Power Levels Not in Excess of 2527 Mwt

ML20066K770
Person / Time
Site:	Dresden
Issue date:	02/20/1991
From:	Murley T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20066K773	List: ML20066K770
References
NUDOCS 9102280077
Download: ML20066K770 (5)

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COMMONWEALTH EDISON COMPANY D_0CKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 FACILITY OPERATING LICENSE License No. DPR-19 1.

The Nuclear Regulatory Commission (the Commission) has found that; A.

The application for a license filed by the 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 Chapter I, and all required notifications to other agencies or bodies have been duly made; B.

Construction of the Dresden Nuclear Power Station, Unit 2 (the facility) has been completed in conformity with Construction Permit No. CPPR-18 and the application, as amended, the provisions of the Act, and the regulations of the Commission, and has been operating under a provisional license since December 22, 1969; C.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission (except as exempted from compliance in Section 2.0.

below);

D.

~There is reasonable assurance (i) that the activities authorized by this operating license can be conducted without endangering the bealth and safety of the public, and (ii) that such activities will t,e conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.0. beles);

E.

Commonwealth Edison Company is technically qualified to engage in the activities authorized by this license, as amended, 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; 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; I

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H.

The issuance of this license 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,horized by this license will be in accordance and use of source, byproduct and special nuclear raterials as aut with the Connission's regulations in 10 CFR Parts 30, 40 and 70.

2.

Provisional Operating License No. DPR-19, dated December 22, 1969 as amended, is superseded in its entirety by Facility Operating Licen,se No.

DPR-19 hereby issued to Conrnonwealth Edison Company (the licensee or CECO) to read as follows:

A.

This license applies to the Dresden Nuclear Power Station Unit 2, a boiling water reactor and associated equipment (the faci 1Ity).

The facility is located in Grundy County, Illinois, and is described in the licensee's Updated Final Safety Analysis Report, as supplenented i

and amended, and in the licensee's Environinental Report, at supplenented and amended.

B.

Subject to the conditions and requirements incorporated herein, the l

Commission hereby licenses:

(1) Ceco, pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the desig sted location in Grundy 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, l

possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and announts required for reactor o>eration, as described in the Updated final Safety Analysis leport, as suppienented and amended; (3)

CECO pu receive,rsuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, and use at any time any byproduct, source and I

special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and l

radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Ceco pu receive,rsuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibraticn or associated with radioactive apparatus or l

components; and

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3 (5) CECO, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct 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 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 2527 megawatts thermal (100 percent rated power) in accordance with the condit. ions specified herein.

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 113. are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Operation in the constdown mode is permitted to 40% power.

(4) The valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation.

D.

The facility has been granted certain exemptions from the require-ments of Section III.G of Appendix R to 10 CFR Part 50, " Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979 " This section relates to fire protection features for ensuring the systems and associated circuits used to achieve and maintain safe shutdown are free of fire damage.

These exemptions were granted and sent to the licensee in letters dated February 2, 1983, September 28, 1987 and August 15, 1989.

In addition, the facility has been granted certain exemptions from Sections II and III of Appendix J to 10 CFR Part 50, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors." This section contains leakage test requirements, schedules and acceptance criteria for tests of the lenk-tight integrity of the primary reactor containment and systems and components which penetrate the containment.

These exemptions were granted and sent to the licensee in a letter dated June 25, 1982.

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4 These exemptions granted pursuant to 10 CFR 50.12 are authorized by 4

law, will not present an undue risk to the pubiic health and safety, and are consistent with the common defense and security.

With these exemptions, the facility will operate, to the extent authorized i

herein, in conformity with the application, as amended, the provisions

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of the Act, and the rules and regulations of the Commission.

E.

Commonwealth Edison Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated final Safety Analysis Report for the facility and as approved in the $afety Evaluation Reports dated March 22, 1978 with supplements dated December 2,1980, and February 12, 1981; January 19, l

e 1983; July 17 1987 September 28, 1987; and January 5,1989, subject tothefollowIngpro; vision:

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 and maintain safe shutdown in the event of a fire.

F.

The licensee shall fully implement and maintain in effect all provi-sions of the Commission approved physical security, guard training and n @.Mication, and safeguards contingency plans including amend.

men n made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10'CFR 50.90 and 10 CFR 50.54(p). The plans, which contein Safeguards Information protected under.10 CFR 73.21, are entitled: "Dresden Nuclear Power Station Security Plan," with revisions submitted through October 30,1990; "Dresden Nuclear power Station Security personnel Training and Qualification plan," with revisions submitted through October 30.-1990; and "Dresden Nuclear power Station Safeguards-Contingency Plan," with revisions submitted through October 30, 1990.

Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

G.

Except as otherwise provided in the Technical Specifications, the licensee shall report any violations of the requirements contained in 4

Section-2.0-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 follow-up within 30 days in accordance with the procedures described in 10 CTR 50.73(b),(c),and(e).

H.

The licensee shall have and maintain financial protection of such type ano in such a'nounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.

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1.

This license is effective as of the date of issuance and shall expire at midnight on January 10, 2006.

FOR 1HE NUCLEAR REGULATORY COMMIS510N k

Thomas E. Murley, Director Offd:e of Nuclear Reactor Regulation

Attachment:

Appendix A. Technical Specifications Date of 1scuance:

February 20, 1991 l

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