ML041330109
| ML041330109 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/19/2004 |
| From: | Rajender Auluck NRC/NRR/DRIP/RLEP |
| To: | Mecredy R Rochester Gas & Electric Corp |
| Auluck R, NRR/DRIP/RLEP, 415-1025 | |
| Shared Package | |
| ML041330037 | List: |
| References | |
| Download: ML041330109 (5) | |
Text
Renewed Operating License No. DPR-18 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R. E. GINNA NUCLEAR POWER PLANT RENEWED FACILITY OPERATING LICENSE NO. DPR-18 1.
The U.S. Nuclear Regulatory Commission (the Commission) having previously made the findings set forth in License No. DPR-18 issued December 10, 1984, has now found that:
A.
The application to renew License No. DPR-18 filed by Rochester Gas and Electric Corporation (RG&E or the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the rules and regulations of the Commission set forth in Title 10 of the Code of Federal Regulations (10 CFR) Chapter I and all required notifications to other agencies or bodies have been duly made; B.
Actions have been identified and have been or will be taken with respect to (1) managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified to require review under 10 CFR 54.21(a)(1), and (2) time-limited aging analyses that have been identified to require review under 10 CFR 54.21(c), such that there is reasonable assurance that the activities authorized by this renewed license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for R. E. Ginna Nuclear Power Plant (the facility), and that any changes made to the plants current licensing basis in order to comply with 10 CFR 54.29(a) are in accord with the Act and the Commissions regulations; C.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; D.
There is reasonable assurance (i) that the facility can be operated at power levels up to 1520 megawatts (thermal) without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the regulations of the Commission (except as exempted from compliance in Section 2.D below);
E.
RG&E is technically and financially qualified to engage in the activities authorized by this renewed operating license in accordance with the rules and regulations of the Commission; Renewed Operating License No. DPR-18 F.
RG&E has furnished proof of financial protection that satisfies the requirements of 10 CFR Part 140; G.
The issuance of this renewed license will not be inimical to the common defense and security or to the health and safety of the public; and H.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the Commission concludes that the issuance of Renewed Operating License No.
DPR-18 is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.
- 2.
On the basis of the foregoing findings regarding this facility, Facility Operating License No. DPR-18, is superseded by Renewed Facility Operating License No. DPR-18, hereby issued to Rochester Gas and Electric Corporation to read as follows:
A.
This renewed license applies to the R. E. Ginna Nuclear Power Plant, a closed cycle, pressurized, light-water-moderated and cooled reactor, and electric generating equipment which is owned by Rochester Gas and Electric Corporation. The facility is located on the licensees site on the south shore of Lake Ontario, Wayne County, New York, about 16 miles east of the City of Rochester and is described in the licensees Updated Final Safety Analysis Report (UFSAR), as supplemented and amended.
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses RG&E:
(1)
Pursuant to Section 104b of the Act and 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, to possess, use and operate the facility at the designated location in Wayne County, New York, in accordance with the procedures and limitations set forth in this renewed license; (2)
Pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time special nuclear material or reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation as described in the Final Safety Analysis Report, as amended, and Commission Safety Evaluations dated November 15, 1976, October 5, 1984, November 14, 1984, and August 30, 1995.
(a)
Pursuant to the Act and 10 CFR Part 70, to receive and store four (4) mixed oxide fuel assemblies in accordance with the licensees application dated December 14, 1979 (transmitted by letter dated December 20, 1979);
Renewed Operating License No. DPR-18 (b)
Pursuant to the Act and 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the licensees application dated December 14, 1979 (transmitted by letter dated December 20, 1979), as supplemented February 20, 1980, and March 5, 1980; (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, 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 calibration or associated with radioactive apparatus or components; and (5)
Pursuant to the Act and 10 CFR Parts 30 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 renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR 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 of the Act and rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
(1)
Maximum Power Level RG&E is authorized to operate the facility at steady-state power levels up to a maximum of 1520 megawatts (thermal).
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 83, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Fire Protection (a)
The licensee shall implement and maintain in effect all fire protection features described in the licensees submittals referenced in and as approved or modified by the NRCs Fire Protection Safety Evaluation (SE) dated February 14, 1979, and Renewed Operating License No. DPR-18 SE supplements dated December 17, 1980, February 6, 1981, June 22, 1981, February 27, 1985, and March 21, 1985 or configurations subsequently approved by the NRC, subject to provision (b) below.
(b)
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.
(c)
Deleted (4)
Deleted (5)
Deleted (6)
Deleted D.
The facility requires an exemption from certain requirements of 10 CFR 50.46(a)(1). This includes an exemption from 50.46(a)(1), that emergency core cooling system (ECCS) performance be calculated in accordance with an acceptable calculational model which conforms to the provisions in Appendix K (SER dated April 18, 1978). The exemption will expire upon receipt and approval of revised ECCS calculations. The aforementioned exemption is authorized by law and will not endanger life property or the common defense and security and is otherwise in the public interest. Therefore, the exemption is hereby granted pursuant to 10 CFR 50.12.
E.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27827 and 27822) and 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: Robert Emmet Ginna Nuclear Plant Physical Security Plan, with revisions submitted through August 18, 1987; Robert Emmet Ginna Nuclear Plant Guard Training and Qualification Plan with revisions submitted through July 30, 1981; and Robert Emmet Ginna Nuclear Plant Safeguards Contingency Plan with revisions submitted through April 14, 1981. Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
F.
The Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21(d), describes certain future activities to be completed prior to the period of extended operation. RG&E shall complete these activities no later than September 18, 2009, and shall notify the Commission in writing when implementation of these activities is complete and can be verified by Commission inspection.
Renewed Operating License No. DPR-18 The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71(e)(4) following issuance of this renewed license. Until that update is complete, RG&E may make changes to the programs and activities described in the supplement without prior Commission approval, provided that RG&E evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
G.
All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. Any capsules placed in storage must be maintained for future insertion, unless approved by the NRC.
H.
This renewed license is effective as of the date of issuance and shall expire at midnight on September 18, 2029.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
J. E. Dyer, Director Office of Nuclear Reactor Regulation
Attachment:
Appendix A - Technical Specifications Date of Issuance: May 19, 2004