Letter Sequence Other |
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MONTHYEARML0531902132005-11-0707 November 2005
Application for Amendment to Facility Operating License Revising Technical Specification, Section 3.9.3. to Allow Refueling Operations with the Containment Equipment Hatch Open
Project stage: Request
ML0608102112006-03-23023 March 2006
R. E. Ginna Nuclear Power Plant - Request for Additional Information Movement of Fuel with Eqiupment Hatch Open
Project stage: RAI
ML0613204802006-05-0505 May 2006
R. E. Ginna Nuclear Power Plant, Response to Request for Information Application for Amendment to Facility Operating License Revising Technical Specification Section 3.9.3 to Allow Refueling Operations with the Containment Equipment Hatch O
Project stage: Response to RAI
ML0616002232006-07-26026 July 2006
R. E. Ginna, License Amendment 98 Regarding Refueling Operations with Equipment Hatch Open
Project stage: Approval
ML0620903672006-07-26026 July 2006
Technical Specifications, Revises TS 3.9.3, Containment Penetrations, to Allow an Emergency Egress Door, Access Door, or Roll Up Door, as Associated with the Equipment Hatch Penetration, to Be Open, But Capable of Being Closed
Project stage: Other
2006-03-23
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[Table view] |
Text
(b) Pursuant to the Act and 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the RG&E's 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 instrunentation 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 Ginna LLC is authorized to operate the facility at steady-state power levels up to a maximum of 1775 megawatts (thermal).
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 98, 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 licensee's submittals
.eferenced in and as approved or modified by the NRC's Fire P*otection Safety Evaluation (SE) dated February 14, 1979 and Amendment No. 98
Containment Penetrations 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Containment Penetrations LCO 3.9.3 The containment penetrations shall be in the following status:
- a. The equipment hatch shall be either:
- 1. bolted in place with at least one access door closed or I capable of being closed under administrative control,
- 2. isolated by a closure plate that restricts air flow from containment with the associated emergency egress door closed or capable of being closed under administrative control, or
- 3. isolated by a roll up door and enclosure building with the roll up door closed or capable of being closed under administrative control.
- b. One door in the personnel air lock shall be closed; and
- c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:
- 1. closed by a manual or automatic isolation valve, blind flange, or equivalent, or
- 2. capable of being closed by an OPERABLE Containment Ventilation Isolation System.
APPLICABILITY: During CORE ALTERATIONS, During movement of irradiated fuel assemblies within containment.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment A.1 Suspend CORE Immediately penetrations not in ALTERATIONS.
required status.
AND R.E. Ginna Nuclear Power Plant 3.9.3-1 Amendment 98
Containment Penetrations 3.9.3 CONDITION REQUIRED ACTION COMPLETION TIME A.2 Suspend movement of Immediately iracroted fuel assemblies within containment.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify each required containment penetration is in the 7 days required status.
SR 3.9.3.2 Verify each required containment purge and exhaust 24 months valve actuates to the isolation position on an actual or simulated actuation signal.
R.E. Ginna Nuclear Power Plant 3.9-3-2 Amendment 98
