ML072630122
| ML072630122 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/18/2007 |
| From: | Plant Licensing Branch III-2 |
| To: | |
| Lamb John G./NRR/DORL, 415-3100 | |
| Shared Package | |
| ML072290118 | List: |
| References | |
| TAC MD2943, TAC MD2944 | |
| Download: ML072630122 (2) | |
Text
Connecticut, in accordance with the procedures and limitations set forth in this renewed operating license; (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, 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 and equipment calibration or associated with radioactive apparatus or components; (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 operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 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 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 2700 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.300, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the Technical Specifications.
Renewed License No. DPR-65 Amendment No.300
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- h.
At least once per 18 months by verifying each low pressure safety injection pump stops automatically on an actual or simulated actuation signal.
- i.
By verifying the correct position of each electrical and/or mechanical position stop for each injection valve in Table 4.5-1:
- 1.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after completion of valve operations.
- 2.
At least once per 18 months.
- j.
At least once per 18 months by verifying through visual inspection of the containment sump that each Emergency Core Cooling System subsystem suction inlet is not restricted by debris and the suction inlet strainers show no evidence of structural distress or abnormal corrosion.
- k.
At least once per 18 months by verifying the Shutdown Cooling System open permissive interlock prevents the Shutdown Cooling System inlet isolation valves from being opened with an actual or simulated Reactor Coolant System pressure signal ofŽ_ 300 psia.
I MILLSTONE - UNIT 2 3/4 5-5 Amendment No. -, 4-5,, 6+, 40+-,
4-59, 4-6+, 2-44, 2-+-5, 2-39, 283,300