ML073620133
| ML073620133 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/12/2008 |
| From: | NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | |
| Hughey J, NRR/DORL, 301-415-3204 | |
| Shared Package | |
| ML073620105 | List: |
| References | |
| TAC MD6631 | |
| Download: ML073620133 (11) | |
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.302, 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. 302
REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.3.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE:
- a.
Once per 31 days by performance of a CHANNEL FUNCTIONAL TEST, excluding valve operation, and
- b.
Once per 18 months by performance of a CHANNEL CALIBRATION.
- c.
Once per 18 months by operating the PORV through one complete cycle of full travel at conditions representative of MODES 3 or 4.
4.4.3.2 Each block valve shall be demonstrated OPERABLE once per 92 days by operating the valve through one complete cycle of full travel. This demonstration is not required if a PORV block valve is closed and power removed to meet Specification 3.4.3 b or c.
MILLSTONE - UNIT 2 3/4 4-3a Amendment No. 66, 68, 4-8-, 302