ML070380493

Technical Specification, Core Spray Instrumentation

ML070380493
Person / Time
Site:	Nine Mile Point
Issue date:	01/31/2007
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
References
TAC MC9626
Download: ML070380493 (2)

Text

(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 I:

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. This renewed license 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 also 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 1850 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 1o2 is hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications.

(3) The licensee shall submit an application for license amendment, including supporting analyses and evaluations by December 18, 1998. This amendment application shall contain the proposed methods for compliance with GDC 19 dose guidelines under accident conditions based upon system design .and without reliance upon the use of potassium iodide.

F'eneovved License Nc~. DPR-630

LIMITING CONDITION FOR OPERATION - 0 SURVEILLANCE REQUIREMENT If Specifications a, b and c are not met, a normal d. (Deleted) orderly ,s1'hutdown shall be initiated within one-hour and the reactor shall be in the cold shuldown condition within ten hours.

e. During reactor operation, except during core e. Surveillance with Inoperable Components spray system surveillance testing, core spray isolation valves 40-02 and 40-12 shall be in the When a component becomes inoperable its open position and the associated valve motor redundant component or system shall be verified starler circuit breakers for these valves shall be to be operable immediately and daily thereafter.

locked in the off position. In addition, redundant valve position indication shall be available in the (onterol 0oomI,

\VIie iever irradiated fuel is in the reactor vessel f. With a core spray subsystem suction from the and the reactor coolant temperature is less than CST, CST level shall be checked once per day.

or equal to 21:2-F, two core spray subsystems shall be operable except as specified in g and h below.

.!. If one of the above required subsystems g. At least once per month when the reactor becomes inoperable, restore at least two coolant temperature is greater than 2121F, verify subsystems to an operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that the piping system between valves 40-03, cr suspenrd all operations that have a potential 13 and 40-01, 09, 10, 11 is filled with water.

for draining the reactor vessel.

AM I- ND MVIN- NO. .14;),. 1920 55