ML080420386

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Technical Specifications, Issuance of Amendment Technical Specification Change for Scram Time Testing Activities, Using the Consolidated Line Item Improvement Process
ML080420386
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 02/07/2008
From: David M
NRC/NRR/ADRO/DORL/LPLI-1
To:
david marshall NRR/DORL 415-1547
References
TAC MD6903
Download: ML080420386 (2)


Text

4-(1) Maximum Power Level Nine Mile Point Nuclear Station, LLC, Is authorized to operate the facility at reactor core power levels not In excess of 3467 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained InAppendix B.both of which are attached hereto, as revised through Amendment No. 12 are hereby Incorporated into this license. Nine Mile Point Nu..iear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Fuel Storage and Handling (Section 9.1, SSER 4)

a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.
b. When not in the reactor vessel, no more 1than three fuel assemblies shall be allowed outside of their shipping containers or storage racks in the New Fuel Vault or Spent Fuel Storage Facility.
c. The above three fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) Inches from the shipping contalner array and approved storage rack locations.
d. The New Fuel Storage Vault shall have no more than ten fresh.

fuel assemblies uncovered at any one time.

(4) Turbine System Maintenance Program (Section 3.5,1.310. SER)

The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities.

(Submitted by NMPC letter dated October 30, 1989, from CD. Terry and approved by NRC letter dated March 15, 1990, from Robert Martin to Mr. Lawrence Burkhardt, I1l).

The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition Ih; discussed.

Renewed License No. NPF.69 AvndTbB.t: th. 1l1

System Leakage and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 System Leakage and Hydrostatic Testing Operation LCO 3.10.1 The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to "NA," and operation considered not to be in MODE 3; and the requirements of LCO 3.4.10, "Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown," may be suspended to allow reactor coolant temperature > 200°F:

" For performance of a system leakage or hydrostatic test,

  • As a consequence of maintaining adequate pressure for a system leakage or hydrostatic test, or

" As a consequence of maintaining adequate pressure for control rod scram time testing initiated in conjunction with a system leakage or hydrostatic test, provided the following MODE 3 LCOs are met:

a. LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation," Functions 1, 3, and 4 of Table 3.3.6.2-1;
b. LCO 3.3.8.2, "Reactor Protection System (RPS) Electric Power Monitoring - Logic";
c. LCO 3.6.4.1, "Secondary Containment";
d. LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)"; and
e. LCO 3.6.4.3, "Standby Gas Treatment (SGT) System."

APPLICABILITY: MODE 4 with average reactor coolant temperature > 200°F.

NMP2 3.10.1-1 M31-.endment -9,