ML062830313
| ML062830313 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/06/2006 |
| From: | NRC/NRR/ADRO/DORL/LPLIII-1 |
| To: | |
| P. TAM | |
| Shared Package | |
| ML062830153 | List: |
| References | |
| TAC MD2106 | |
| Download: ML062830313 (2) | |
Text
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; and (5)
Pursuant to the Act and 10 CFR 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; and is subject to all applicable provisions of thee Act and to 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 to exceed 3304 megawatts thermal in accordance with the conditions specified therein.
(2)
Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 296, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3)
Less Than Four Loop Operation The licensee shall not operate the reactor at power levels above P-7 (as defined in Table 3.3.1-1 of Specification 3.3.1 of Appendix A to this renewed operating license) with less than four reactor coolant loops in operation until (a) safety analyses for less than four loop operation have been submitted, and (b) approval for less than found loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.
(4)
Indiana Michigan Power Company shall implement and maintain, in effect, all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for the facility and as approved in the SERs dated December 12, 1977, July 31, 1979, January 10, 1981, February 7, 1983, November 22, 1983, December 23, 1983, March 16, 1984, August 27, 1985 Renewed License No. DPR-58 Amendment No. + thgh 2
, 296
RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.11 NOTES
- 1.
For Function 4, not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER is below the P-1 0 interlock.
- 2.
For Function 5, not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after THERMAL POWER is below the P-6 interlock.
Perform COT.
184 days SR 3.3.1.12 Perform CHANNEL CALIBRATION.
184 days SR 3.3.1.13 Perform CHANNEL CALIBRATION.
24 months SR 3.3.1.14 NOTE Neutron detectors are excluded from CHANNEL CALIBRATION.
Perform CHANNEL CALIBRATION.
24 months SR 3.3.1.15 NOTE Normalization of the AT is not required to be performed until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after THERMAL POWER is z98% RTP.
Perform CHANNEL CALIBRATION.
24 months SR 3.3.1.16 Perform COT.
24 months SR 3.3.1.17 Perform TADOT.
24 months I
Cook Nuclear Plant Unit 1 3.3.1-9 Amendment No. M87, 2 9 6