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Category:Technical Specifications
MONTHYEARAEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System ML22046A2332022-06-21021 June 2022 Issuance of Amendment Nos. 360 and 342 Regarding Change to the Technical Specification Requirement for Containment Water Level Instrumentation ML21125A5762021-04-19019 April 2021 9 Technical Specification Bases, List of Effective Pages (Unit 2) ML21125A5482021-04-19019 April 2021 2 to Technical Specifications Bases, List of Effective Pages (Unit 1) ML20366A1552021-01-15015 January 2021 Issuance of Amendments Nos. 357 and 336 Regarding Revision to Technical Specifications Bases Control Program ML20329A0012021-01-12012 January 2021 Issuance of Amendment No. 356 Regarding Updating the Reactor Coolant System Pressure-Temperature Limits ML20322A4282021-01-0606 January 2021 Issuance of Amendment Nos. 355 and 335, Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues AEP-NRC-2020-78, License Amendment Request Regarding a Change to the Steam Generator (SG) Program to Allow for a One-Time Deferral of SG Inspections2020-12-14014 December 2020 License Amendment Request Regarding a Change to the Steam Generator (SG) Program to Allow for a One-Time Deferral of SG Inspections ML19170A3622019-08-0101 August 2019 Issuance of Amendment Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping ML17131A2772017-06-0707 June 2017 Issuance of Amendments License Amendment Request Regarding Containment Leakage Rate Testing Program ML16195A0042016-08-0404 August 2016 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 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ML0604400222006-02-10010 February 2006 Technical Specifications, Delete the Power Range Neutron Flux High Negative Rate Trip Function ML0601700302006-01-12012 January 2006 Tech Spec Pages for Amendments 292 and 274 Regarding Elimination of Requirements for Monthly Operating Reports and Occupational Radiation Exposure Reports 2024-08-28
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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. 295, 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. q ,.hoti.h 294, 295
AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.8.1.11 -----------
NOTES---------------------------
- 1. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance rnay be performed to reestablish OPERABILITY provided an assessment determines the safety of the unit is maintained or enhanced.
Credit may be taken for unplanned events that satisfy this SR.
- 2. If performed with DG synchronized with offsite power, it shall be performed at a power factor _0.86. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.
Verify each DG does not trip and voltage is 24 months maintained *5350 V during and following a load rejection Ž3150 kW and *3500 kW.
Cook Nuclear Plant Unit 1 3.8.1-10 Amendment No. 27, 291, 295