ML100321306
Text
ATTACHMENT 2 Markup of Proposed Operating License and Technical Specifications Pages LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 REVISED OPERATING LICENSE AND TECHNICAL SPECIFICATIONS PAGES Operating License (Units 1 and 2), Page 3 TS Page 1.1-5 TS Page 3.3.1.1-7 TS Page 3.3.1.3-3
09/16/09 License No. NPF-11 Am. 146 (4)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR Parts 01/12/01 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 calibration or associated with radioactive apparatus or components; and Am. 146 (5)
Exelon Generation Company, LLC, pursuant to the Act and 10 CFR 01/12/01 Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2.
C.
This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and 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 subject to the additional conditions specified or incorporated below:
(1)
Maximum Power Level The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3489 megawatts thermal).
Am. 195 (2)
Technical Specifications and Environmental Protection Plan 09/16/09 The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Am. 194 (3)
DELETED 08/28/09 Am. 194 (4)
DELETED 08/28/09 Am. 194 (5)
DELETED 08/28/09 Am. 194 (6)
DELETED 08/28/09 Am. 194 (7)
DELETED 08/28/09 3546
09/16/09 License No. NPF-18 Am. 34 (5)
Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not 12/08/87 separate, such byproduct and special nuclear materials as may be produced by the operation of LaSalle County Station, Units 1 and 2.
C.
The license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and 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 subject to the additional conditions specified or incorporated below:
Am. 125 (1)
Maximum Power Level 05/09/00 The licensee is authorized to operate the facility at reactor core power levels not in excess of full power (3489 megawatts thermal). Items in shall be completed as specified. Attachment 1 is hereby incorporated into this license.
Am. 182 (2)
Technical Specifications and Environmental Protection Plan 09/16/09 The Technical Specifications contained in Appendix A, as revised through Amendment No. 182, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Am. 181 (3)
DELETED 08/28/09 Am. 181 (4)
DELETED 08/28/09 Am. 181 (5)
DELETED 08/28/09 Am. 181 (6)
DELETED 08/28/09 Am. 181 (7)
DELETED 08/28/09 Am. 181 (8)
DELETED 08/28/09 Am. 181 (9)
DELETED 08/28/09 3546
Defini tions 1.1 1.1 Definitions (continued)
LINEAR HEAT GENERATION RATE (LHGR)
LOGIC SYSTEM FUNCTIONAL TEST MINIMUM CRITICAL POWER RATIO (MCPR)
MODE OPERABLE-OPERABILITY RATED THERMAL POWER (RTP)
The LHGR shall be the heat generation rate per unit length of fuel rod.
It is the integral of the heat flux over the heat transfer area associated with the unit length.
A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY.
The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each class of fuel.
The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
A MODE shall correspond to anyone inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
RTP shall be a total reactor core heat transfer rate to the reactor coolant of ~ MWt.
113546 I (continued)
LaSalle 1 and 2 1.1-5 Amendment No.
IH/133 3546
RPS Instrumentation 3.3.1.1 LaSalle 1 and 2 3.3.1.1-7 Amendment No. 147/133 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
- 1.
- a. Neutron FluxHigh 2
3 G
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.15 123/125 divisions of full scale 5(a) 3 H
SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.13 SR 3.3.1.1.15 123/125 divisions of full scale
- b. Inop 2
3 G
SR 3.3.1.1.4 SR 3.3.1.1.15 NA 5(a) 3 H
SR 3.3.1.1.5 SR 3.3.1.1.15 NA
- 2.
Average Power Range Monitors
- a. Neutron FluxHigh, Setdown 2
2 G
SR 3.3.1.1.1 SR 3.3.1.1.4 SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.15 20% RTP
- b. Flow Biased Simulated Thermal PowerUpscale 1
2 F
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.15 0.62 W +
69.3% RTP and 115.5%
RTP(b)
- c. Fixed Neutron Flux-High 1
2 F
SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.15 SR 3.3.1.1.17 120% RTP (continued)
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b)
Allowable Value is 0.55 W + 56.8% RTP and 112.3% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
< 0.54 W + 55.9% RTP (d)
(d)
(b) [Insert 1]
(c) [Insert 2]
< 0.61 W + 68.2% RTP (b) (c)
Inserts for TS Table 3.3.1.1-1 INSERT 1 If the as-found channel setpoint is outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
INSERT 2 The instrument channel setpoint shall be reset to a value that is within the as-left tolerance around the nominal trip setpoint (NTSP) at the completion of the surveillance; otherwise, the channel shall be declared inoperable. Setpoints more conservative than the NTSP are acceptable provided that the as-found and as-left tolerances apply to the actual setpoint implemented in the surveillance procedures (field setting) to confirm channel performance. The NTSP and the methodologies used to determine the as-found and the as-left tolerances are specified in the Technical Requirements Manual.
OPRM Instrumentation 3.3.1.3 LaSalle 1 and 2 3.3.1.3-3 Amendment No. 195/182 SURVEILLANCE REQUIREMENTS
NOTE-------------------------------------
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the OPRM maintains trip capability.
SURVEILLANCE FREQUENCY SR 3.3.1.3.1 Perform CHANNEL FUNCTIONAL TEST.
184 days SR 3.3.1.3.2 Calibrate the local power range monitors.
2000 effective full power hours SR 3.3.1.3.3 -------------------NOTE--------------------
Neutron detectors are excluded.
Perform CHANNEL CALIBRATION. The setpoints for the trip function shall be as specified in the COLR.
24 months SR 3.3.1.3.4 Perform LOGIC SYSTEM FUNCTIONAL TEST.
24 months SR 3.3.1.3.5 Verify OPRM is not bypassed when THERMAL POWER is 28.6% RTP and recirculation drive flow is 60% of rated recirculation drive flow.
24 months SR 3.3.1.3.6 -------------------NOTE--------------------
Neutron detectors are excluded.
Verify the RPS RESPONSE TIME is within limits.
24 months on a STAGGERED TEST BASIS 28.1%