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#REDIRECT [[RS-10-001, LaSalle, Units 1 and 2, Attachment 2 - Markup of Proposed Operating License and Technical Specifications Pages]]
{{Adams
| number = ML100321306
| issue date = 01/27/2010
| title = Attachment 2 - Markup of Proposed Operating License and Technical Specifications Pages
| author name =
| author affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee name =
| addressee affiliation = NRC/NRR
| docket = 05000373, 05000374
| license number = NPF-011, NPF-018
| contact person =
| case reference number = RS-10-001
| package number = ML100321303
| document type = License-Application for Facility Operating License (Amend/Renewal) DKT 50, Technical Specifications
| page count = 7
}}
 
=Text=
{{#Wiki_filter: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 Commission's 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 pow er (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 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 Commission's 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 Attachment 1 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 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 ofMWt.113546 I (continued)
LaSalle 1 and 2 1.1-5 Amendment No.IH/133 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. Intermediate Range Monitors
: a. Neutron Flux-High 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 Flux-High, 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 Power-Upscale 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."
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 2The 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 hours 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}}

Latest revision as of 01:25, 19 March 2019

Attachment 2 - Markup of Proposed Operating License and Technical Specifications Pages
ML100321306
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 01/27/2010
From:
Exelon Generation Co, Exelon Nuclear
To:
Office of Nuclear Reactor Regulation
Shared Package
ML100321303 List:
References
RS-10-001
Download: ML100321306 (7)
v • d • e


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 Commission's 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 pow er (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 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 Commission's 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 Attachment 1 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 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 ofMWt.113546 I (continued)

LaSalle 1 and 2 1.1-5 Amendment No.IH/133 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. Intermediate Range Monitors
a. Neutron Flux-High 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 Flux-High, 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 Power-Upscale 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."

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 2The 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

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