Text

5 to Technical Requirements Manual
	ML21300A341
Person / Time
Site:	Quad Cities
Issue date:	10/21/2021
From:	; Exelon Generation Co
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML21300A331	List: ML21298A208; ML21300A255; ML21300A256; ML21300A258; ML21300A260; ML21300A261; ML21300A262; ML21300A263; ML21300A264; ML21300A265; ML21300A266; ML21300A268; ML21300A269; ML21300A270; ML21300A272; ML21300A274; ML21300A339; ML22041A844; ML22042B306; ML22042B307; ML22042B308; RS-21-107, 5 to Technical Requirements Manual;
References
	RS-21-107
	Download: ML21300A341 (333)
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Affected Page List - Technical Requirements Manual TABLE OF CONTENTS - Technical Requirements Manual I ................................................................................................................. Revision QC-TRM-12-003 Ii ................................................................................................................ Revision QC-TRM-20-008 Iii ............................................................................................................... Revision QC-TRM-11-001 TABLE OF CONTENTS - Technical Requirements Manual Bases I ................................................................................................................. Revision QC-TRM-20-008 Ii ................................................................................................................ Revision 0 1.0 USE AND APPLICATION 1.1-1 thru 1.1-2 ........................................................................................ Revision 0 1.1-3 ......................................................................................................... Revision QC-TRM-02-007 1.2-1 thru 1.2-3 ........................................................................................ Revision 0 1.3-1 thru 1.3-13 ...................................................................................... Revision QC-TRM-19-011 1.4-1 thru 1.4-5 ........................................................................................ Revision 0 1.5-1 ......................................................................................................... Revision 0 1.6-1 ......................................................................................................... Revision 0 2.0 TEST REQUIREMENTS 2.1.a-1....................................................................................................... Revision QC-TRM-09-002 2.1.a-2....................................................................................................... Revision 0 3.0 TECHNICAL REQUIREMENTS MANUAL LIMITING CONDITION FOR OPERATION (TLCO) APPLICABILITY 3.0-1 ......................................................................................................... Revision QDC-TRM-05-003 3.0-2 thru 3.0-3 ........................................................................................ Revision QC-TRM-17-006 3.0-4 ......................................................................................................... Revision QC-TRM-05-003 3.1 REACTIVITY CONTROL SYSTEMS N/A (No pages at this time) 3.3. INSTRUMENTATION 3.3.a-1 thru 3.3.a-2 ................................................................................... Revision 0 3.3.a-3 ...................................................................................................... Revision QC-TRM-21-003 3.3.a-4 ...................................................................................................... Revision 0 3.3.a-5....................................................................................................... Revision QC-TRM-02-005 & QC-TRM-01-004 3.3.a-6....................................................................................................... Revision QC-TRM-02-005 Quad Cities 1 and 2 Page 1 of 5 Revision 35

Affected Page List - Technical Requirements Manual 3.3.b-1 thru 3.3.b-4 .................................................................................. Revision QC-TRM-05-008 3.3.c-1 thru 3.3.c-2 ................................................................................... Revision 0 3.3.c-3 ....................................................................................................... Revision QC-TRM-01-006 3.3.c-4 ....................................................................................................... Revision 0 3.3.d-1 thru 3.3.d-3 .................................................................................. Revision 0 3.3.e-1 ...................................................................................................... Revision QC-TRM-03-001 3.3.f-1 thru 3.3.f-4 .................................................................................... Revision 0 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.a-1 thru 3.4.a-2 ................................................................................... Revision QC-TRM-12-003 3.4.b-1 thru 3.4.b-4 .................................................................................. Revision QC-TRM-01-005 3.7 PLANT SYSTEMS 3.7.a-1....................................................................................................... Revision QC-TRM-07-003 3.7.b-1 ...................................................................................................... Revision 0 3.7.b-2 ...................................................................................................... Revision QC-TRM-19-006 3.7.c-1 thru 3.7.c-2 ................................................................................... Revision QC-TRM-19-010 3.7.d-1 thru 3.7.d-2 .................................................................................. Revision 0 3.7.e-1 ...................................................................................................... Revision 0 3.7.f-1 thru 3.7.f-2 .................................................................................... Revision 0 3.7.g-1 thru 3.7.g-4 ................................................................................... Revision 0 3.7.h-1 ...................................................................................................... Revision QC-TRM-18-006 3.9 REFUELING OPERATIONS 3.9.a-1....................................................................................................... Revision 0 5.0 ADMINSTRATIVE CONTROLS 5.0.a-1....................................................................................................... Revision QC-TRM-03-004 5.0.a-2....................................................................................................... Revision QC-TRM-17-005 5.0.a-3....................................................................................................... Revision QC-TRM-20-001 5.0.a-4....................................................................................................... Revision QC-TRM-21-006 Quad Cities 1 and 2 Page 2 of 5 Revision 35

Affected Page List - Technical Requirements Manual APPENDICES Appendix A - Unit 1 Primary Containment Isolation Valves A1-1 thru A1-3 .......................................................................................... Revision QC-TRM-17-002 A1-4 thru A1-5 .......................................................................................... Revision QC-TRM-20-010 A1-6 thru A1-14 ........................................................................................ Revision QC-TRM-17-002 Appendix A - Unit 2 Primary Containment Isolation Valves A2-1 thru A2-3 .......................................................................................... Revision QC-TRM-09-005 A2-4 thru A2-5 .......................................................................................... Revision QC-TRM-20-010 A2-6 thru A2-9 .......................................................................................... Revision QC TRM 09-005 A2-10 thru A2-11 ...................................................................................... Revision QC-TRM-16-003 A2-12 ........................................................................................................ Revision QC-TRM-20-006 A2-13 thru A2-14 ...................................................................................... Revision QC-TRM-09-005 Appendix B - Secondary Containment Isolation Valves B-1 ............................................................................................................ Revision QC-TRM-19-009 Appendix C- Safety Function Determination Program C-1 thru C-40 ............................................................................................ Revision 0 Appendix D - Technical Specification Bases Control Program 1 thru 8 ..................................................................................................... Revision QC-TRM-21-001 Appendix E- Quad Cities Unit 1 Core Operating Limits Report Unit 1 Cycle 27 Revision 16 (entire report) .............................................. Revision 16 Appendix F- Quad Cities Unit 2 Core Operating Limits Report Unit 2 Cycle 26 Revision 14 (entire report) .............................................. Revision 14 Appendix G - Technical Requirements Manual Control Program 1 thru 11 ................................................................................................... Revision QC-TRM-21-001 Appendix H - Response Times H-1 ............................................................................................................ Revision QC-TRM-05-004 Quad Cities 1 and 2 Page 3 of 5 Revision 35

Affected Page List - Technical Requirements Manual Bases B 1.0 USE AND APPLICATION NONE B 2.0 MISCELLANEOUS TEST REQUIREMENTS NONE B 3.0 TECHNICAL REQUIREMENTS MANUAL LIMITING CONDITION FOR OPERATION (TLCO) APPLICABILITY B 3.0-1 ...................................................................................................... Revision 0 B 3.0-2 ...................................................................................................... Revision QC-TRM-19-012 B 3.0-3 ...................................................................................................... Revision 0 B 3.0-4 thru B 3.0-9 .................................................................................. Revision QC-TRM-05-003 B 3.0-10 thru B 3.0-11 .............................................................................. Revision QC-TRM 19-012 B 3.0-12 thru B 3.0-13 .............................................................................. Revision QC-TRM-05-003 B 3.1 REACTIVITY CONTROLS SYSTEMS N/A (no pages at this time)

B 3.3 INSTRUMENTATION B 3.3.a-1 ................................................................................................... Revision QC-TRM-11-003 B 3.3.b-1 ................................................................................................... Revision QC-TRM-05-008 B 3.3.c-1 .................................................................................................... Revision 0 B 3.3.d-1 ................................................................................................... Revision 0 B 3.3.e-1 ................................................................................................... Revision QC-TRM-03-001 B 3.3.f-1 .................................................................................................... Revision 0 B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.a-1 ................................................................................................... Revision QC-TRM-12-003 B 3.4.b-1 ................................................................................................... Revision QC-TRM-13-003 B 3.7 PLANT SYSTEMS B 3.7.a-1 ................................................................................................... Revision QC-TRM-06-002 B 3.7.b-1 ................................................................................................... Revision QC-TRM-19-006 B 3.7.c-1 .................................................................................................... Revision QC-TRM-06-002 B 3.7.d-1 ................................................................................................... Revision 0 B 3.7.e-1 ................................................................................................... Revision 0 Quad Cities 1 and 2 Page 4 of 5 Revision 35

Affected Page List - Technical Requirements Manual B 3.7.f-1 .................................................................................................... Revision QC-TRM-14-004 B 3.7.g-1 ................................................................................................... Revision 0 B 3.7.h-1 ................................................................................................... Revision QC-TRM-04-004 B 3.9 REFUELING OPERATIONS B 3.9.a-1 ................................................................................................... Revision 0 Quad Cities 1 and 2 Page 5 of 5 Revision 35

TABLE OF CONTENTS TECHNICAL REQUIREMENTS MANUAL 1.0 USE AND APPLICATION ..........................................................................................1.0-1 1.1 Definitions ...............................................................................................1.1-1 1.2 Logical Connectors ........................................................................................1.2-1 1.3 Completion Times ..........................................................................................1.3-1 1.4 Frequency ...............................................................................................1.4-1 1.5 TLCO and TSR Implementation .....................................................................1.5-1 1.6 TRM Revisions ..............................................................................................1.6-1 2.1.a Miscellaneous Test Requirements .............................................................. 2.1.a-1 3.0 TLCO Applicability ...............................................................................................3.0-1 3.0 TSR Applicability ...............................................................................................3.0-3 3.1 Not Used 3.2 Not Used 3.3 INSTRUMENTATION ................................................................................. 3.3.a-1 3.3.a Control Rod Block Instrumentation .................................................. 3.3.a-1 3.3.b Post Accident Monitoring (PAM) Instrumentation............................. 3.3.b-1 3.3.c Explosive Gas Monitoring Instrumentation....................................... 3.3.c-1 3.3.d Suppression Chamber and Drywell Spray Actuation Instrumentation .................................................................... 3.3.d-1 3.3.e Toxic Gas Monitoring System .......................................................... 3.3.e-1 3.3.f Reactor Water Cleanup (RWCU) Area Temperature Monitoring .............................................................................3.3.f-1 3.4 REACTOR COOLANT SYSTEM (RCS) ...................................................... 3.4.a-1 3.4.a Structural Integrity ........................................................................... 3.4.a-1 3.4.b Reactor Coolant System (RCS) Chemistry ...................................... 3.4.b-1 3.5 Not Used Quad Cities 1 and 2 i Revision QC-TRM-12-003

TABLE OF CONTENTS TECHNICAL REQUIREMENTS MANUAL 3.6 Not Used 3.7 PLANT SYSTEMS ...................................................................................... 3.7.a-1 3.7.a Residual Heat Removal Service Water (RHRSW) System Shutdown ........................................................................ 3.7.a-1 3.7.b Diesel Generator Cooling Water (DGCW) System Shutdown ........................................................................ 3.7.b-1 3.7.c Ultimate Heat Sink (UHS) Shutdown ........................................... 3.7.c-1 3.7.d Liquid Holdup Tanks ........................................................................ 3.7.d-1 3.7.e Explosive Gas Mixture ..................................................................... 3.7.e-1 3.7.f Flood Protection ...............................................................................3.7.f-1 3.7.g Sealed Source Contamination ......................................................... 3.7.g-1 3.7.h Snubbers ......................................................................................... 3.7.h-1 3.8 Not Used 3.9 REFUELING OPERATIONS ....................................................................... 3.9.a-1 3.9.a Communications.............................................................................. 3.9.a-1 4.0 Not Used 5.0 ADMINISTRATIVE CONTROLS ................................................................. 5.0.a-1 5.0.a Programs......................................................................................... 5.0.a-1 Appendix A Primary Containment Isolation Valves Appendix B Secondary Containment Isolation Valves Appendix C Safety Function Determination Program Appendix D Technical Specifications Bases Control Program Appendix E Quad Cities Unit 1 Core Operating Limits Report Appendix F Quad Cities Unit 2 Core Operating Limits Report Quad Cities 1 and 2 ii Revision QC-TRM-20-008

TABLE OF CONTENTS TECHNICAL REQUIREMENTS MANUAL Appendix G Technical Requirements Manual Change Process Appendix H Response Times Quad Cities 1 and 2 iii Revision QC-TRM-21-006

TABLE OF CONTENTS TECHNICAL REQUIREMENTS MANUAL BASES B3.0 TLCO Applicability ............................................................................................ B3.0-1 B3.0 TSR Applicability ............................................................................................ B3.0-7 B3.1 Not Used B3.2 Not Used B3.3 INSTRUMENTATION .............................................................................. B3.3.a-1 B3.3.a Control Rod Block Instrumentation ........................................................... B3.3.a-1 B3.3.b Post Accident Monitoring (PAM) Instrumentation ..................................... B3.3.b-1 B3.3.c Explosive Gas Monitoring Instrumentation ............................................... B3.3.c-1 B3.3.d Suppression Chamber and Drywell Spray Actuation Instrumentation ................................................................. B3.3.d-1 B3.3.e Toxic Gas Monitoring System .................................................................. B3.3.e-1 B3.3.f Reactor Water Cleanup (RWCU) Area Temperature Monitoring .......................................................................... B3.3.f-1 B3.4 REACTOR COOLANT SYSTEM (RCS) ................................................... B3.4.a-1 B3.4.a Structural Integrity .................................................................................... B3.4.a-1 B3.4.b Reactor Coolant System (RCS) Chemistry............................................... B3.4.b-1 B3.5 Not Used B3.6 Not Used B3.7 PLANT SYSTEMS ................................................................................... B3.7.a-1 B3.7.a Residual Heat Removal Service Water (RHRSW) System Shutdown ..................................................................... B3.7.a-1 B3.7.b Diesel Generator Cooling Water (DGCW) System Shutdown ..................................................................... B3.7.b-1 B3.7.c Ultimate Heat Sink (UHS) Shutdown .................................................... B3.7.c-1 Quad Cities 1 and 2 i Revision QC-TRM-20-008

TABLE OF CONTENTS TECHNICAL REQUIREMENTS MANUAL BASES B3.7.d Liquid Holdup Tanks ................................................................................ B3.7.d-1 B3.7.e Explosive Gas Mixture ............................................................................. B3.7.e-1 B3.7.f Flood Protection ........................................................................................ B3.7.f-1 B3.7.g Sealed Source Contamination.................................................................. B3.7.g-1 B3.7.h Snubbers ................................................................................................. B3.7.h-1 B3.8 Not Used B3.9 REFUELING OPERATIONS .................................................................... B3.9.a-1 B3.9.a Communications ...................................................................................... B3.9.a-1 B4.0 Not Used B5.0 Not Used Quad Cities 1 and 2 ii Revision 0

TRM Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

NOTE----------------------------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Requirements Manual and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Requirement that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

(continued)

Quad Cities 1 and 2 1.1-1 Revision 0

TRM Definitions 1.1 1.1 Definitions (continued)

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and

b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Technical Specification 5.6.5. Plant operation within these limits is addressed in individual requirements.

LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of TEST 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 (continued)

Quad Cities 1 and 2 1.1-2 Revision 0

1.1 Definitions (continued)

LOGIC SYSTEM FUNCTIONAL FUNCTIONAL TEST may be performed by means of any TEST series of sequential overlapping, or total system (continued) steps so that the entire logic system is tested.

MODE A MODE shall correspond to any one inclusive combination of MODE switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Technical Specifications Table 1.1-1 with fuel in the reactor vessel.

OFFSITE DOSE CALCULATION The ODCM shall contain the methodology and MANUAL (ODCM) parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports.

OPERABLE - OPERABILITY 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).

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to (RTP) the reactor coolant of 2957 MWt.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

Quad Cities 1 and 2 1.1-3 Revision QC-TRM-02-007

TRM Logical Connectors 1.2 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Requirements Manual (TRM) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TRM are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).

The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

EXAMPLES The following examples illustrate the use of logical connectors.

(continued)

Quad Cities 1 and 2 1.2-1 Revision 0

TRM Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-1 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. TLCO not A.1 Verify . . .

met.

AND A.2 Restore . . .

In this example, the logical connector AND is used to indicate that, when in Condition A, both Required Actions A.1 and A.2 must be completed.

(continued)

Quad Cities 1 and 2 1.2-2 Revision 0

TRM Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. TLCO not A.1 Trip . . .

met.

OR A.2.1 Verify . . .

AND A.2.2.1 Reduce . . .

OR A.2.2.2 Perform . . .

OR A.3 Align . . .

This example represents a more complicated use of logical connectors.

Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Quad Cities 1 and 2 1.2-3 Revision 0

TRM Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Technical Requirements Manual Limiting Conditions for Operation (TLCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with a TLCO state Conditions that typically describe the ways in which the requirements of the TLCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the discovery of a situation (e.g.,

inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the TLCO.

Unless otherwise specified, the Completion Time begins when a senior licensed operator on the operating shift crew with responsibility for plant operations makes the determination that an LCO is not met and an ACTIONS Condition is entered. The otherwise specified exceptions are varied, such as a Required Action Note or Surveillance Requirement Note that provides an alternative time to perform specific tasks, such as testing, without starting the Completion Time. While utilizing the Note, should a Condition be applicable for any reason not addressed by the Note, the Completion Time begins. Should the time allowance in the Note be exceeded, the Completion Time begins at that point. The exceptions may also be incorporated into the Completion Time. For example, LCO 3.8.1, AC Sources - Operating, Required Action B.2, requires declaring required feature(s) supported by an inoperable diesel generator, inoperable when the redundant required feature(s) are inoperable. The Completion Time states, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery of Condition B concurrent with inoperability of redundant required feature(s). In this case the Completion Time does not begin until the conditions in the Completion Time are satisfied. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the TLCO Applicability.

(continued)

Quad Cities 1 and 2 1.3-1 Revision QC-TRM-19-011

TRM Completion Times

1.3 DESCRIPTION

(continued) If situations are discovered that require entry into more than one Condition at a time within a single TLCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the discovery of the situation that required entry into the Condition, unless otherwise specified.

Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition, unless otherwise specified.

However, when a subsequent division, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extension does not apply to those TLCOs that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual TLCOs.

(continued)

Quad Cities 1 and 2 1.3-2 Revision QC-TRM-19-011

TRM Completion Times

1.3 DESCRIPTION

(continued) The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . . ."

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and associated Completion AND Time not met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for reaching MODE 4 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

(continued)

Quad Cities 1 and 2 1.3-3 Revision QC-TRM-19-011

TRM Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required Action B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and associated Completion AND Time not met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a pump is declared inoperable, Condition A is entered. If the pump is not restored to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump.

TLCO 3.0.c is entered, since the ACTIONS do not include a Condition for more than one inoperable pump. The Completion Time clock for Condition A does not stop after TLCO 3.0.c is entered, but continues to be tracked from the time Condition A was initially entered.

While in TLCO 3.0.c, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired, TLCO 3.0.c may be exited and operation continued in accordance with Condition A.

(continued)

Quad Cities 1 and 2 1.3-4 Revision QC-TRM-19-011

TRM Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

While in TLCO 3.0.c, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has expired, TLCO 3.0.c may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.

On restoring one of the pumps to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first pump was declared inoperable. This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for > 7 days.

(continued)

Quad Cities 1 and 2 1.3-5 Revision QC-TRM-19-011

TRM Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore Function X 7 days Function X subsystem to subsystem OPERABLE status.

inoperable.

B. One B.1 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y subsystem to subsystem OPERABLE status.

inoperable.

C. One C.1 Restore Function X 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X subsystem to subsystem OPERABLE status.

inoperable.

AND OR One C.2 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y subsystem to subsystem OPERABLE status.

inoperable.

(continued)

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TRM Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.

(continued)

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TRM Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one or more valves are still inoperable, Condition B is entered.

(continued)

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TRM Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

ACTIONS

NOTE----------------------------------------

Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

(continued)

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TRM Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. TSR 3.x.x.x.

OR A.2 Reduce 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months THERMAL POWER to

< 50% RTP.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated Completion Time not met.

(continued)

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TRM Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-6 (continued)

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per TSR 3.0.b, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be completed within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by TSR 3.0.b),

Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

(continued)

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TRM Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem inoperable. isolated. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem to OPERABLE status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by TSR 3.0.b), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A.1 (continued)

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TRM Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued) is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

IMMEDIATE When "Immediately" is used as a Completion Time, the COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.

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TRM Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Technical Requirements Manual Surveillance Requirement (TSR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Technical Requirements Manual Limiting Condition for Operation (TLCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the TSR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Technical Requirements Manual Surveillance Requirement (TSR) Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each TSR, as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by TSR 3.0.a. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both. Example 1.4-4 discusses these special situations.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated TLCO is within its Applicability, represent potential TSR 3.0.d conflicts. To avoid these conflicts, the TSR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an TSR satisfied, TSR 3.0.d imposes no restriction.

The use of "met" or "performed" in these instances conveys specified meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to (continued)

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TRM Frequency 1.4 1.4 Frequency DESCRIPTION specifically determine the ability to meet the acceptance (continued) criteria. TSR 3.0.d restrictions would not apply if both the following conditions are satisfied:

a. The Surveillance is not required to be performed; and

b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the TLCO (TLCO not shown) is MODES 1, 2, and 3.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of TSR most often encountered in the Technical Requirements Manual (TRM). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by TSR 3.0.b for operational flexibility. The measurement of this interval continues at all times, even when the TSR is not required to be met per TSR 3.0.a (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the TLCO). If the interval specified by TSR 3.0.b is exceeded while the unit is in a MODE or other specified condition in the (continued)

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TRM Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-1 (continued)

Applicability of the TLCO, and the performance of the Surveillance is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then TSR 3.0.c becomes applicable.

If the interval as specified by TSR 3.0.b is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the TLCO for which performance of the TSR is required, the Surveillance must be performed within the Frequency requirements of TSR 3.0.b prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of TSR 3.0.d.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

> 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

< 25% RTP to > 25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

(continued)

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TRM Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

This type of Frequency does not qualify for the extension allowed by TSR 3.0.b.

"Thereafter" indicates future performances must be established per TSR 3.0.b, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

NOTE-----------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

> 25% RTP.

Perform channel adjustment. 7 days The interval continues whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches > 25% RTP to perform the Surveillance. The Surveillance is still considered to be within the "specified Frequency."

Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension (continued)

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TRM Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued) allowed by TSR 3.0.b), but operation was < 25% RTP, it would not constitute a failure of the TSR or failure to meet the TLCO. Also, no violation of TSR 3.0.d occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power > 25% RTP.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of TSR 3.0.c would apply.

EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

NOTE-----------------------------

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance were not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by TSR 3.0.b), but the unit was not in MODE 1, there would be no failure of the TSR nor failure to meet the TLCO. Therefore, no violation of TSR 3.0.d occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), TSR 3.0.d would require satisfying the TSR.

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TRM TLCO and TSR Implementation 1.5 1.0 USE AND APPLICATION 1.5 TLCO and TSR Implementation The Technical Requirements Manual (TRM) provides those limitations upon plant operations which are part of the licensing basis for the station but do not meet the criteria for continued inclusion in the Technical Specifications.

It also provides information which supplements the Technical Specifications. Nothing in the TRM shall supersede any Technical Specification requirement.

TLCOs and TSRs are implemented the same as Technical Specifications (see TRM 3.0). However, TLCOs and TSRs are treated as plant procedures and are not part of the Technical Specifications. Therefore the following exceptions apply:

a. Violations of the Action or Surveillance requirements in a TLCO are not reportable as conditions prohibited by, or deviations from, the Technical Specifications per 10 CFR 50.72 or 10 CFR 50.73, unless specifically required by the TRM.

b. Power reduction or plant shutdowns required to comply with the Actions of a TLCO or as a result of the application of TLCO 3.0.c are not reportable per 10 CFR 50.72 or 10 CFR 50.73.

c. Violations of TLCO or TSR requirements, except as provided for in TLCO 3.0 of this manual, shall be treated the same as plant procedure violations.

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TRM Technical Requirements Manual Revisions 1.6 1.0 USE AND APPLICATION 1.6 Technical Requirements Manual Revisions Changes to this manual shall be made under the following provisions:

a. Changes to the TRM shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to TRM without prior NRC approval provided the change does not require NRC approval pursuant to 10 CFR 50.59.

c. The TRM revision process shall contain provisions to ensure that the TRM is maintained consistent with the UFSAR.

d. Proposed changes that require NRC approval prior to shall be reviewed and approved by the NRC prior to implementation. Changes to the TRM implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e) as modified by approved exemptions.

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TRM Miscellaneous Test Requirements 2.1.a 2.1.a MISCELLANEOUS TEST REQUIREMENTS

NOTE-------------------------------------------------------------------

Failure to meet the surveillance requirement require immediate actions to determine OPERABILITY of the associated equipment.

APPLICABILITY: As defined in the TSR.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 2.1.a.1 -----------------------------NOTE---------------------------

Only applicable in MODES 1 and 2.

Verify reactor recirculation control system programmed 24 months maximum speed limit setting and adjustable speed drive programmed maximum speed limit setting are within the limits specified by the COLR.

(continued)

Quad Cities 1 and 2 2.1.a-1 Revision QC-TRM-09-002

TRM Miscellaneous Test Requirements 2.1.a SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 2.1.a.2 ---------------------------NOTE-------------------------------

TSR 2.1.a.2 provides the scram time limits for <800 psig steam dome pressure to satisfy Technical Specification SR 3.1.4.3 and is only applicable in MODES 1 and 2.

Verify each affected control rod scram time is within Prior to declaring limits of Technical Specification Table 3.1.4-1 with control rod any reactor pressure. The control rod scram time OPERABLE after acceptance criteria shall be < 2.04 seconds from fully work on the withdrawn position to 90% insertion at 0 psig reactor control rod or CRD steam dome pressure. System that could affect scram time TSR 2.1.a.3 -----------------------------NOTE-------------------------------

Only applicable when associated diesel generator is required to be OPERABLE.

Drain each diesel generator fuel oil storage tank, 10 years remove the accumulated sediment, and clean the tank.

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TRM TLCO Applicability 3.0 3.0 TECHNICAL REQUIREMENTS MANUAL LIMITING CONDITION FOR OPERATION (TLCO) APPLICABILITY TLCO 3.0.a TLCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in TLCO 3.0.b.

TLCO 3.0.b Upon discovery of a failure to meet a TLCO, the Required Actions of the associated Conditions shall be met, except as provided in TLCO 3.0.e.

If the TLCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

TLCO 3.0.c When a TLCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to:

a. Implement appropriate compensatory actions as needed;

b. Verify that the plant is not in an unanalyzed condition(s) or that a required safety function is not compromised by the inoperabilities; and

c. Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , obtain Station Duty Officer approval of the compensatory actions and the plan for exiting TLCO 3.0.c.

Exceptions to this TLCO are stated in the individual TLCOs.

Where corrective measures are completed that permit operation in accordance with the TLCO or ACTIONS, completion of the actions required by TLCO 3.0.c is not required.

TLCO 3.0.c is only applicable in MODES 1, 2, and 3.

TLCO 3.0.d When an TLCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

1. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time; (continued)

Quad Cities 1 and 2 3.0-1 Revision QDC-TRM-05-003

TRM TLCO Applicability 3.0 3.0 TLCO APPLICABILITY (continued)

TLCO 3.0.d 2. After performance of a risk assessment addressing inoperable (continued) systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate (exceptions to this TLCO are stated in the individual TLCOs); or

3. When an allowance is stated in the individual value, parameter, or other TLCO.

This TLCO shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

TLCO 3.0.e Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to TLCO 3.0.b for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

TLCO 3.0.f TLCOs, including associated ACTIONS, shall apply to each unit individually, unless otherwise indicated. Whenever the TLCO refers to a system or component that is shared by both units, the ACTIONS will apply to both units simultaneously.

Quad Cities 1 and 2 3.0-2 Revision QDC-TRM-17-006

TRM TSR Applicability 3.0 3.0 TECHNICAL REQUIREMENTS MANUAL SURVEILLANCE REQUIREMENT (TSR)

APPLICABILITY TSR 3.0.a TSRs shall be met during the MODES or other specified conditions in the Applicability for individual TLCOs, unless otherwise stated in the TSR.

Failure to meet a TSR, whether such failure is experienced during the performance of the TSR or between performances of the TSR, shall be failure to meet the TLCO. Failure to perform a TSR within the specified Frequency shall be failure to meet the TLCO except as provided in TSR 3.0.c. TSRs do not have to be performed on inoperable equipment or variables outside specified limits.

TSR 3.0.b The specified Frequency for each TSR is met if the TSR is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per . . ."

basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this TSR are stated in the individual TSRs.

TSR 3.0.c If it is discovered that a TSR was not performed within its specified Frequency, then compliance with the requirement to declare the TLCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the TSR. The delay period is only applicable when there is a reasonable expectation the surveillance will be met when performed. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the TSR is not performed within the delay period, the TLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the TSR is performed within the delay period and the TSR is not met, the TLCO must immediately be declared not met, and the applicable Condition(s) must be entered.

(continued)

Quad Cities 1 and 2 3.0-3 Revision QC-TRM-17-006

TRM TSR Applicability 3.0 3.0 TSR APPLICABILITY (continued)

TSR 3.0.d Entry into a MODE or other specified condition in the Applicability of an TLCO shall only be made when the TLCO's TSRs have been met within their specified Frequency, except as provided by TSR 3.0.c. When an TLCO is not met due to TSRs not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with TLCO 3.0.d.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

TSR 3.0.e TSRs shall apply to each unit individually, unless otherwise indicated.

Quad Cities 1 and 2 3.0-4 Revision QC-TRM-05-003

This Section Intentionally Blank Technical Requirements Manual Section 3.1 Not Used

TRM Control Rod Block Instrumentation 3.3.a 3.3 INSTRUMENTATION 3.3.a Control Rod Block Instrumentation TLCO 3.3.a The control rod block instrumentation for each Function in Table T3.3.a-1 shall be OPERABLE.

APPLICABILITY: According to Table T3.3.a-1.

ACTIONS

NOTE------------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. For Functions 1.a, 1.b, 1.c, A.1 Restore inoperable channel 7 days 1.d, 2.a, 2.b, 2.c, 3.a, 3.b, to OPERABLE status.

3.c, and 3.d, one required channel inoperable.

B. For Functions 4.a and 4.b, B.1 Place inoperable channels 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months one or more required in trip.

channels inoperable.

(continued)

Quad Cities 1 and 2 3.3.a-1 Revision 0

TRM Control Rod Block Instrumentation 3.3.a ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. For Functions 1.a, 1.b, 1.c, C.1 Place inoperable channels in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1.d, 2.a, 2.b, 2.c, 3.a, 3.b, trip.

3.c, and 3.d, two or more required channels inoperable.

OR Required Action and associated Completion Time of Condition A not met.

Quad Cities 1 and 2 3.3.a-2 Revision 0

TRM Control Rod Block Instrumentation 3.3.a SURVEILLANCE REQUIREMENTS

NOTES---------------------------------------------------------------

1. Refer to Table T3.3.a-1 to determine which TSRs apply to each Control Rod Block Function.

2. 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains Control Rod Block capability.

SURVEILLANCE FREQUENCY TSR 3.3.a.1 -------------------------------NOTE-------------------------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 31 days TSR 3.3.a.2 -----------------------------NOTE--------------------------------

For Function 1.d, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2 Perform CHANNEL FUNCTIONAL TEST. 92 days TSR 3.3.a.3 --------------------------------NOTES-----------------------------

1. For Function 1.d, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

2. Neutron detectors are excluded.

3. For Function 1.a, not required for the flow portion of the channels.

Perform CHANNEL CALIBRATION. 184 days (continued)

Quad Cities 1 and 2 3.3.a-3 Revision QC-TRM-21-003

TRM Control Rod Block Instrumentation 3.3.a SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.a.4 -----------------------------NOTE-----------------------------

1. Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

2. Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 18 months TSR 3.3.a.5 Perform CHANNEL FUNCTIONAL TEST. 24 months TSR 3.3.a.6 -----------------------------NOTE-----------------------------

1. Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

2. Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 24 months Quad Cities 1 and 2 3.3.a-4 Revision 0

TRM Control Rod Block Instrumentation 3.3.a Table T3.3.a-1 (page 1 of 2)

Control Rod Block Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION REQUIREMENTS VALUE

1. Average Power Range Monitors

a. Flow Biased Neutron Flux 1 4 TSR 3.3.a.2 < 0.56W + 55.4%(a)

High TSR 3.3.a.3 RTP and d 109.9%

RTP

b. Inoperative 1, 2, 5(e) 4 TSR 3.3.a.2 N.A.

c. Downscale 1 4 TSR 3.3.a.2 > 3.5 % RTP TSR 3.3.a.3

d. Neutron Flux High, Setdown 2,5(e) 4 TSR 3.3.a.2 < 14.1 % RTP TSR 3.3.a.3

2. Source Range Monitors

a. Detector not full in 2(b)(d) 3 TSR 3.3.a.1 N.A.

TSR 3.3.a.6 5(d)(h) 2 TSR 3.3.a.1 N.A.

TSR 3.3.a.6

b. Upscale 2(c) 3 TSR 3.3.a.1 < 2.8 x 105 cps TSR 3.3.a.4 5(h) 2 TSR 3.3.a.1 <2.8 x 105 cps TSR 3.3.a.4

c. Inoperative 2(c) 3 TSR 3.3.a.1 N.A.

5(h) 2 TSR 3.3.a.1 N.A.

(continued)

(a) Allowable Value is d 0.56W + 51.2% RTP and d 109.9% RTP when reset for single loop operation per Technical Specification 3.4.1, "Recirculation Loops Operating."

(b) With the Intermediate Range Monitor (IRM) channels are on range 2 or below.

(c) With IRM channels on range 7 or below.

(d) With detector count rate less than or equal to the Allowable Value (Detector Not Full In AV t 163 cps).

(e) Required to be OPERABLE only during SHUTDOWN MARGIN demonstrations performed per Specification 3.10.7.

Quad Cities 1 and 2 3.3.a-5 Revision QC-TRM-01-004 & QC-TRM-02-005

TRM Control Rod Block Instrumentation 3.3.a Table T3.3.a-1 (page 2 of 2)

Control Rod Block Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION REQUIREMENTS VALUE

3. Intermediate Range Monitors

a. Detector not full in 2, 5(h) 6 TSR 3.3.a.1 N.A.

TSR 3.3.a.6

b. Upscale 2, 5(h) 6 TSR 3.3.a.1 < 112/125 of full TSR 3.3.a.6 scale

c. Inoperative 2, 5(h) 6 TSR 3.3.a.1 N.A.

d. Downscale(f) 2, 5(h) 6 TSR 3.3.a.1 > 5/125 of full TSR 3.3.a.6 scale

4. Scram Discharge Volume

a. Water Level High 1, 2, 5(g) 1 per bank TSR 3.3.a.2 < 25.5 gal

b. Scram Discharge Volume 5(g) 1 TSR 3.3.a.5 N.A.

Switch in Bypass (f) With IRM channels on range 2 or higher.

(g) With two or more control rods withdrawn. Not applicable to control rods removed per Technical Specification 3.10.4, "Single Control Rod Drive Removed Refueling", or 3.10.5, "Multiple Control Rod Withdrawal Refueling."

(h) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

Quad Cities 1 and 2 3.3.a-6 Revision QC-TRM-02-005

TRM PAM Instrumentation 3.3.b 3.3 INSTRUMENTATION 3.3.b Post Accident Monitoring (PAM) Instrumentation TLCO 3.3.b The PAM instrumentation for each Function in Table T3.3.b-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel to 30 days with one required channel OPERABLE status.

inoperable.

B. One or more Functions B.1 Restore one required 7 days with two required channel to OPERABLE channels inoperable. status.

NOTE ---------------

Functions 1, 2, 3, and 4 only.

C. Required Action and C.1 Initiate alternate method of Immediately associated Completion monitoring the appropriate Time of Condition A or B parameters.

not met.

AND C.2 Prepare a corrective action Immediately program report.

Quad Cities 1 and 2 3.3.b-1 Revision QC-TRM-05-008

TRM PAM Instrumentation 3.3.b ACTIONS

NOTE ---------------

Functions 5 and 6 only.

D. Required Action and D.1 Prepare a corrective action Immediately associated Completion program report.

Time of Condition A or B not met. AND D.2 Initiate alternate method of Immediately monitoring the appropriate parameters.

OR D.3 Enter TLCO 3.0.c Quad Cities 1 and 2 3.3.b-2 Revision QC-TRM-05-008

TRM PAM Instrumentation 3.3.b SURVEILLANCE REQUIREMENTS

NOTE-------------------------------------------------------------

1. These TSRs apply to each Function in Table T3.3.b-1, except where identified in the TSR.

2. 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the other required channel in the associated Function is OPERABLE.

SURVEILLANCE FREQUENCY TSR 3.3.b.1 Perform CHANNEL CHECK. 31 days TSR 3.3.b.2 ----------------------------NOTE---------------------------

Functions 5 and 6 only.

Perform CHANNEL CALIBRATION. 92 days TSR 3.3.b.3 ----------------------------NOTE---------------------------

1. Function 3 only.

2. Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 18 months TSR 3.3.b.4 ----------------------------NOTE---------------------------

Functions 1, 2, and 4 only.

Perform CHANNEL CALIBRATION. 24 months Quad Cities 1 and 2 3.3.b-3 Revision QC-TRM-05-008

TRM PAM Instrumentation 3.3.b Table T3.3.b-1 (page 1 of 1)

Post Accident Monitoring Instrumentation REQUIRED FUNCTION CHANNELS

1. Drywell Air Temperature 2

2. Safety/Relief Valve Position Indicators Acoustic and Temperature 2/valve (1 each)

3. Source Range Neutron Monitors 2

4. Torus Air Temperature 2

5. Drywell H2 Concentration Analyzer and Monitor 2

6. Drywell O2 Concentration Analyzer and Monitor 2 Quad Cities 1 and 2 3.3.b-4 Revision QC-TRM-05-008

TRM Explosive Gas Monitoring Instrumentation 3.3.c 3.3 INSTRUMENTATION 3.3.c Explosive Gas Monitoring Instrumentation TLCO 3.3.c The explosive gas monitoring instrumentation channels in Table T3.3.c-1 shall be OPERABLE with their Alarm/Trip Setpoints set to ensure that the limits of the Explosive Gas and Storage Tank Radioactivity Monitoring Program are not exceeded.

APPLICABILITY: During operation of the Offgas Holdup System.

ACTIONS

NOTE---------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required channel A.1.1 Take grab samples. Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable.

OR (continued)

Quad Cities 1 and 2 3.3.c-1 Revision 0

TRM Explosive Gas Monitoring Instrumentation 3.3.c ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.1.2 ---------NOTE--------

Only applicable if recombiner(s) temperature remains constant and THERMAL POWER has not changed.

Take grab samples. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND A.2 Analyze grab samples. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following each grab sample AND A.3.1 Restore channel to 30 days OPERABLE status.

OR A.3.2 Prepare a corrective 30 days action program report.

Quad Cities 1 and 2 3.3.c-2 Revision 0

TRM Explosive Gas Monitoring Instrumentation 3.3.c SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.c.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TSR 3.3.c.2 Perform CHANNEL FUNCTIONAL TEST. 31 days TSR 3.3.c.3 Perform CHANNEL CALIBRATION. 180 days Quad Cities 1 and 2 3.3.c-3 Revision QC-TRM-01-006

TRM Explosive Gas Monitoring Instrumentation 3.3.c Table T3.3.c-1 (page 1 of 1)

Explosive Gas Monitoring Instrumentation INSTRUMENT REQUIRED CHANNELS Main Condenser Offgas Treatment System Explosive Gas 1 Monitoring System Hydrogen Monitor Quad Cities 1 and 2 3.3.c-4 Revision 0

TRM Suppression Chamber and Drywell Spray Actuation Instrumentation 3.3.d 3.3 INSTRUMENTATION 3.3.d Suppression Chamber and Drywell Spray Actuation Instrumentation TLCO 3.3.d The suppression chamber and drywell spray actuation instrumentation shown in Table 3.3.d-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTE-------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place one inoperable 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable in one trip channel in trip such that it system. will not prevent containment spray.

B. One or more channels B.1 Declare Suppression Immediately inoperable in both trip Chamber and Drywell Spray systems. Actuation mode of the Residual Heat Removal OR system inoperable.

Required Action and Associated Completion Time of Condition A not met.

Quad Cities 1 and 2 3.3.d-1 Revision 0

TRM Suppression Chamber and Drywell Spray Actuation Instrumentation 3.3.d SURVEILLANCE REQUIREMENTS

NOTES----------------------------------------------------------

1. Refer to Table T3.3.d-1 to determine which TSRs apply to each Function.

2. 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains suppression chamber and drywell spray actuation capability.

SURVEILLANCE FREQUENCY TSR 3.3.d.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TSR 3.3.d.2 Perform CHANNEL FUNCTIONAL TEST. 92 days TSR 3.3.d.3 Calibrate the trip units. 92 days TSR 3.3.d.4 Perform CHANNEL CALIBRATION. 92 days TSR 3.3.d.5 Perform CHANNEL CALIBRATION. 24 months TSR 3.3.d.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months Quad Cities 1 and 2 3.3.d-2 Revision 0

TRM Suppression Chamber and Drywell Spray Actuation Instrumentation 3.3.d Table T3.3.d-1 (page 1 of 1)

Suppression Chamber and Drywell Spray Actuation Instrumentation REQUIRED NUMBER OF CHANNELS PER TRIP SURVEILLANCE ALLOWABLE FUNCTION SYSTEM REQUIREMENTS VALUE

1. Drywell Pressure High (permissive) 2 TSR 3.3.d.2 > 0.56 psig TSR 3.3.d.4 and TSR 3.3.d.6 < 1.44 psig

2. Reactor Vessel Water Level Low (permissive) 1 TSR 3.3.d.1 > -175.7 TSR 3.3.d.2 inches TSR 3.3.d.3 TSR 3.3.d.5 TSR 3.3.d.6 Quad Cities 1 and 2 3.3.d-3 Revision 0

TRM Toxic Gas Monitoring System 3.3.e 3.3 INSTRUMENTATION 3.3.e Toxic Gas Monitoring System TLCO 3.3.e The Toxic Gas Monitoring System shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Toxic Gas Monitoring A.1 Initiate and maintain Control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months System inoperable. Room Emergency Ventilation System in the isolation mode of operation.

B. One Toxic Gas Monitor B.1 Restore channel to 30 days channel inoperable. OPERABLE status.

C. Required Action and C.1 Prepare a corrective action Immediately associated Completion program report (Condition Time of Condition A or B Report).

not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.3.e.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months TSR 3.3.e.2 Perform CHANNEL FUNCTIONAL TEST. 92 days TSR 3.3.e.3 Perform CHANNEL CALIBRATION. The Allowable 12 months Value shall be < 50 ppm concentration of ammonia.

Quad Cities 1 and 2 3.3.e-1 Revision QC-TRM-03-001

TRM RWCU Area Temperature Monitoring 3.3.f 3.3 INSTRUMENTATION 3.3.f Reactor Water Cleanup (RWCU) Area Temperature Monitoring TLCO 3.3.f Temperature monitors listed in Table T3.3f-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3 with the RWCU system unisolated.

ACTIONS

NOTE----------------------------------------------------------

Separate Condition entry is allowed for each temperature monitor.

CONDITION REQUIRED ACTION COMPLETION TIME A. With one temperature A.1 Restore inoperable 30 days monitor inoperable. temperature monitor to OPERABLE status.

AND (continued)

Quad Cities 1 and 2 3.3.f-1 Revision 0

TRM RWCU Area Temperature Monitoring 3.3.f ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.1 ---------NOTE---------

For RWCU heat exchanger and Phase Separator Rooms only.

Observe area 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months temperature. AND twice per shift thereafter AND A.2.2 ---------NOTE---------

For D Heater Bay area only.

Monitor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Non-Regenerative Heat AND twice per shift Exchanger Discharge thereafter temperature and RWCU Discharge Pressure.

B. With less than the B.1 Isolate the RWCU 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months minimum requirement in system.

any area.

OR One or more Main Steam Tunnel Temperature Isolation Bypass switches at panel 901-4 in bypass.

OR Required Action and Associated Completion Time of Condition A not met.

Quad Cities 1 and 2 3.3.f-2 Revision 0

TRM RWCU Area Temperature Monitoring 3.3.f SURVEILLANCE REQUIREMENTS

NOTE------------------------------------------------------------

TSRs apply to each monitor in Table T3.3.f-1.

SURVEILLANCE FREQUENCY TSR 3.3.f.1 --------------------------NOTE--------------------------------

Not required for Main Steam Tunnel Temperature switches.

Perform a resistance check of the temperature 24 months monitor.

TSR 3.3.f.2 Perform a functional test of the temperature monitor. 24 months TSR 3.3.f.3 Perform a logic test of the temperature monitor. 24 months TSR 3.3.f.4 Perform a calibration of the temperature monitor. 24 months Quad Cities 1 and 2 3.3.f-3 Revision 0

TRM RWCU Area Temperature Monitoring 3.3.f Table T3.3.f-1 (page 1 of 1)

RWCU Temperature Monitoring MINIMUM PARAMETER INSTRUMENT AFFECTED LOGIC REQUIREMENT RWCU Heat Exchanger 1(2)-1291-60K RWCU Isolation Panel 1 Room Temperature 1(2)-1291-60L 2201(2)-77B 1(2)-1291-60N RWCU Isolation Panel 1 1(2)-1291-60P 2201(2)-77A Phase Separator Area 1(2)-1291-60J RWCU System Panels 2 1(2)-1291-60M 2201-(2)-77A and 2201(2)-77B D Heater Bay 1(2)-1291-60R RWCU System Panel 1 1(2)-1291-60S 2201-(2)-77B 1(2)-1291-60T RWCU System Panel 1 1(2)-1291-60U 2201-(2)-77A MST Temperature NA RWCU Inboard and NA Isolation Bypass(a) Outboard Isolation Valves (a) Either bypass switch at panel 901(2)-4 in bypass.

Quad Cities 1 and 2 3.3.f-4 Revision 0

TRM Structural Integrity 3.4.a 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.a Structural Integrity TLCO 3.4.a The structural integrity of ASME Code Class 1, 2, and 3 components shall be maintained in accordance with the Inservice Inspection and Testing Programs.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTIONS

NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each component.

CONDITION REQUIRED ACTION COMPLETION TIME A. ---------------NOTE------------- A.1 Restore the structural Prior to increasing Only applicable to ASME integrity of the affected the RCS temperature Code Class 1 components. component to within its to > 50 F above the

limits. minimum temperature required Structural integrity of one by NDT or more ASME considerations component(s) not in OR conformance.

A.2 Isolate the affected Prior to increasing component. the RCS temperature to > 50 F above the minimum temperature required by NDT considerations (continued)

Quad Cities 1 and 2 3.4.a-1 Revision QC-TRM-12-003

TRM Structural Integrity 3.4.a ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. --------------NOTE-------------- B.1 Restore the structural Immediately Only applicable to ASME integrity of the affected Code Class 2 components. components to within its

limits.

Structural integrity of one OR or more ASME component(s) not in conformance. B.2 Isolate the affected Immediately component.

C. ---------------NOTE------------- C.1 Restore the structural Immediately Only applicable to ASME integrity of the affected Code Class 3 components. components to within its

limits.

Structural integrity of one or more ASME OR component(s) not in conformance.

C.2 Isolate the affected Immediately component.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.a.1 Verify the structural integrity of ASME Code Class 1, 2, In accordance with and 3 components. the Inservice Inspection and Testing Programs Quad Cities 1 and 2 3.4.a-2 Revision QC-TRM-12-003

TRM RCS Chemistry 3.4.b 3.4 REACTOR COOLANT SYSTEM 3.4.b Reactor Coolant System (RCS) Chemistry TLCO 3.4.b The chemistry of the RCS shall be maintained within the limits specified in Table T3.4.b-1.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS chemistry not within A.1 Determine chlorides. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months limits in MODE 1. when conductivity is not within limit AND A.2 Perform TSR 3.4.b.4. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when conductivity is AND not within limit A.3 Restore RCS chemistry 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to within limits.

AND 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months cumulative in the past 365 days B. Required Action and B.1 Be in MODE 2. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated Completion Time of Condition A not met.

(continued)

Quad Cities 1 and 2 3.4.b-1 Revision QC-TRM-01-005

TRM RCS Chemistry 3.4.b ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. Conductivity C.1 Be in MODE 2. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

> 10 mho/cm at 25oC in MODE 1.

OR Chloride concentration

> 0.5 ppm in MODE 1.

D. -------------NOTE------------- D.1 Determine chlorides. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Not applicable during when conductivity is Noble Metal Chemical not within limit Applications (injection and cleanup periods). AND D.2 Perform TSR 3.4.b.4. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months RCS chemistry not within when conductivity is required limits in MODE 2 not within limit or 3. AND D.3 Restore RCS chemistry 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to within limits.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition D not AND met.

E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. RCS chemistry not within F.1 Initiate action to be in Immediately required limits in MODE 3 MODE 4.

during Noble Metal Chemical Application (injection and cleanup).

Quad Cities 1 and 2 3.4.b-2 Revision QC-TRM-01-005

TRM RCS Chemistry 3.4.b SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.4.b.1 --------------------------------NOTE------------------------------

Only applicable when the continuous recording conductivity monitor is inoperable.

Obtain an in-line conductivity measurement of the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months reactor coolant.

TSR 3.4.b.2 Analyze a sample of the reactor coolant for chlorides 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and conductivity.

TSR 3.4.b.3 -----------------------------NOTE-------------------------------

Only applicable during Noble Metal application (injection and cleanup).

Analyze a sample of the reactor coolant for pH. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months TSR 3.4.b.4 Perform a CHANNEL CHECK of the continuous 7 days conductivity monitor with an in-line flow cell.

Quad Cities 1 and 2 3.4.b-3 Revision QC-TRM-01-005

TRM RCS Chemistry 3.4.b Table T3.4.b-1 (page 1 of 1)

Reactor Coolant System Chemistry Limits MODE CHLORIDES CONDUCTIVITY o

(ppm) (mhos/cm at 25 C) 1 < 0.2 < 1.0 2, 3(a) < 0.1 < 2.0 3(b) < 0.1 < 10.0 (a) Except during Noble Metal Chemical Applications.

(b) During Noble Metal Chemical Applications.

Quad Cities 1 and 2 3.4.b-4 Revision QC-TRM-01-005

TRM RHRSW System Shutdown 3.7.a 3.7 PLANT SYSTEMS 3.7.a Residual Heat Removal Service Water (RHRSW) System Shutdown TLCO 3.7.a For each required OPERABLE RHR system, a RHRSW subsystem shall be OPERABLE.

APPLICABILITY: MODES 4 and 5, During movement of recently irradiated fuel assemblies in secondary containment, During operations with a potential for draining the reactor vessel.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare supported safety- Immediately RHRSW subsystems related equipment inoperable. inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.a.1 Verify each RHRSW manual, power operated, and 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

Quad Cities 1 and 2 3.7.a-1 Revision QC-TRM-07-003

TRM DGCW Shutdown 3.7.b 3.7 PLANT SYSTEMS 3.7.b Diesel Generator Cooling Water (DGCW) System Shutdown TLCO 3.7.b The DGCW System shall be OPERABLE with:

1. One OPERABLE DGCW pump per required subsystem, and

2. An OPERABLE flow path capable of taking suction from the Ultimate Heat Sink and transferring water to the associated diesel generator.

3. An operable DGCW pump capable of transferring cooling water to the Emergency Core Cooling System (ECCS) room emergency coolers.

APPLICABILITY: MODES 4 and 5 when the associated diesel generator or ECCS is required to be OPERABLE.

ACTIONS

NOTE-----------------------------------------------------

Separate Condition entry is allowed for each DGCW subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required DGCW A.1 Declare associated diesel Immediately subsystem inoperable generator inoperable.

and not capable of supporting its associated DG.

(continued)

Quad Cities 1 and 2 3.7.b-1 Revision 0

TRM DGCW Shutdown 3.7.b ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required DGCW B.1 Align a DGCW subsystem 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem inoperable to the ECCS room and not capable of emergency coolers.

supporting the ECCS room emergency OR coolers.

B.2 Evaluate ECCS operability 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months without ECCS room emergency coolers.

OR B.3 Declare the supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ECCS components inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.b.1 Verify each required DGCW subsystem valve in the 31 days flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

TSR 3.7.b.2 Verify each required DGCW pump starts automatically 24 months on an actual or simulated initiation signal.

Quad Cities 1 and 2 3.7.b-2 Revision QC-TRM-19-006

TRM UHS Shutdown 3.7.c 3.7 PLANT SYSTEMS 3.7.c Ultimate Heat Sink (UHS) Shutdown TLCO 3.7.c The UHS shall be OPERABLE.

APPLICABILITY: MODES 4 and 5, During movement of irradiated fuel assemblies in secondary containment, During CORE ALTERATIONS, ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. UHS inoperable in MODE A.1 Declare the required Immediately 4 and 5. Residual Heat Removal Service Water subsystems and Diesel Generator Cooling Water subsystems inoperable.

B. UHS inoperable during B.1 Declare the required Diesel Immediately movement of irradiated Generator Cooling Water fuel assemblies in subsystems inoperable.

secondary containment or during CORE ALTERATIONS.

Quad Cities 1 and 2 3.7.c-1 Revision QC-TRM-19-010

TRM UHS Shutdown 3.7.c SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.c.1 Verify average water temperature is < 95oF. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TSR 3.7.c.2 Verify water level is > 568 ft mean sea level. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Quad Cities 1 and 2 3.7.c-2 Revision QC-TRM-19-010

TRM Liquid Holdup Tanks 3.7.d 3.7 PLANT SYSTEMS 3.7.d Liquid Holdup Tanks TLCO 3.7.d The quantity of radioactive material contained in any outside tanks shall be less than or equal to the limits calculated in the OFFSITE DOSE CALCULATION MANUAL.

APPLICABILITY: At all times.

ACTIONS

NOTE-------------------------------------------------------

Separate Conditions entry is allowed for each tank.

CONDITION REQUIRED ACTION COMPLETION TIME A. Quantity of radioactive A.1 Suspend all additions of Immediately material in one or more of radioactive material to the the outside tanks not affected tank(s).

within limits.

AND A.2 Reduce affected tank 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months contents to within limits.

Quad Cities 1 and 2 3.7.d-1 Revision 0

TRM Liquid Holdup Tanks 3.7.d SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.d.1 ------------------------------NOTE-------------------------------

Not required to be performed for 7 days if when tank(s) is empty at the start of addition.

Determine the quantity of radioactive material of each 7 days when outside tank is within limits by analyzing a radioactive representative sample of the tanks contents. materials are being added to the tank(s)

AND Once within 7 days after each completion of radioactive material to the tank Quad Cities 1 and 2 3.7.d-2 Revision 0

TRM Explosive Gas Mixture 3.7.e 3.7 PLANT SYSTEMS 3.7.e Explosive Gas Mixture TLCO 3.7.e The concentration of hydrogen in the Offgas Holdup System shall be < 4%

by volume.

APPLICABILITY: During Offgas Holdup System operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Hydrogen concentration A.1 Restore concentration to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months in the Offgas Holdup within limit.

System > 4% by volume.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.e.1 Verify hydrogen concentration in the Offgas Holdup 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months System is < 4% by volume.

Quad Cities 1 and 2 3.7.e-1 Revision 0

TRM Flood Protection 3.7.f 3.7 PLANT SYSTEMS 3.7.f Flood Protection TLCO 3.7.f Flood protection shall be available for all required safe shutdown systems, components, and structures.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Water level > 586 ft mean A.1 Initiate applicable flood Immediately sea level USGS datum. protection measures.

B. Water level > 594 ft mean B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months sea level USGS datum.

AND OR B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Water level predicted to be > 594 ft mean sea level USGS datum in < 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Quad Cities 1 and 2 3.7.f-1 Revision 0

TRM Flood Protection 3.7.f SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.f.1 -----------------------------NOTE--------------------------------

Not required to be performed if water level is < 585.5 ft mean sea level USGS datum.

Determine water level at the plant intake bay. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months TSR 3.7.f.2 Determine water level at the plant intake bay. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Quad Cities 1 and 2 3.7.f-2 Revision 0

TRM Sealed Source Contamination 3.7.g 3.7 PLANT SYSTEMS 3.7.g Sealed Source Contamination TLCO 3.7.g Each sealed source containing radioactive material either in excess of 100 Ci of beta and/or gamma emitting material or 5 Ci of alpha emitting material shall be free of 0.005 Ci of removable contamination.

APPLICABILITY: At all times.

ACTIONS

NOTE------------------------------------------------------

Separate Condition entry is allowed for each source.

CONDITION REQUIRED ACTION COMPLETION TIME A. -------------NOTE------------- A.1 Withdraw the sealed Immediately Required Actions A.2 and source from use.

A.3 shall be completed whenever Condition A is AND entered.

A.2.1 Initiate action to Immediately decontaminate and repair One or more sealed the sealed source.

sources with removable contamination not within OR limits.

(continued)

Quad Cities 1 and 2 3.7.g-1 Revision 0

TRM Sealed Source Contamination 3.7.g ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Initiate action to dispose Immediately of the sealed source in accordance with NRC Regulations.

AND A.3 Initiate a corrective action Immediately program report.

Quad Cities 1 and 2 3.7.g-2 Revision 0

TRM Sealed Source Contamination 3.7.g SURVEILLANCE REQUIREMENTS

NOTES-------------------------------------------------------

1. Each sealed source shall be tested for leakage and/or contamination by the licensee, or other persons specifically authorized by the Commission or Agreement State.

2. The test method shall have a detection sensitivity of at least 0.005 Ci per test sample.

3. Startup sources and fission detectors previously subjected to core flux are exempted from the TSRs.

4. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

SURVEILLANCE FREQUENCY TSR 3.7.g.1 -----------------------------NOTE----------------------------

Only required to be performed on sources in use.

Perform leakage testing for all sealed sources 184 days containing radioactive materials with a half-life > 30 days (excluding Hydrogen 3) and in any form other than gas.

TSR 3.7.g.2 --------------------------NOTES----------------------------------

1. Only required to be performed on stored sources not in use.

2. Only required to be performed if not tested within the previous 6 months.

Perform leakage testing for each sealed source and Prior to use or fission detector. transfer to another licensee (continued)

Quad Cities 1 and 2 3.7.g-3 Revision 0

TRM Sealed Source Contamination 3.7.g SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.7.g.3 --------------------------------NOTE-------------------------------

Only required to be performed on stored sources not in use.

Perform leakage testing on sealed sources and fission Prior to use detectors transferred without a certificate indicating the last test date.

TSR 3.7.g.4 ------------------------------NOTE---------------------------------

Only required to be performed on sealed startup sources and fission detectors not previously subjected to core flux.

Perform leakage testing for each sealed startup Once within 31 source and fission detector. days prior to being subjected to core flux or installed in the core or following repair or maintenance to sources Quad Cities 1 and 2 3.7.g-4 Revision 0

TRM Snubbers 3.7.h 3.7 PLANT SYSTEMS 3.7.h Snubbers

NOTE-----------------------------------------

Superseded by Technical Specification Limiting Condition for Operation (LCO) 3.0.8 and Technical Requirement Program 5.5.15, Augmented Inservice Inspection Program.

Quad Cities 1 and 2 3.7.h-1 Revision QC-TRM-18-006

TRM Communications 3.9.a 3.9 REFUELING OPERATIONS 3.9.a Communications TLCO 3.9.a Direct communications shall be maintained between the control room and refueling platform personnel.

APPLICABILITY: During CORE ALTERATIONS, except movement of control rods with their normal drive system.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Direct communications A.1 Suspend CORE Immediately not maintained. ALTERATIONS.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY TSR 3.9.a.1 Demonstrate direct communications between the control Once within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months room and refueling platform personnel. prior to the start of CORE ALTERATIONS AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Quad Cities 1 and 2 3.9.a-1 Revision 0

TRM Programs and Manuals 5.0.a 5.0 ADMINISTRATIVE CONTROLS 5.5.1 Offsite Dose Calculation Manual Technical Specification 5.5.1, Offsite Dose Calculation Manual, is implemented by the Quad Cities Offsite Dose Calculation Manual.

5.5.2 Primary Coolant Sources Outside Containment Technical Specification 5.5.2, Primary Coolant Sources Outside Containment, requires controls be provided to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The program is implemented by the following procedures:

QCTP 0820-08, and QCOS 7500-05.

5.5.3 [Deleted]

Quad Cities 1 and 2 5.0.a-1 Revision QC-TRM-03-004

TRM Programs and Manuals 5.0.a 5.0 ADMINISTRATIVE CONTROLS 5.5.4 Radioactive Effluent Controls Program Technical Specification 5.5.4, Radioactive Effluent Controls Program, requires controls be established to conform with 10 CFR 50.36a for control of radioactive effluents and for maintaining doses to members of the public from radioactive effluents as low as reasonably achievable. This program is implemented through Sections 12.2, 12.3, 12.4, and 12.5 of the Quad Cities Station Offsite Dose Calculation Manual.

5.5.5 Component Cyclic or Transient Limit Program Technical Specification 5.5.5, Component Cyclic or Transient Limit Program, requires controls be provided to track the UFSAR, Table 3.9-1, cyclic and transient occurrences to ensure that components are maintained within design limits. The program is implemented by ER-AA-470.

5.5.6 Inservice Testing Program The INSERVICE TESTING PROGRAM requires controls be established for inservice testing of ASME Code Class 1, 2, and 3, pumps and valves. This program is implemented by the following:

IST-QDC-PLAN and the applicable procedures that implement the ASME Code for Operation and Maintenance of Nuclear Power Plants (i.e., the OM Code) requirements.

5.5.7 Ventilation Filter Testing Program (VFTP)

Technical Specification 5.5.7, Ventilation Filter Testing Program (VFTP),

requires testing of the Engineered Safety Feature filter ventilation systems for the following Technical Specification systems:

Control Room Emergency Ventilation System and Standby Gas Treatment System.

The program is implemented by QCIS 5700-04, QCIS 7500-01, QCMPM 7500-01, QCMPM 9400-01, QCMPM 9400-02, QCTS 0810-08, QCOS 7500-07, QCOS 7500-05, QCOS 5750-11.

In addition, laboratory analysis required by Technical Specification 5.5.7.c must be completed within 31 days after removal of a representative sample.

Quad Cities 1 and 2 5.0.a-2 Revision QC-TRM-17-005

TRM Programs and Manuals 5.0.a 5.0 ADMINISTRATIVE CONTROLS 5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program Explosive Gas Monitoring:

Technical Specification 5.5.8, Explosive Gas and Storage Tank Radioactivity Monitoring Program, requires controls be provided for potentially explosive gas mixtures contained in the Off-gas System and the quantity of radioactivity contained in the unprotected outdoor storage tanks. The program is implemented by TRM Specification 3.3.c, Explosive Gas Monitoring Instrumentation, TRM Specification 3.7.d, Liquid Holdup Tanks, TRM Specification 3.7.e, Explosive Gas Mixtures, and procedures QCOP 2700-07, QCIS 5400-03, QOS 0005-01, CY-QC-120-600, QCIS 5400-04, QCIS 5400-05, QCIS 5400-06, CY-QC-110-601.

Storage Tank Radioactivity Monitoring:

CY-AB-120-200 5.5.9 Diesel Fuel Oil Testing Program Technical Specification 5.5.9, Diesel Fuel Oil Testing Program, requires testing requirements be provided for new fuel oil and stored fuel oil and includes sampling requirements and acceptance criteria. The program is implemented by the following procedures:

CY-QC-110-630 and CY-QC-130-700.

5.5.10 Technical Specification Bases Control Program Technical Specification 5.5.10, Technical Specification Bases Control Program, requires means be provided for processing changes to the Bases of the Technical Specifications. The program is implemented by Appendix D of the Technical Requirements Manual.

5.5.11 Safety Function Determination Program Technical Specification 5.5.11, Safety Function Determination Program, requires means be provided to ensure a loss of function is detected and appropriate actions taken. The program is implemented by Appendix C of the Technical Requirements Manual.

Quad Cities 1 and 2 5.0.a-3 Revision QC-TRM-17-005

TRM Programs and Manuals 5.0.a 5.0 ADMINISTRATIVE CONTROLS 5.5.12 Primary Containment Leakage Rate Testing Program Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program, requires implementation of leakage rate testing of the primary containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B as modified by approved exemptions. This program shall be in accordance with the guidelines contained in NEI 94-01, Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J, Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A, dated October 2008. The program is implemented by ER-AA-380, QCTP 0130-01 and QCTS 0500-01.

5.5.13 Control Room Envelope Habitability Program Technical Specification 5.5.13, Control Room Envelope Habitability Program, requires implementation of a program to ensure that the Control Room Envelope (CRE) habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposure in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program is implemented by the following procedures:

ER-QC-390, ER-QC-390-1001, and QCTP 0440-07.

5.5.14 Surveillance Frequency Control Program (SFCP)

The SFCP ensures that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation (LCOs) are met. The provisions of Technical Specifications Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the SFCP. The SFCP program document is located in a SFCP folder in the TS records program.

5.5.15 Augmented Inservice Inspection Program Examination and testing of safety related snubbers shall be performed in accordance with the 10CFR50.55a approved edition of the ASME OMa Code, Subsection ISTD as denoted in the current revision of the Inservice Inspection Program Plan.

Quad Cities 1 and 2 5.0.a-4 Revision QC-TRM-21-006

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TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 1 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-007A 0203-1A Main steam line AO Valve Inside Open 3dTd5 X-007A 0203-2A Main steam line AO Valve Outside Open 3dTd5 X-007A 0220-10A Main steam line - pressure test inboard stop Manual Outside Closed NA tap between 0203-1A & 2A X-007B 0203-1B Main steam line AO Valve Inside Open 3dTd5 X-007B 0203-2B Main steam line AO Valve Outside Open 3dTd5 X-007B 0220-10B Main steam line - pressure test inboard stop Manual Outside Closed NA tap between 0203-1B & 2B X-007C 0203-1C Main steam line AO Valve Inside Open 3dTd5 X-007C 0203-2C Main steam line AO Valve Outside Open 3dTd5 X-007C 0220-10C Main steam line - pressure test inboard stop Manual Outside Closed NA tap between 0203-1C & 2C X-007D 0203-1D Main steam line AO Valve Inside Open 3dTd5 X-007D 0203-2D Main steam line AO Valve Outside Open 3dTd5 X-007D 0220-10D Main steam line - pressure test inboard stop Manual Outside Closed NA tap between 0203-1D & 2D X-008 0220-1 Main steam line drain MO Valve Inside Closed 35 X-008 0220-2 Main steam line drain MO Valve Outside Closed 35 X-008 0220-5 Main steam line drain - pressure test inbd stop Manual Outside Closed NA tap between 0220-1 & 2 X-009A 0220-62A From reactor feedwater Check Outside Open NA X-009A 0220-58A From reactor feedwater Check Inside Open NA X-009A 0220-86A From Rx FW - local pressure test inboard stop Manual Outside Closed NA tap between 0220-58A & 62A X-009A 3299-130 From Rx FW - LLRT inboard valve Manual Inside Closed NA tap between 0220-58A & 62A X-009A 220-115A From Rx FW - inboard drain valve Manual Inside Closed NA tap between 0220-58A & Rx X-009A 3299-128 From Rx FW - inboard vent valve Manual Inside Closed NA tap between 0220-58A & Rx X-009B 0220-62B From reactor feedwater Check Outside Open NA X-009B 0220-58B From reactor feedwater Check Inside Open NA X-009B 0220-86B From Rx FW - local pressure test inboard stop Manual Outside Closed NA tap between 0220-58B & 62B X-009B 3299-124 From Rx FW - LLRT inboard valve Manual Inside Closed NA tap between 0220-58B & 62B X-009B 0220-115B From Rx FW - inboard drain valve Manual Inside Closed NA tap between 0220-58B & Rx X-009B 3299-122 From Rx FW - inboard vent valve Manual Inside Closed NA tap between 0220-58B & Rx Quad Cities Unit 1 and 2 A2-1 Revision QC-TRM-09-005

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 2 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-010 1301-16 RCIC turbine steam supply MO Valve Inside Open 25 X-010 1301-17 RCIC turbine steam supply MO Valve Outside Open 25 X-010 1301-18A RCIC turbine steam supply - pressure test inboard stop Manual Outside Closed NA tap between 1301-16 & 17 X-011 2301-4 HPCI turbine steam MO Valve Inside Open 50 X-011 2301-5 HPCI turbine steam MO Valve Outside Open 63 X-011 2301-16 HPCI turbine steam - pressure test inbd stop Manual Outside Closed NA tap between X-11 & 2301-5 X-012 1001-47 RHR reactor shutdown cooling supply MO Valve Outside Closed 40 X-012 1001-50 RHR reactor shutdown cooling supply MO Valve Inside Closed 40 X-012 1099-178 shutdown cooling supply-inboard vent Manual Inside Closed NA tap between 1001-50 & 47 X-012 1001-48 shutdown cooling supply - press test inbd stop Manual Outside Closed NA tap between 1001-50 & 47 X-012 1001-156A shutdown cooling supply - inboard vent Manual Outside Closed NA tap between 1001-50 & 47 X-012 1001-156D shutdown cooling supply - inboard vent Manual Outside Closed NA tap between 1001-50 & 47 X-013A 1001-29A RHR reactor LPCI / shutdown cooling injection MO Valve Outside Closed NA X-013A 1001-28A RHR reactor LPCI / shutdown cooling injection MO Valve Outside Open NA X-013A 1001-68A RHR reactor LPCI / shutdown cooling injection AO Check Inside Closed NA X-013A 1001-30A 'A' LPCI loop - pressure test inboard stop Manual Outside Closed NA tap between 1001-29A & 68A X-013B 1001-29B RHR reactor LPCI / shutdown cooling injection MO Valve Outside Closed NA X-013B 1001-28B RHR reactor LPCI / shutdown cooling injection MO Valve Outside Open NA X-013B 1001-68B RHR reactor LPCI / shutdown cooling injection AO Check Inside Closed NA X-013B 1001-31B 'B' LPCI / SDC loop - press test inboard stop Manual Outside Closed NA tap between 1001-29B & 68B X-014 1201-2 Reactor water cleanup supply MO Valve Inside Open 30 X-014 1201-5 Reactor water cleanup supply MO Valve Outside Open 38 X-014 RV-1299-87 Reactor water cleanup supply Relief Inside Closed NA X-014 1201-121 RWCU supply - pressure test inboard stop Manual Outside Closed NA tap between 1201-2 & 5 X-016A 1402-24A Core spray to reactor MO Valve Outside Open NA X-016A 1402-25A Core spray to reactor MO Valve Outside Closed NA X-016A 1402-9A Core spray to reactor Check Inside Closed NA X-016A 1402-5A Core Spray to Rx - pump dsch press test inbd stop Manual Outside Closed NA tap between 1402-24A & 25A Quad Cities Unit 1 and 2 A2-2 Revision QC-TRM-09-005

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 3 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-016A 1499-51 Core Spray to Rx-inboard vent Manual Outside Closed NA tap between 1402-24A & 25A X-016A 1402-33A Core Spray to Rx - pump dsch press test inbd stop Manual Outside Closed NA tap between 1402-25A & 9A X-016B 1402-24B Core spray to reactor MO Valve Outside Open NA X-016B 1402-25B Core spray to reactor MO Valve Outside Closed NA X-016B 1402-9B Core spray to reactor Check Inside Closed NA X-016B 1402-5B Core Spray to Rx - pump dsch press test inbd stop Manual Outside Closed NA tap between 1402-24B & 25B X-016B 1402-33B Core Spray to Rx - pump dsch press test inbd stop Manual Outside Closed NA tap between 1402-25B & 9B X-018 2001-3 Drywell floor drain discharge AO Valve Outside Closed 20 X-018 2001-4 Drywell floor drain discharge AO Valve Outside Closed 20 X-018 2099-394 DW floor drain discharge - press test inbd stop Manual Outside Closed NA tap between 2001-3 & 4 X-019 2001-15 Drywell equipment drain discharge AO Valve Outside Closed 20 X-019 2001-16 Drywell equipment drain discharge AO Valve Outside Closed 20 X-019 2099-500 DW equip drain discharge - press test inbd stop Manual Outside Closed NA tap between 2001-15 & 16 X-020 4399-45 Clean demineralizer water in Manual Outside Closed NA X-020 4399-46 Clean demineralizer water in Check Outside Closed NA X-020 4399-347 Clean demin water in - pressure test inbd stop Manual Outside Closed NA tap between 4399-46 & X-20 X-020 4399-349 Clean demin water in - pressure test inbd stop Manual Outside Closed NA tap between 4399-45 & 46 X-021 4699-47 Service air to drywell Check Outside Closed NA X-021 4699-46 Service air to drywell Manual Outside Closed NA X-021 4699-314 Service air to drywell - press test inbd stop Manual Outside Closed NA tap between 4699-46 & 47 X-022 4799-155 Instrument air to drywell Check Inside Open NA X-022 4799-156 Instrument air to drywell Check Outside Open NA X-022 4799-157 Instrument air to drywell Manual Outside Open NA X-022 4799-518 Inst. air to drywell - local drop shutoff valve Manual Outside Closed NA tap between 4799-155 & 156 X-023 3799-31 Rx building closed cooling water supply Check Inside Open NA X-023 3702 Rx building closed cooling water supply MO Valve Outside Open NA X-023 3799-136 RBCCW supply - press test inbd stop Manual Outside Closed NA tap between 3799-31 & 3702 X-024 3703 Rx building closed cooling water return MO Valve Outside Open NA Quad Cities Unit 1 and 2 A2-3 Revision QC-TRM-09-005

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 4 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-024 3706 Rx building closed cooling water return MO Valve Inside Open NA X-024 3799-138 RBCCW return - press test inbd stop Manual Outside Closed NA tap between 3703 & 3706 X-025 1601-23 Drywell main exhaust AO Valve Outside Closed 10 X-025 1601-62 Drywell main exhaust valve bypass (vent relief) AO Valve Outside Closed 15 X-025 1601-24 Main primary containment vent to Rx building exh AO Valve Outside Closed 10 X-025 1601-63 Primary Containment exhaust to SBGT system AO Valve Outside Closed 10 X-025 1601-72 Drywell main exh. / Main primary containment vent to Manual Outside Closed NA tap between 1601-23 & 24 Rx bldg exh - press test inbd stop X-025 2599-64 ACAD to SBGT - DW PT 1641-12 test tap stop Manual Outside Closed NA tap between X-25 & 2599-4A/B X-025 1699-98 Hardened Containment Vent System (HCVS) Inlet AO Valve Outside Closed NA Can only be opened using HCVS nitrogen supply - spring closed X-026 1601-55 Drywell nitrogen purge inlet AO Valve Outside Open 10 X-026 1601-21 Drywell purge inlet AO Valve Outside Closed 10 X-026 1601-22 Drywell purge inlet AO Valve Outside Closed 10 X-026 1601-74 Drywell purge inlet - press test inbd stop Manual Outside Closed NA tap between 1601-21 & 22 X-026 RV-8799-214 Nitrogen makeup Relief Outside Closed NA X-026 1601-57 Nitrogen makeup MO Valve Outside Open 15 X-026 1601-59 Nitrogen makeup to Drywell AO Valve Outside Open 15 X-026 8803 Oxygen analyzer return AO Valve Outside Open 10 X-026 8804 Oxygen analyzer return AO Valve Outside Open 10 X-026 1601-77 Oxygen analyzer return - DW air sample system Manual Outside Closed NA tap between X-26 & 8804 / 1601-21 pressure test stop X-027C PT 2-1624 test tap Drywell pressure NA Outside Cap NA Installed X-027C PT 2-1625 test tap Drywell pressure NA Outside Cap NA Installed X-027C DPT 2-1641-51 Drywell to Suppression Chamber differential pressure NA Outside Cap NA low side sensing line from X-205 high side test tap Installed X-030E 0220-176A 'A' RR Pmp DPT 0261-5A & DPIS 0261-35A,C,E,G low Manual Outside Closed NA tap between X-30E & 0220-13A inboard vent Quad Cities Unit 1 and 2 A2-4 Revision QC-TRM-20-010

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 5 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-030F 0220-174A 'A' RR Pmp DPT 0261-5A & DPIS 0261-35A,C,E,G high Manual Outside Closed NA tap between X-30F & 0220-14A inboard vent X-031E 0220-176B 'B' RR Pmp DPT 0261-5B & DPIS 0261-35B,D,F,H low Manual Outside Closed NA tap between X-31E & 0220-13B inboard vent X-031F 0220-174B 'B' RR Pmp DPT 0261-5B & DPIS 0261-35B,D,F,H high Manual Outside Closed NA tap between X-31F & 0220-14B inboard vent X-032 4720 Drywell pneumatic suction X-32D AO Valve Outside Open 10 X-032 4721 Drywell pneumatic suction X-32D AO Valve Outside Open 10 X-033 2499-1A CAM/drywell (position E) SO Valve Outside Closed NA X-033 2499-2A CAM/drywell (position E) SO Valve Outside Closed NA X-033 2499-7A CAM/drywell (pos. E) - press test inbd stop Manual Outside Closed NA tap between 2499-1A & 2A X-033 2499-22A CAM return (position D) Check Outside Closed NA X-033 2499-25A CAM return (pos. D) - smpl outlet press test inbd stop Manual Outside Closed NA tap between X-033 & 2499-22A X-035A 0743 Traversing in-core probe purge Check Outside Closed NA X-035B 0737-1C Traversing in-core probe SO Valve Outside Closed NA X-035B 0737-2C Traversing in-core probe Shear Outside Open NA X-035C 0737-1B Traversing in-core probe SO Valve Outside Closed NA X-035C 0737-2B Traversing in-core probe Shear Outside Open NA X-035D 0737-1D Traversing in-core probe SO Valve Outside Closed NA X-035D 0737-2D Traversing in-core probe Shear Outside Open NA X-035E 0737-1F Traversing in-core probe SO Valve Outside Closed NA X-035E 0737-2F Traversing in-core probe Shear Outside Open NA X-035F 0737-1E Traversing in-core probe SO Valve Outside Closed NA X-035F 0737-2E Traversing in-core probe Shear Outside Open NA X-037 2499-22B CAM return (pos. C) Check Outside Closed NA X-037 2499-25B CAM return (pos. C) - smpl outlet pressure test inboard Manual Outside Closed NA tap between X-037 & 2499-22B stop Quad Cities Unit 1 and 2 A2-5 Revision QC-TRM-20-010

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 6 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-039A 1001-26A RHR - containment spray MO Valve Outside Closed NA X-039A 1001-23A RHR - containment spray MO Valve Outside Closed NA X-039A 1001-197 RHR containment spray - pressure test stop Manual Outside Closed NA tap between 1001-26A & 23A X-039A 1099-166 RHR - containment spray Manual Outside Closed NA tap between 1001-26A & 23A X-039A 1001-26A bonnet RHR - containment spray NA Outside Cap NA bonnet test tap cap for 1001-26A test tap Installed X-039A 1001-25A 'A' Containment Spray - loop inboard drain Manual Outside Closed NA tap between 1001-23A & 26A X-039B 1001-26B RHR - containment spray MO Valve Outside Closed NA X-039B 1001-23B RHR - containment spray MO Valve Outside Closed NA X-039B 1001-26B bonnet RHR - containment spray NA Outside Cap NA bonnet test tap cap for 1001-26B test tap Installed X-039B 1001-25B 'B' Containment Spray - loop inboard drain Manual Outside Closed NA tap between 1001-23B & 26B X-039B 1001-196 'B' Containment Spray - loop pressure test Manual Outside Closed NA tap between 1001-23B & 26B X-039B Blind Flange RHR DW spray blind flange NA Outside Installed NA between 1001-23B & 26B X-041 0220-44 Reactor water sample AO Valve Inside Open 5 X-041 0220-45 Reactor water sample AO Valve Outside Open 5 X-041 0220-43 Reactor water sample - press test inbd stop Manual Outside Closed NA tap between 0220-44 & 45 X-043 8800-02B Particulate sample lines (line B) Manual Outside Closed NA X-043 8800-03B Particulate sample lines (line B) Manual Outside Closed NA X-043 8800-02C Particulate sample lines (line C) Manual Outside Closed NA X-043 8800-03C Particulate sample lines (line C) Manual Outside Closed NA X-043 8800-02D Particulate sample lines (line D) Manual Outside Closed NA X-043 8800-03D Particulate sample lines (line D) Manual Outside Closed NA X-043 8800-02E Particulate sample lines (line E) Manual Outside Closed NA X-043 8800-03E Particulate sample lines (line E) Manual Outside Closed NA X-043 8800-02F Particulate sample lines (line F) Manual Outside Closed NA X-043 8800-03F Particulate sample lines (line F) Manual Outside Closed NA X-043 8800-02G Particulate sample lines (line G) Manual Outside Closed NA X-043 8800-03G Particulate sample lines (line G) Manual Outside Closed NA Quad Cities Unit 1 and 2 A2-6 Revision QC-TRM-09-005

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 7 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-043 8800-02H Particulate sample lines (line H) Manual Outside Closed NA X-043 8800-03H Particulate sample lines (line H) Manual Outside Closed NA X-043 8800-02I Particulate sample lines (line I) Manual Outside Closed NA X-043 8800-03I Particulate sample lines (line I) Manual Outside Closed NA X-043 8800-02J Particulate sample lines (line J) Manual Outside Closed NA X-043 8800-03J Particulate sample lines (line J) Manual Outside Closed NA X-043 8800-02K Particulate sample lines (line K) Manual Outside Closed NA X-043 8800-03K Particulate sample lines (line K) Manual Outside Closed NA X-043 8800-02L Particulate sample lines (line L) Manual Outside Closed NA X-043 8800-03L Particulate sample lines (line L) Manual Outside Closed NA X-043 8800-02M Particulate sample lines (line M) Manual Outside Closed NA X-043 8800-03M Particulate sample lines (line M) Manual Outside Closed NA X-043 8800-02N Particulate sample lines (line N) Manual Outside Closed NA X-043 8800-03N Particulate sample lines (line N) Manual Outside Closed NA X-043 8800-02O Particulate sample lines (line O) Manual Outside Closed NA X-043 8800-03O Particulate sample lines (line O) Manual Outside Closed NA X-043 8800-02P Particulate sample lines (line P) Manual Outside Closed NA X-043 8800-03P Particulate sample lines (line P) Manual Outside Closed NA X-043 8800-02Q Particulate sample lines (line Q) Manual Outside Closed NA X-043 8800-03Q Particulate sample lines (line Q) Manual Outside Closed NA X-043 8800-02R Particulate sample lines (line R) Manual Outside Closed NA X-043 8800-03R Particulate sample lines (line R) Manual Outside Closed NA X-043 8800-02S Particulate sample lines (line S) Manual Outside Closed NA X-043 8800-03S Particulate sample lines (line S) Manual Outside Closed NA X-043 8800-02T Particulate sample lines (line T) Manual Outside Closed NA X-043 8800-03T Particulate sample lines (line T) Manual Outside Closed NA X-043 8800-02U Particulate sample lines (line U) Manual Outside Closed NA X-043 8800-03U Particulate sample lines (line U) Manual Outside Closed NA Quad Cities Unit 1 and 2 A2-7 Revision QC-TRM-09-005

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 8 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-043 8800-02V Particulate sample lines (line V) Manual Outside Closed NA X-043 8800-03V Particulate sample lines (line V) Manual Outside Closed NA X-043 8801A Drywell oxygen analyzer sample (line A) AO Valve Outside Open 10 X-043 8802A Drywell oxygen analyzer sample (line A) AO Valve Outside Open 10 X-043 8801B Drywell oxygen analyzer sample (line B) AO Valve Outside Open 10 X-043 8802B Drywell oxygen analyzer sample (line B) AO Valve Outside Open 10 X-043 8801C Drywell oxygen analyzer sample (line C) AO Valve Outside Open 10 X-043 8802C Drywell oxygen analyzer sample (line C) AO Valve Outside Open 10 X-044 4799-176 HVAC instrument penetration Manual Outside Closed NA capped line X-044 4799-479A HVAC instrument penetration (line A) Manual Outside Closed NA capped line X-044 4799-479B HVAC instrument penetration (line B) Manual Outside Closed NA capped line X-044 4799-479C HVAC instrument penetration (line C) Manual Outside Closed NA capped line X-044 4799-479D HVAC instrument penetration (line D) Manual Outside Closed NA capped line X-044 4799-479E HVAC instrument penetration (line E) Manual Outside Closed NA capped line X-044 4799-479F HVAC instrument penetration (line F) Manual Outside Closed NA capped line X-044 4799-479G HVAC instrument penetration (line G) Manual Outside Closed NA capped line X-044 4799-479H HVAC instrument penetration (line H) Manual Outside Closed NA capped line X-044 4799-479J HVAC instrument penetration (line J) Manual Outside Closed NA capped line X-044 4799-479K HVAC instrument penetration (line K) Manual Outside Closed NA capped line X-044 4799-479L HVAC instrument penetration (line L) Manual Outside Closed NA capped line X-044 4799-479M HVAC instrument penetration (line M) Manual Outside Closed NA capped line X-044 4799-479N HVAC instrument penetration (line N) Manual Outside Closed NA capped line X-044 4799-479P HVAC instrument penetration (line P) Manual Outside Closed NA capped line X-044 4799-479Q HVAC instrument penetration (line Q) Manual Outside Closed NA capped line X-044 4799-479R HVAC instrument penetration (line R) Manual Outside Closed NA capped line X-044 4799-479S HVAC instrument penetration (line S) Manual Outside Closed NA capped line X-044 4799-479T HVAC instrument penetration (line T) Manual Outside Closed NA capped line X-044 4799-479U HVAC instrument penetration (line U) Manual Outside Closed NA capped line Quad Cities Unit 1 and 2 A2-8 Revision QC-TRM-09-005

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 9 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-044 4799-479V HVAC instrument penetration (line V) Manual Outside Closed NA capped line X-044 4799-479W HVAC instrument penetration (line W) Manual Outside Closed NA capped line X-044 4799-479X HVAC instrument penetration (line X) Manual Outside Closed NA capped line X-044 4799-479Y HVAC instrument penetration (line Y) Manual Outside Closed NA capped line X-044 4799-479Z HVAC instrument penetration (line Z) Manual Outside Closed NA capped line X-047 1101-16 Standby liquid control Check Outside Closed NA X-047 1101-15 Standby liquid control Check Inside Closed NA X-047 1101-34 SBLC - injection line pressure tap inboard stop Manual Outside Closed NA tap between 1101-15 & 16 X-100D 2499-1B CAM/drywell (position F) SO Valve Outside Closed NA X-100D 2499-2B CAM/drywell (position F) SO Valve Outside Closed NA X-100D 2499-7B CAM/drywell (pos. F) - press test inbd stop Manual Outside Closed NA tap between 2499-1B & 2B X-100D 4799-353 SRM/IRM purge Check Outside Closed NA X-100D 4799-354 SRM/IRM purge Check Outside Closed NA X-100D 4799-480A Instrumentation Lines (line A) Manual Outside Closed NA capped line X-100D 4799-480B Instrumentation Lines (line B) Manual Outside Closed NA capped line X-100D 4799-480C Instrumentation Lines (line C) Manual Outside Closed NA capped line X-104E 4799-477A Instrumentation Lines (line A) Manual Outside Closed NA capped line X-104E 4799-477B Instrumentation Lines (line B) Manual Outside Closed NA capped line X-104E 4799-477C Instrumentation Lines (line C) Manual Outside Closed NA capped line X-104E 4799-477D Instrumentation Lines (line D) Manual Outside Closed NA capped line X-104E 4799-477E Instrumentation Lines (line E) Manual Outside Closed NA capped line X-104E 4799-477F Instrumentation Lines (line F) Manual Outside Closed NA capped line X-104E 4799-477G Instrumentation Lines (line G) Manual Outside Closed NA capped line X-108 0263-944A RVLIS Backfill (line 2-2334A) Check Outside Open NA X-108 0263-945A RVLIS Backfill (line 2-2334A) Check Outside Open NA X-108 0263-947A RVLIS Backfill (line 2-2335A) Check Outside Open NA X-108 0263-948A RVLIS Backfill (line 2-2335A) Check Outside Open NA X-108 0263-960A RVLIS Backfill - test valve Manual Outside Closed NA tap between 0263-944A & X-108 Quad Cities Unit 1 and 2 A2-9 Revision QC-TRM-09-005

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 10 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-108 0263-958A RVLIS Backfill - vent valve Manual Outside Closed NA tap between 0263-944A & X-108 X-108 0263-955A RVLIS Backfill - test valve Manual Outside Closed NA tap between 0263-947A & X-108 X-108 0263-953A RVLIS Backfill - vent valve Manual Outside Closed NA tap between 0263-947A & X-108 X-109 0263-944B RVLIS Backfill (line 2-2334B) Check Outside Open NA X-109 0263-945B RVLIS Backfill (line 2-2334B) Check Outside Open NA X-109 0263-947B RVLIS Backfill (line 2-2335B) Check Outside Open NA X-109 0263-948B RVLIS Backfill (line 2-2335B) Check Outside Open NA X-109 0263-960B RVLIS Backfill - test valve Manual Outside Closed NA tap between 0263-944B & X-109 X-109 0263-958B RVLIS Backfill - vent valve Manual Outside Closed NA tap between 0263-944B & X-109 X-109 0263-955B RVLIS Backfill - test valve Manual Outside Closed NA tap between 0263-947B & X-109 X-109 0263-953B RVLIS Backfill - vent valve Manual Outside Closed NA tap between 0263-947B & X-109 X-203A 1601-60 Suppression chamber main exhaust AO Valve Outside Closed 10 X-203A 1601-61 Suppression chamber main exhaust valve bypass AO Valve Outside Closed 15 X-203A 1601-24 Main primary containment vent to Rx building exh AO Valve Outside Closed 10 X-203A 1601-63 Primary Containment exhaust to SBGT system AO Valve Outside Closed 10 X-203A 1601-72 Suppression chamber main exhaust / Main primary Manual Outside Closed NA tap between 1601-60/61 & 24 containment vent to Rx bldg exh - pressure test inboard stop X-203A 1699-98 Hardened Containment Vent System (HCVS) Inlet AO Valve Outside Closed NA Can only be opened using HCVS nitrogen supply - spring closed X-205 1601-20A Vacuum breaker secondary containment to suppression AO Valve Outside Closed NA chamber X-205 1601-31A Vacuum breaker secondary containment to suppression Check Outside Closed NA chamber X-205 1601-73A Vac. breaker secondary containment to suppression Manual Outside Closed NA tap between 1601-20A & 31A chamber - pressure test inbd stop X-205 1601-20B Vacuum breaker secondary containment to suppression AO Valve Outside Closed NA chamber X-205 1601-31B Vacuum breaker secondary containment to suppression Check Outside Closed NA chamber Quad Cities Unit 1 and 2 A2-10 Revision QC-TRM-16-003

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 11 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-205 1601-73B Vac. breaker secondary containment to suppression Manual Outside Closed NA tap between 1601-20B & 31B chamber - pressure test inbd stop X-205 1601-56 Suppression chamber purge inlet AO Valve Outside Open 10 X-205 1601-58 Nitrogen makeup to suppression chamber AO Valve Outside Closed 15 X-205 1601-91B Suppression chamber LT 1641-5B low side vent Manual Outside Closed NA X-205 DPT 2-1641-51 low Drywell to Suppression Chamber differential pressure NA Outside Cap NA hi side sensing line from X-027C side test tap Installed X-205 DPT 2-1622A test Suppression Chamber to Reactor Building differential NA Outside Cap NA tap pressure Installed X-205 DPT 2-1622B test Suppression Chamber to Reactor Building differential NA Outside Cap NA tap pressure Installed X-205 PT 2-1623 test tap Suppression Chamber pressure NA Outside Cap NA Installed X-206A 1601-100 Suppression chamber LG 1602-10 upper shutoff Manual Outside Closed NA X-206A 1699-17 Suppression chamber LT 2-1626 upper shutoff Manual Outside Closed NA X-206A 1699-42 Suppression Chamber level indicator drain pot drain valve Manual Outside Closed NA X-206A PT 2-1602-8 test Suppression Chamber pressure NA Outside Cap NA tap Installed X-206A LT 2-1602-9 low Suppression Chamber level NA Outside Cap NA side test tap Installed X-206B 1699-16 Suppression chamber level instrumentation drain Manual Outside Closed NA X-206B 1601-101 Suppression chamber LG 1602-10 lower shutoff Manual Outside Closed NA X-206B 1699-15 Suppression chamber LT 2-1626 lower shutoff Manual Outside Closed NA X-206B 1699-19 Suppression chamber water reservoir fill tap Manual Outside Closed NA X-206B LT 2-1602-9 high Suppression Chamber level NA Outside Cap NA side test tap Installed X-206C 2399-35 Suppression chamber LS 2351A & B high side drain Manual Outside Closed NA X-206C 2399-38A Suppression chamber LS 2351A drain Manual Outside Closed NA X-206C 2399-38B Suppression chamber LS 2351B drain Manual Outside Closed NA X-210A 1402-4A Core spray test to suppression pool MO Valve Outside Closed NA X-210A 1402-4B Core spray test to suppression pool MO Valve Outside Closed NA Quad Cities Unit 1 and 2 A2-11 Revision QC-TRM-16-003

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 12 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-210A 1001-36A RHR test line to suppression pool MO Valve Outside Closed NA X-210A 1001-18A RHR min flow bypass MO Valve Outside Open NA X-210B 2301-14 HPCI min flow bypass MO Valve Outside Closed NA X-210B 1301-47 RCIC min flow bypass Check Outside Closed NA X-210B 1402-38A Core spray min bypass MO Valve Outside Closed NA X-210B 1402-38B Core spray min bypass MO Valve Outside Closed NA X-210B 1001-36B RHR test line to suppression pool MO Valve Outside Closed NA X-210B 1001-18B RHR min flow bypass MO Valve Outside Open NA X-211A 1001-34A RHR - suppression pool test return MO Valve Outside Closed NA X-211A 1001-37A RHR to suppression spray header MO Valve Outside Closed NA X-211B 1001-34B RHR-suppression pool test return MO Valve Outside Closed NA X-211B 1001-37B RHR to suppression spray header MO Valve Outside Closed NA X-212 1301-41 RCIC turbine exhaust Check Outside Closed NA X-212 1301-64 RCIC turbine exhaust Stop Check Outside Open NA X-212 1399-105 RCIC turbine exhaust - press test inbd stop Manual Outside Closed NA tap on 1301-64 X-212 1399-58A RCIC turbine exhaust - press test inbd stop Manual Outside Closed NA tap between 1301-41 & 64 X-213A 1601-80B Supp Chamber drain - inboard drain valve Manual Outside Closed NA X-213A 1601-81B Supp Chamber drain - press test inbd stop Manual Outside Closed NA off torus drain line X-213A 1601-89A Supp Chamber drain - LT 1641-5A hi side inbd drain Manual Outside Closed NA off 1641-5A hi side sensing line X-213B 1601-83 Supp Chamber drain - press test inbd stop Manual Outside Closed NA X-213B 1601-89B Supp Chamber drain - LT 1641-5B hi side inbd drain Manual Outside Closed NA off 1641-5B hi side sensing line X-213B 1699-5 Supp Chamber drain - PT 1641-14 drain Manual Outside Closed NA X-216 4799-159 Instrument air to suppression chamber Check Outside Open NA X-216 4799-158 Instrument air to suppression chamber Check Inside Open NA X-216 4799-527 IA to suppression chamber - press test inbd stop Manual Outside Closed NA tap between 4799-158 & 159 X-217 8801D Torus oxygen analyzer sample AO Valve Outside Open 10 X-217 8802D Torus oxygen analyzer sample AO Valve Outside Open 10 X-220 2301-45 HPCI turbine exhaust Check Outside Closed NA Quad Cities Unit 1 and 2 A2-12 Revision QC-TRM-20-006

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 13 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-220 2301-74 HPCI turbine exhaust Stop Check Outside Open NA X-220 2399-74 HPCI exhaust vac. breaker - press test inbd stop Manual Outside Closed NA tap between 2301-74 & X-220 X-220 2301-74A HPCI turbine exhaust - press test inbd stop Manual Outside Closed NA tap on 2301-74 X-220 2301-41A HPCI turbine exhaust - press test inbd stop Manual Outside Closed NA tap on 2301-74 & 45 X-221 2301-34 HPCI turbine exhaust drain Check Outside Closed NA X-221 2301-71 HPCI turbine exhaust drain Stop Check Outside Open NA X-221 2301-41B HPCI turbine exh. drain - press test inbd stop Manual Outside Closed NA tap between 2301-34 & 71 X-221 2399-55 HPCI turbine exh. drain - press test inbd stop Manual Outside Closed NA tap between 2301-71 & X-221 X-222 1301-55 RCIC vacuum pump discharge to suppression chamber Stop Check Outside Open NA X-222 1301-40 RCIC vacuum pump discharge to suppression chamber Check Outside Closed NA X-222 1301-58B RCIC vacuum pump discharge to suppression chamber Manual Outside Closed NA tap between 1301-55 & 40

- pressure test inboard stop X-222 1399-106 RCIC vacuum pump discharge to suppression chamber Manual Outside Closed NA tap between 1301-55 & X-222

- pressure test inboard stop X-223A 1001-7A RHR pump suction from suppression chamber MO Valve Outside Open NA X-223A 1001-7B RHR pump suction from suppression chamber MO Valve Outside Open NA X-223A 1001-159A 'A' RHR Loop - torus suction inboard vent Manual Outside Closed NA tap between 1001-7A & 7B X-223A RV-1001-125A 'A' RHR Loop - pump 'A' suction RV discharge line NA Outside Cap NA between 1001-7A & torus capped line Installed X-223A RV-1001-125B 'A' RHR Loop - pump 'B' suction RV discharge line NA Outside Cap NA between 1001-7B & torus capped line Installed X-223B 1001-7C RHR pump suction from suppression chamber MO Valve Outside Open NA X-223B 1001-7D RHR pump suction from suppression chamber MO Valve Outside Open NA X-223B 1001-159B 'B' RHR Loop - torus suction inboard vent Manual Outside Closed NA tap between 1001-7C & 7D X-223B RV-1001-125C 'B' RHR Loop - pump 'C' suction RV discharge line NA Outside Cap NA between 1001-7C & torus capped line Installed X-223B RV-1001-125D 'A' RHR Loop - pump 'D' suction RV discharge line NA Outside Cap NA between 1001-7D & torus capped line Installed X-224A 1402-3A Core spray pump suction from suppression chamber MO Valve Outside Open NA X-224A 1402-21A Core spray pump suction header vent valve Manual Outside Closed NA tap between 1402-3A & torus Quad Cities Unit 1 and 2 A2-13 Revision QC-TRM-09-005

TRM Appendix A Primary Containment Isolation Devices Table A-2 Primary Containment Isolation Devices (Unit 2)

(Page 14 of 14)

Containment Valve Location Ref. Max.

Penetration Part Line to Normal Operating Number Number Isolated Valve Type Containment Status Time (sec) Comments X-224B 1402-3B Core spray pump suction from suppression chamber MO Valve Outside Open NA X-224B 1402-21B Core spray pump suction header vent valve Manual Outside Closed NA tap between 1402-3B & torus X-225 2301-36 HPCI pump suction from suppression chamber MO Valve Outside Closed NA X-225 2301-37 HPCI pmp suct from Supp chamber - press test stop Manual Outside Closed NA X-225 2399-107 HPCI pump suct from Supp chamber - vent valve Manual Outside Closed NA tap between 2301-36 and torus X-226 1301-25 RCIC pump suction from suppression chamber MO Valve Outside Closed NA X-226 1301-28 RCIC pump suction from suppression chamber - Manual Outside Closed NA tap between 1301-25 & 27 pressure test inboard stop X-227A 2499-3A CAM/suppression chamber SO Valve Outside Closed NA X-227A 2499-4A CAM/suppression chamber SO Valve Outside Closed NA X-227A 2499-9A CAM/supp chamber - press test inbd stop Manual Outside Closed NA tap between 2499-3A & 4A X-227A 1601-91A Suppression chamber LT 1641-5A low side vent Manual Outside Closed NA X-227B 2499-3B CAM/suppression chamber SO Valve Outside Closed NA X-227B 2499-4B CAM/suppression chamber SO Valve Outside Closed NA X-227B 2499-9B CAM/supp chamber - press test inbd stop Manual Outside Closed NA tap between 2499-3B & 4B X-227B 1601-91B Suppression chamber LT 1641-5B low side vent Manual Outside Closed NA X-229 2399-40 HPCI exhaust vacuum breaker MO Valve Outside Open 50 X-229 2399-41 HPCI exhaust vacuum breaker MO Valve Outside Open 50 X-229 2399-68 HPCI exhaust vac. breaker - press test inbd stop Manual Outside Closed NA tap between 2399-40 and X-229 X-229 2399-70 HPCI exhaust vac. breaker - press test inbd stop Manual Outside Closed NA tap between 2399-40 & 64 X-229 2399-71 HPCI exhaust vac. breaker - press test inbd stop Manual Outside Closed NA tap between 2399-65 & 67 X-229 2399-72 HPCI exhaust vac. breaker - press test inbd stop Manual Outside Closed NA tap between 2399-64 & 66 X-229 2399-73 HPCI exhaust vac. breaker - press test inbd stop Manual Outside Closed NA tap between 2399-66 & 41

-- 1001-20 RHR discharge to radwaste MO Valve Outside Closed 25

-- 1001-21 RHR discharge to radwaste MO Valve Outside Closed 25 Quad Cities Unit 1 and 2 A2-14 Revision QC-TRM-09-005

APPENDIX B SECONDARY CONTAINMENT ISOLATION VALVES

TRM Appendix B Secondary Containment Isolation Valves Table B-1 (page 1 of 2)

Secondary Containment Isolation Valves VALVE ISOLATION TIME (seconds)

1. [Deleted] NA

2. [Deleted] NA

3. [Deleted] NA

4. Unit 1 RWCU Precoat tank to Radwaste Drain Valve NA 1-1279-61

5. Fire Water to Reactor Building Strainer Drain Valve NA 1-4199-43

6. Fire Header to Containment Spray Header Cross-tie Stop NA Valve 1-4199-127

7. Unit 1 Primary Containment Integrated Leak Rate Test NA Flange Connection 1-4199

8. 2A RWCU Filter Demin to Radwaste Drain Valve NA RM 2-1279-21A

9. 2B RWCU Filter Demin to Radwaste Drain Valve NA RM 2-1279-21B

10. Unit 2 RWCU Precoat Outlet to Radwaste Stop Valve NA RM 2-1279-60

11. Unit 2 RWCU Precoat Tank to Radwaste Drain Valve NA 2-1279-61

12. Fire Header Strainer to Reactor Building Flush Valve NA 2-4199-43

13. Fire Header Stop Valve 2-4199-127 NA

14. Fire Header Stop Valve 2-4199-170 NA

15. Unit 2 Primary Containment Integrated Leak Rate Test NA Flange Connection 2-4199

16. Reactor Building Ventilation Inlet Isolation Damper 60 1- 5741A

17. Reactor Building Ventilation Inlet Isolation Damper 60 1-5741B

18. Reactor Building Ventilation Exhaust Isolation Damper 60 1-5742A

19. Reactor Building Ventilation Exhaust Isolation Damper 60 1-5742B

20. Reactor Building Ventilation Inlet Isolation Damper 60 2-5741A

21. Reactor Building Ventilation Inlet Isolation Damper 60 2-5741B

22. Reactor Building Ventilation Exhaust Isolation Damper 60 2-5742A

23. Reactor Building Ventilation Exhaust Isolation Damper 60 2-5742B

24. [Deleted] NA

25. [Deleted] NA

26. [Deleted] NA

27. HCVS Vent Line Rupture Disc 1-1603-2 NA Quad Cities 1 and 2 B-1 Revision QC-TRM-19-009

TRM Appendix B Secondary Containment Isolation Valves Table B-1 (page 2 of 2)

Secondary Containment Isolation Valves VALVE ISOLATION TIME (seconds)

28. HCVS Vent Line Rupture Disc 2-1603-2 NA

29. HCVS Vent Line Drn Vlv 1-1603-30 NA

30. HCVS Vent Line Drn Vlv 2-1603-30 NA

31. HCVS Nitrogen Isol Vlv to Torus Vent Vlv 1-1604-14 NA

32. HCVS Nitrogen Isol Vlv to Torus Vent Vlv 2-1604-14 NA

33. HCVS Argon Supply 3-Way Vlv 1-1605-14 NA

34. HCVS Argon Supply 3-Way Vlv 2-1605-14 NA

35. HCVS PCI Vlv Nitrogen Isol Vlv 1-1604-24 NA

36. HCVS PCI Vlv Nitrogen Isol Vlv 2-1604-24 NA Quad Cities 1 and 2 B-2 Revision QC-TRM-19-009

TRM Appendix C SFDP TABLE OF CONTENTS A. PURPOSE ............................................................................................................................2 B. REFERENCES ....................................................................................................................2 C. DEFINITIONS .....................................................................................................................2 D. LIMITATIONS....................................................................................................................3 E. PROCEDURE......................................................................................................................4 E.1 LCO 3.0.6 REQUIREMENTS.......................................................................................4 E.2 T.S. 5.5.11, Safety Function Determination Program (SFDP) Requirements .............6 E.3 Program Implementation................................................................................................8 FIGURE 1 LOSF Evaluation Flow Chart.......................................................................................11 ATTACHMENTS 1 Loss Of Safety Function Evaluation ............................................................................13 2 Supported System (s) Completion Time Extensions ..................................................19 3 SFDP Tracking Worksheet...........................................................................................26 TABLE 1 Cross Train Check Guidance........................................................................................30 Quad Cities 1 & 2 C-1 Revision 0

TRM Appendix C SFDP A. PURPOSE A.1 Objective The purpose of the SFDP is to enusre that when Technical Specification LCO 3.0.6 is used to preclude performing the Conditions and Actions for inoperable SUPPORTED SYSTEMS:

A Loss of Safety Function does not go undetected,

The plant will be placed in a safe condition if a Loss of Safety Function is determined to exist, and

A supported SYSTEM(S) Completion Time will not be inappropriately extended.

B. REFERENCES B.1 Technical Specification (TS) 3.0.6.

B.2 TS 5.5.11, "Safety Function Determination Program (SFDP)"

C. DEFINITIONS C.1 SAFETY FUNCTION -

An accident mitigation feature required by NRC regulation, plant design or Technical Specifications normally composed of two trains of SUPPORT and SUPPORTED equipment.

C.2 LOSS OF SAFETY FUNCTION (LOSF) -

A LOSF exists when, assuming no concurrent single failure and assuming no concurrent loss of offsite power or loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed.

(SEE ATTACHMENT 1.0)

C.3 SUPPORT SYSTEM -

A SYSTEM(S) that is needed by another TS LCO required SYSTEM(S) to perform a safety function.

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TRM Appendix C SFDP C.4 SUPPORTED SYSTEM -

A SYSTEM, required by the TS, which requires a SUPPORT SYSTEM to ensure its safety function can be performed. Process parameters or operating limits do not comprise SUPPORTED SYSTEM(S) for the purposes of implementing TS LCO 3.0.6.

C.5 MAXIMUM OUT OF SERVICE TIME -

A SUPPORTED SYSTEM(S) made inoperable by the SUPPORT SYSTEM(S) inoperability shall be restored to OPERABLE status within the Maximum Out Of Service Time (MOST). The MOST is the Completion Time specified in the Technical Specifications for restoring the first inoperable SUPPORT SYSTEM(S) to OPERABLE status plus the time specified in the TS for restoring the SUPPORTED SYSTEM(S) to OPERABLE status. (SEE ATTACHMENT 2 - Completion Time Extensions )

The inoperability of the SUPPORTED SYSTEM(S) must only be directly attributed to its associated SUPPORT SYSTEM(S) being inoperable and the SUPPORT SYSTEM(S) Required Actions not specifically requiring entry into the SUPPORTED SYSTEM(S) Conditions and Required Actions.

D. LIMITATIONS D.1 Reporting Requirements will be done in accordance with the Reportability Manual.

D.2 Changes to this Program shall be performed in accordance with the TRM Change Control Program.

D.3 The Shift Manager is responsible for implementing the Safety Function Determination Program.

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TRM Appendix C SFDP E. PROCEDURE E.1 LCO 3.0.6 REQUIREMENTS E.1.1 TS LCO 3.0.2 states that upon discovery of a failure to meet an TS LCO, the Required Actions of the associated Conditions shall be met, except as provided in TS LCO 3.0.5 and TS LCO 3.0.6.

E.1.2 TS LCO 3.0.6 provides an exception to TS LCO 3.0.2 for SUPPORT SYSTEM(S) by not requiring the Conditions and Required Actions for the SUPPORTED SYSTEM(S) to be performed when the failure to meet an TS LCO is solely due to a SUPPORT SYSTEM(S) LCO not being met. In this situation, although the SUPPORTED SYSTEM(S) is determined to be inoperable as defined in the Technical Specifications, LCO 3.0.6 requires only the ACTIONS of the SUPPORT SYSTEM(S) to be performed. The Conditions and Required Actions for the SUPPORTED SYSTEM(S) are not required to be performed (i.e., cascading to the SUPPORTED SYSTEM(S)) per TS LCO 3.0.6.

E.1.3 There are two types of SUPPORT SYSTEM(S) that must be considered when implementing TS LCO 3.0.6:

SUPPORT SYSTEM(S) specifically addressed in Technical Specifications, and

SUPPORT SYSTEM(S) that are not specifically addressed in Technical Specifications NOTE It may be necessary to perform OPERABILITY Determinations in accordance with Procedure RS-AA-105 in order to determine SUPPORTED SYSTEMS made Inoperable by Inoperable SUPPORT SYSTEMS.

If required SUPPORT SYSTEM(S) is addressed in the Technical Specifications, then only the SUPPORT SYSTEM(S) Conditions and Actions must be entered per TS LCO 3.0.6 (i.e., "cascading" to the SUPPORTED SYSTEM(S) is not required).

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TRM Appendix C SFDP If required SUPPORT SYSTEM(S) is NOT addressed in the Technical Specifications, then impact of the SUPPORT SYSTEM(S) inoperability must be evaluated with respect to any SUPPORTED SYSTEM(S) that is addressed in Technical Specifications.

E.1.4 A single component inoperability may result in multiple inoperabilities within a single train and affect multiple TS LCOs. TS LCO 3.0.6 limits the amount of "cascading" Actions that are required when an inoperable SYSTEM(S) renders a SUPPORTED SYSTEM(S) inoperable.

E.1.5 Any SUPPORT SYSTEM(S) inoperability must be evaluated with respect to the existing plant conditions to ensure that a Loss of Safety Function (LOSF) does not exist.

Example: The loss of Residual Heat Removal Service Water (RHRSW)

Pump to one RHRSW heat exchanger. If the heat exchanger bypass valve was found stuck open in the opposite subsystem, a LOSF will exist following a loss-of-coolant-accident and this plant configuration must be evaluated.

E.1.6 When exception of TS LCO 3.0.6 is utilized, evaluations are required in accordance with TS 5.5.11, "Safety Function Determination Program (SFDP)".

E.1.7 If LOSF is determined to exist by this Program, the appropriate Conditions and Required Actions of the TS LCO in which the LOSF exists are required to be entered.

E.1.8 When SUPPORT SYSTEM(S) Required Action directs a SUPPORTED SYSTEM(S) to be declared inoperable or directs entry into Conditions and Required Actions for a SUPPORTED SYSTEM(S), the applicable Conditions and Required Actions shall be entered in accordance with TS LCO 3.0.2.

E.1.9 It should be noted that for cases in which the inoperable SUPPORT SYSTEM(S) is addressed in Technical Specifications, "cascading" Conditions and Required Actions may still be performed in lieu of entry into TS LCO 3.0.6.

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TRM Appendix C SFDP E.2 T.S. 5.5.11, SAFETY FUNCTION DETERMINATION PROGRAM (SFDP) REQUIREMENTS NOTE If failure of a TS required SUPPORT SYSTEM(S) results in the inoperability of a SYSTEM(S) outside of the TS, and that SYSTEM(S) is subsequently relied upon by a SUPPORTED SYSTEM(S) to remain OPERABLE, then TS LCO 3.0.6 could apply and only the SUPPORT SYSTEM(S) Required Actions would be entered.

E.2.1 When TS LCO 3.0.6 is used as an exception to TS LCO 3.0.2, an evaluation is required to ensure a LOSF is detected and appropriate actions are taken.

E.2.2 Therefore, the SFDP requires:

E.2.2.1 Cross train checks to ensure a LOSF does not go undetected;

Since "cascading" the Conditions and Required Actions of a Specification are not required when applying TS LCO 3.0.6, a possibility exists that unrelated concurrent failures of more than one SYSTEM(S) could result in the complete loss of both trains of a SUPPORTED SYSTEM(S). Therefore, upon a failure to meet two or more LCOs during the same time period, an evaluation shall be conducted to determine if a LOSF exists. Generally, this is done by confirming that the remaining required redundant SYSTEM(S) are OPERABLE. ( Per ATTACHMENT 1 and TABLE 1) If a LOSF does exist, the SFDP directs that the appropriate actions be taken.

E.2.2.2 Placing the plant in a safe condition if a LOSF is detected;

If LOSF is determined to exist by this Program, the appropriate Conditions and Required Actions of the LCO in which the LOSF exists are required to be entered per step E.3.4.

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TRM Appendix C SFDP E.2.2.3 Controls on extending completion times on inoperable supported SYSTEM(S);

MOST is determined per Attachment 2.

E.2.2.4 Appropriate limitations and remedial or compensatory actions to be taken as a result of the support SYSTEM(S) inoperability.

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TRM Appendix C SFDP E.3 PROGRAM IMPLEMENTATION Performing steps E.3.1 thru E.3.7 and / or use of the Flowchart (Figure 1) will implement the requirements of the SFDP.

E.3.1 Does the degraded SYSTEM(S) render a TS required SYSTEM(S) inoperable?

E.3.1.1 If NO, then no further evaluation is necessary.

E.3.1.2 If YES, then evaluate this inoperabilities impact on any current SFDs and document on worksheet.

E.3.2 Is the inoperable SYSTEM(S) also a SUPPORT SYSTEM(S)?

E.3.2.1 If NO, then perform Conditions and Required Actions for the inoperable SYSTEM(S).

E.3.2.2 If YES, then evaluate all Conditions and Required Actions of any SUPPORTED SYSTEM(S) that are rendered inoperable as a result of this TS SUPPORT SYSTEM Inoperability.

E.3.3 Does the Inoperable SUPPORT SYSTEM(S) Specification Conditions and Required Actions direct either the Immediate Declaration of Inoperability of SUPPORTED SYSTEM(S) or performance of any SUPPORTED SYSTEM(S) Required Action(s)?

E.3.3.1 If YES, then enter the TS Condition for the SUPPORTED SYSTEM(S) as directed and perform the Required Actions.

E.3.3.2 If NO, then:

EITHER

PERFORM both the SUPPORT and the SUPPORTED SYSTEM(S) Required Actions.

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TRM Appendix C SFDP OR

PERFORM SUPPORT SYSTEM(S) Required Actions, And

PERFORM a LOSF Evaluation for ALL inoperable SUPPORT and SUPPORTED SYSTEM(S) , per ATTACHMENT 1 and Table 1.

E.3.4 If LOSF is determined to exist, then perform the appropriate Conditions and Required Actions as determined from using the following guidance.

E.3.4.1 SINGLE SUPPORT SYSTEM INOPERABILITY-When LOSF is solely due to a single T.S. SUPPORT SYSTEM ( e.g., loss of a pump suction source due to low tank level ) the appropriate LCO is the LCO for the SUPPORT SYSTEM. The Actions for the SUPPORT SYSTEM LCO adequately address the inoperabilities of that system without reliance upon the Actions of the SUPPORTED SYSTEM.

E.3.4.2 MULTIPLE SUPPORT SYSTEM INOPERABILITY-When LOSF is due to multiple T.S. SUPPORT SYSTEM inoperabilities, the appropriate LCO is the LCO for the SUPPORTED SYSTEMS.

(e.g. loss of minimum flow switch on Division 1 and the B RHR Pump is inoperable. LOSF associated with ECCS may exist following a loss-of-coolant-accident and this plant configuration must be evaluated.)

E.3.5 If NO LOSF exists or LOSF is solely due to a single T.S. support system, then for all SUPPORTED SYSTEM(S) which are rendered inoperable:

E.3.5.1 Invoke TS LCO 3.0.6 to defer entry into the Conditions and Required Actions associated with the inoperable SUPPORTED SYSTEM(S) by the following:

E.3.5.1.1 Calculate the MOST for the inoperable SUPPORTED SYSTEM(S) using ATTACHMENT 2.

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TRM Appendix C SFDP E.3.5.1.2 Complete the SFDP Worksheet per Attachment 3.0.

When filling out the SFD Worksheet it is only necessary to enter names of those SUPPORTED SYSTEMS that are made Inoperable by the Inoperable SUPPORT SYSTEM. It is not necessary to identify either OPERABLE SUPPORTED SYSTEMS or SUPPORTED SYSTEMS that are not in the MODE OF APPLICABILITY.

EXAMPLE:

Assume the C LPCI Pump minimum flow switch is INOPERABLE which results in TS LCO 3.3.5.1 not being met while the Unit is in MODE 1. A review indicates that TS LCO 3.3.5.1 equipment supports systems governed by TS 3.5.1, TS 3.5.2, TS 3.8.1, and TS 3.8.2. Although TS 3.8.1 and TS 3.8.2 are supported by TS 3.3.5.1 ( the emergency DGs are started by a Injection Spray Logic signal) , it would not be necessary to list these supported LCOs because they are not made INOPERABLE by the INOPERABLE minimum flow switch. It is also not necessary to list TS 3.5.2 because this LCO is not applicable in MODE 1. TS LCO 3.5.1 is the only SUPPORTED SYSTEM made INOPERABLE by the minimum flow switch.

E.3.6 If SUPPORTED SYSTEM(S) is NOT restored to OPERABLE status (by restoring the SUPPORT SYSTEM(S) and all associated SUPPORTED SYSTEM(S) to Operable status) within the MOST, the associated Condition for the INOPERABLE SUPPORTED SYSTEM(S) Completion Time not being met shall be entered and the Required Actions shall be performed.

E.3.7 The SFD may be closed when the INOPERABLE SUPPORT SYSTEM and SUPPORTED SYSTEM(S) on the SFDP TRACKING SHEET are restored to Operable Status. Enter the time/date when the SUPPORT SYSTEM as well as all SUPPORTED SYSTEM(S) are restored to Operable status, and sign the SFD Worksheet.

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TRM Appendix C SFDP Figure 1 LOSF Evaluation Flow Chart No Does the degraded Yes Evaluate this inoperabilities No further evaluation SYSTEM(S) render impact on any current SFDs and (Step E.3.1) is necessary a TS Required document on worksheet(s).

System Inoperable?

Yes No Yes Perform Applicable Conditions Is the Inoperable Evaluate Inoperable (Step E.3.2) and Required Actions for the System a Support Supported System(s)

Identified Inoperability System? Conditions and Required Actions Yes Does the Inoperable Support System Conditions and Required Actions direct Yes either: (1) Immediate Declaration of Inoperability Perform Applicable Conditions of Supported System(s) or and Required Actions for the (Step E.3.3) Supported System Inoperability (2) Performance of any Supported System Required Actions?

No Go to Next Page Quad Cities 1 & 2 C-11 Revision 0

TRM Appendix C SFDP Figure 1 (Continued)

LOSF Evaluation Flow Chart From previous page (Step E.3.3) (1) Perform Support System Conditions and Required Actions Perform both Support EITHER AND

& Supported System Required Actions (2) Perform LOSF Evaluation (per ATTACHMENT 1 and TABLE 1)

(Step E.3.4)

(Step E.3.5)

1. For Single Support System No Inoperability, Enter LCO, Yes

1. Calculate SUPPORTED SYSTEM(S) MOST LOSF Conditions and Required Actions of the Support System(s)

(Per ATTACHMENT 2) Exists in which the LOSF exists.

2. Complete the SFDP Worksheet (per Attachment 3.0) ? 2. For Multiple Support System Inoperability, Enter LCO, Condiitons and Required Actions of the Supported No System(s) in which the LOSF exists.

(Step E.3.6) (Step E.3.7)

No Supported System Enter associated Conditions and OPERABILITY YES Required Actions for the restored within SFD may be closed when the Supported System Completion allowed completion Support System and Time not being met time? Supported Systems are restored to operable status.

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TRM Appendix C SFDP ATTACHMENT 1 LOSS OF SAFETY FUNCTION EVALUATION A. Guidance for Safety Function Evaluation TS 5.5.11 states that a LOSF exists when, assuming no concurrent single failure, and assuming no concurrent loss of offsite power or loss of onsite diesel generator(s), a safety function assumed in the accident analysis cannot be performed.

For the purpose of this program, a graduated approach may be taken for determining the safety function of the SUPPORTED SYSTEM(S). This approach, detailed below, is graduated from most to least conservative. Even if the least conservative method is used, the requirements of TS 5.5.11 will be met. In determining whether a LOSF has occurred, at least one of these methods must be used.

Method 1: Redundant SUBSYSTEM(S)/Division/Train

a. For this method, the safety function is assumed to be the SYSTEM(S) function as described in the TS BASES. Confirm the OPERABILITY of the corresponding redundant SUPPORTED SYSTEM(S).

b. If one or more of the redundant SYSTEM(S) are found to be INOPERABLE, a LOSF may exist. The appropriate ACTIONS for a LOSF may be taken or alternatively, one of the following methods below may be used.

A redundant train evaluation used to identify a LOSF can be seen in the following three examples.

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TRM Appendix C SFDP ATTACHMENT 1 (Continued)

LOSS OF SAFETY FUNCTION EVALUATION SUPPORT/SUPPORTED SYSTEM(S) DIAGRAM EXAMPLE 1 A LOSF may exist when a SUPPORT SYSTEM is INOPERABLE, and:

A required SYSTEM redundant to the SYSTEM(S) supported by the INOPERABLE SUPPORT SYSTEM is also INOPERABLE.

If SYSTEM 2 of Train A is INOPERABLE, and SYSTEM 5 of Train B is INOPERABLE, a LOSF may exist in SUPPORTED SYSTEM(S) 5, 10, 11.

EXAMPLES TRAIN A TRAIN B System 8 System 8 System 4 System 4 System 9 System 9 System 2 System 2 System 10 System 10 System 5 System 5 System 11 System 11 System 1 System 1 System 12 System 12 System 6 System 6 System 13 System 13 System 3 System 3 System 14 System 14 System 7 System 7 System 15 System 15 Note: Chart reads from left to right, i.e., SYSTEM 1 is a SUPPORT SYSTEM for SYSTEM(S) 2 through 15.

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TRM Appendix C SFDP ATTACHMENT 1 (Continued)

LOSS OF SAFETY FUNCTION EVALUATION SUPPORT/SUPPORTED SYSTEM(S) DIAGRAM EXAMPLE 2 A LOSF may exist when a SUPPORT SYSTEM is INOPERABLE, and:

A required SYSTEM redundant to the SYSTEM(S) in turn supported by the INOPERABLE SUPPORTED SYSTEM(S) is also INOPERABLE.

If SYSTEM 2 of Train A is INOPERABLE, and SYSTEM 11 of Train B is INOPERABLE, a LOSF may exist in SYSTEM 11 which is in turn supported by SYSTEM 5.

EXAMPLES TRAIN A TRAIN B System 8 System 8 System 4 System 4 System 9 System 9 System 2 System 2 System 10 System 10 System 5 System 5 System 11 System 11 System 1 System 1 System 12 System 12 System 6 System 6 System 13 System 13 System 3 System 3 System 14 System 14 System 7 System 7 System 15 System 15 Note: Chart reads from left to right, i.e., SYSTEM 1 is a SUPPORT SYSTEM for SYSTEM(S) 2 through 15.

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TRM Appendix C SFDP ATTACHMENT 1 (Continued)

LOSS OF SAFETY FUNCTION EVALUATION SUPPORT/SUPPORTED SYSTEM(S) DIAGRAM EXAMPLE 3 A LOSF may exist when a SUPPORT SYSTEM is INOPERABLE, and:

A required SYSTEM redundant to the SUPPORT SYSTEM(S) for the SUPPORTED SYSTEM(S) (a) and (b) above is also INOPERABLE.

If SYSTEM 2 of Train A is INOPERABLE, and SYSTEM 1 of Train B is INOPERABLE, a LOSF may exist in SYSTEM(S) 2, 4, 5, 8, 9, 10 and 11.

EXAMPLES TRAIN A TRAIN B System 8 System 8 System 4 System 4 System 9 System 9 System 2 System 2 System 10 System 10 System 5 System 5 System 11 System 11 System 1 System 1 System 12 System 12 System 6 System 6 System 13 System 13 System 3 System 3 System 14 System 14 System 7 System 7 System 15 System 15 Note: Chart reads from left to right, i.e., SYSTEM 1 is a SUPPORT SYSTEM for SYSTEM(S) 2 through 15.

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TRM Appendix C SFDP ATTACHMENT 1 (Continued)

LOSS OF SAFETY FUNCTION EVALUATION Method 2: TS LCO Function Method 2: TS LCO Function

a. In certain cases, multiple SYSTEM(S) with diverse individual functions are specified under one TS LCO statement; i.e., in one Technical Specification. For these cases, the safety function may be considered to be broader than the individual SYSTEM(S) function - the safety function is the Technical Specification LCO function, not the SYSTEM(S) function (as described in Method 1 above).

b. An example of this is TS 3.5.1, ECCSOperating, in which four different SYSTEM(S) are included. In this case, the function as stated in the Bases, to cool the core during a LOCA, may be the safety function to be considered in the SFDP.

c. If a loss of TS LCO function is determined to exist, the appropriate Conditions and Required Actions for a LOSF may be taken or alternatively, the following method below may be used.

Method 3: Safety Analysis In this approach, the function of the SYSTEM(S) described in the UFSAR accident analyses is considered to be the safety function. If the SYSTEM(S) in question is not credited in the accident analyses, or if the accident function it performs is intact, then no LOSF exists. However, if the SYSTEM(S) function is credited and is lost (i.e., the accident function it performs cannot be met),

then the appropriate ACTIONS for a LOSF must be taken.

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TRM Appendix C SFDP ATTACHMENT 1 (Continued)

LOSS OF SAFETY FUNCTION EVALUATION B. Loss of Safety Function (LOSF) Evaluation Is there any INOPERABLE or degraded SUPPORT SYSTEM(S) or SUPPORTED SYSTEM(S) equipment on the opposite/redundant train that, when coupled with this INOPERABLE equipment, might result in a complete loss of a Tech Spec required safety function.

1. NO - No LOSF exists. No further evaluation is necessary.

2. YES - A LOSF may exist. Evaluate which of the following conditions apply:

a. The SYSTEM(S) is part of an TS LCO with multiple SUBSYSTEM(S) and the TS LCO specified function is intact. No LOSF exists.

b. The SYSTEM(S) will still perform its required safety function as defined in the UFSAR. No LOSF exists.

c. A LOSF exists. Perform the Required Actions in which the LOSF exists for the specific Condition(s) that apply.

C. SUPPORTED SYSTEM LOSF When a LOSF is determined to exist, and the SFDP requires entry into the appropriate Conditions and Required Actions of the LCO in which the LOSF exists, consideration must be given to the specific type of function affected.

1. SINGLE SUPPORT SYSTEM INOPERABILITY-When a LOSF is solely due to a single T.S. SUPPORT SYSTEM ( e.g., loss of a pump suction source due to low tank level ) the appropriate LCO is the LCO for the SUPPORT SYSTEM. The Actions for the SUPPORT SYSTEM LCO adequately address the inoperabilities of that system without reliance upon the Actions of the SUPPORTED SYSTEM.

2. MULTIPLE SUPPORT SYSTEM INOPERABILITY-When a LOSF is due to multiple T.S. SUPPORT SYSTEM inoperabilities, the appropriate LCO is the LCO for the SUPPORTED SYSTEMS.

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TRM Appendix C SFDP ATTACHMENT 2 SUPPORTED SYSTEM (S) COMPLETION TIME EXTENSIONS BACKROUND The T.S. require declaring SUPPORTED SYSTEM(S) INOPERABLE if a SUPPORT SYSTEM(S) inoperability renders the SUPPORTED SYSTEM(S) incapable of performing its required function. However, the Conditions and Required Actions of the SUPPORTED SYSTEM(S) do not have to be entered (i.e., the Conditions and Required Actions are not entered) except as directed by the SUPPORT SYSTEM(S) Required Actions.

Consequently, it is possible to have SUPPORTED SYSTEM(S) INOPERABLE for longer periods of time than their respective Completion Time would allow on their own. Per Technical Specifications 5.5.11, the SFDP must include measures to ensure that the SUPPORTED SYSTEM(S) Completion Times are not inappropriately extended.

The following two methods are provided for ensuring Completion Times are not inappropriately extended. METHOD 1 applies to SUPPORTED SYSTEM inoperabilities associated with a single SUPPORT SYSTEM inoperability. METHOD 2 is applicable to those SUPPORTED SYSTEM inoperabilities due to multiple SUPPORT SYSTEM inoperabilities.

METHOD 1 Single SUPPORT SYSTEM(S) INOPERABLE affecting SUPPORTED SYSTEM(S)

1. With a single SUPPORT SYSTEM(S) INOPERABLE, the affected SUPPORTED SYSTEM(S) Conditions and Required Actions are not required to be entered unless directed by the SUPPORT SYSTEM(S) Required Actions.

2. The method to accomplish this will be in the form of a calculated Maximum Out Of Service Time (MOST). The MOST will ensure that a time limit is placed on the INOPERABLE SUPPORTED SYSTEM(S) such that when an additional SUPPORT SYSTEM(S) becomes INOPERABLE no extension of time is added to the original MOST. MOST is only used when implementing the SFDP.

3. The MOST is calculated in the following manner:

Support LCO Required Action + Supported LCO Required Action = MOST Completion Time Completion Time Support Train A, LCO AAA (72hrs) + Supported Train A, LCO BBB (72 hrs)=144 hrs

+ Supported Train A, LCO UUU (72 hrs)=144 hrs

+ Supported Train A, LCO ZZZ(72 hrs)=240 hrs

+ Supported Train A, LCO RRR (168 hrs) = 240 hrs Quad Cities 1 & 2 C-19 Revision 0

TRM Appendix C SFDP ATTACHMENT 2 (Continued)

SUPPORTED SYSTEM (S) COMPLETION TIME EXTENSIONS EXAMPLE 1 Single SUPPORT SYSTEM(S) inoperable affecting SUPPORTED SYSTEM(S)

While in Mode 1, the A and B RHRSW SUBSYSTEM Pumps are declared inoperable at 0800 on 8/13/01. TS LCO 3.7.1 Conditions and Required Actions are entered. A LOSF is performed and all B train components are verified to be operable. Therefore, the TS LCO 3.0.6 and the SFDP can be implemented. All SUPPORTED SYSTEM(S) have been identified and the calculated MOST are as follows:

LCO COMPLETION SUPPORT / SUPPORTED SYSTEM(S) CONDITION TIME MOST RHRSW Pump (A & B) Support 3.7.1 A.1 30 days RHRSW SUBSYSTEM Support 3.7.1 C.1 7 days RHR Suppression Pool Cooling Supported 3.6.2.4 A.1 7 days 14 days RHR Suppression Pool Spray Supported 3.6.2.4 A.1 7 days 14 days 3.7.1 Condition A applies to both inoperable pumps. One RHRSW pump must be operable at 0800 on 8/20/01 (7 days) at which time the RHR Suppression Pool Cooling and Spray are operable. The RHR Suppression Pool Cooling and Spray must be operable at 0800 on 8/27/01 (MOST). The second RHRSW pump must be operable at 0800 on 9/12/01 (30 days).

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TRM Appendix C SFDP ATTACHMENT 2 (Continued)

SUPPORTED SYSTEM (S) COMPLETION TIME EXTENSIONS EXAMPLE 2 With the A and B RHRSW pumps still inoperable, the A and B RHR pumps are determined to be inoperable at 0800 on 8/19/01. TS LCO 3.6.2.3, 3.6.2.4 Conditions and Required Actions are evaluated. It has been determined that both Condition 3.6.2.3.A and 3.6.2.4.A are now applicable.

LCO COMPLETION CONDITION TIME MOST SUPPORT / SUPPORTED SYSTEM(S)

RHRSW Pump (A & B) Support 3.7.1 A.1 30 days RHRSW SUBSYSTEM Support 3.7.1 C.1 7 days ECCS - Operating (LPCI A & B) Support 3.5.1.A.1 30 days ECCS - Operating Support 3.5.1.B.1 7 days RHR Suppression Pool Cooling Support 3.6.2.3 A.1 7 days RHR Suppression Pool Cooling Supported 3.6.2.3 A.1 7 days 14 days RHR Suppression Pool Spray Support 3.6.2.4 A.1 7 days RHR Suppression Pool Spray Supported 3.6.2.4 A.1 7 days 14 days One RHRSW pump must be operable at 0800 on 8/20/01 (7 days). The A and B RHR pumps must be operable at 0800 on 8/26/01 (7 days). The RHR Suppression Pool Cooling and Spray must still be operable at 0800 on 8/27/01 (MOST). The second RHRSW pump must still be operable at 0800 on 9/12/01 (30 days).

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TRM Appendix C SFDP ATTACHMENT 2 (Continued)

SUPPORTED SYSTEM (S) COMPLETION TIME EXTENSIONS EXAMPLE 3 The A RHRSW pump is declared operable at 1000 on 8/19/01 while the A and B RHR pumps remain inoperable. TS LCO 3.7.1 Conditions and Required Actions are evaluated. It has been determined that Condition 3.7.1.C for the RHRSW system is no longer applicable.

LCO COMPLETION CONDITION TIME MOST SUPPORT / SUPPORTED SYSTEM(S)

RHRSW Pump A Support 3.7.1 A.1 30 days ECCS - Operating (LPCI A & B) Support 3.5.1.A.1 30 days ECCS - Operating Support 3.5.1.B.1 7 days RHR Suppression Pool Cooling Support 3.6.2.3 A.1 7 days RHR Suppression Pool Spray Support 3.6.2.4 A.1 7 days RHR Suppression Pool Cooling Supported 3.6.2.3 A.1 7 days 14 days RHR Suppression Pool Spray Supported 3.6.2.4 A.1 7 days 14 days The RHR A and B pumps must be operable at 0800 on 8/26/01 (7 days) which supports the restoration of both RHR Suppression Pool Cooling / Spray and ECCS LCOs. The RHR Suppression Pool Cooling and Spray must be operable at 0800 on 8/27/01 (Original MOST).

The second RHRSW pump must be operable at 0800 on 9/12/01 (30 days).

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TRM Appendix C SFDP ATTACHMENT 2 (Continued)

SUPPORTED SYSTEM (S) COMPLETION TIME EXTENSIONS EXAMPLE 4 With the A and B RHR and B RHRSW pumps still inoperable, the A RHRSW pump is again determined to be inoperable at 0800 on 8/25/01. TS LCO 3.7.1.C Conditions and Required Actions are entered.

LCO COMPLETION CONDITION TIME MOST SUPPORT / SUPPORTED SYSTEM(S)

RHRSW Pump (A & B) Support 3.7.1 A.1 30 days RHRSW SUBSYSTEM Support 3.7.1 C.1 7 days ECCS - Operating (LPCI A & B) Support 3.5.1.A.1 30 days ECCS - Operating Support 3.5.1.B.1 7 days RHR Suppression Pool Cooling Support 3.6.2.3 A.1 7 days RHR Suppression Pool Spray Support 3.6.2.4 A.1 7 days RHR Suppression Pool Cooling Supported 3.6.2.3 A.1 7 days 14 days RHR Suppression Pool Spray Supported 3.6.2.4 A.1 7 days 14 days The A and B RHR pumps must be operable at 0800 on 8/26/01. The RHR Suppression Pool Cooling and Sprays must be operable at 0800 on 8/27/01 (Original MOST). Therefore, at least one of the RHRSW pumps must be operable 0800 on 8/27/01 in order for the RHR Suppression Pool Cooling and Spray to be operable.

If the B RHRSW pump is made operable, then the A RHRSW pump must be operable at 0800 on 9/13/01 (30 days + 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension allowed by TS 1.3)

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TRM Appendix C SFDP ATTACHMENT 2 (Continued)

SUPPORTED SYSTEM (S) COMPLETION TIME EXTENSIONS EXAMPLE 5 A Division 1 Core Spray Pump Discharge Flow - Low (BYPASS) instrument has become inoperable. TS LCO 3.3.5.1 Conditions and Required Actions are entered. A LOSF is performed and all Division 2 components are verified to be operable. Therefore, the TS LCO 3.0.6 and the SFDP can be implemented. All SUPPORTED SYSTEM(S) have been identified and the calculated MOST are as follows:

LCO COMPLETION CONDITION TIME MOST SUPPORT / SUPPORTED SYSTEM(S)

Core Spray Pump Discharge Flow Support 3.3.5.1 E.2 7 Days ECCS SYSTEM (CS) Supported 3.5.1 B.1 7 Days 14 Days In this example, the channel must be restored to operable status within 7 Days per Required Action 3.3.5.1.E.2, or the Supported CS pumps must be declared inoperable per 3.3.5.1.H..1.

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TRM Appendix C SFDP ATTACHMENT 2 (Continued)

SUPPORTED SYSTEM (S) COMPLETION TIME EXTENSIONS METHOD 2 Multiple SUPPORT SYSTEM(S) become INOPERABLE affecting the same SUPPORTED SYSTEM(S)

There may be some cases where two SUPPORT SYSTEMS for a common SUPPORTED SYSTEM become INOPERABLE simultaneously. In this case, the following method should be used to calculate the MOST.

a. The first SUPPORT / SUPPORTED MOST plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The subsequent SUPPORT / SUPPORTED MOST as measured from discovery of the first SUPPORT inoperability.

EXAMPLE 1- Multiple SUPPORT SYSTEM(S)

Two SUPPORT SYSTEM(S) become INOPERABLE at different times.

1. SYSTEMS B and C SUPPORT SYSTEM A.

SYSTEM B (SUPPORT SYSTEM) becomes INOPERABLE at T = 0 days.

SYSTEM A (SUPPORTED SYSTEM) Completion Time - 3 days

SYSTEM B (SUPPORT SYSTEM) Completion Time - 3 days

SYSTEM C (SUPPORT SYSTEM) Completion Time - 7 days

2. SYSTEM B (SUPPORT SYSTEM) with a Completion Time of 3 days, renders SYSTEM A (SUPPORTED SYSTEM) INOPERABLE. Method 1 is applied, which allows an overall MOST of 6 days for the SYSTEM A (SUPPORTED SYSTEM).

3. At T = 1 day, SYSTEM C (SUPPORT SYSTEM) becomes INOPERABLE and has a Completion Time of 7 days. SYSTEM C (SUPPORT SYSTEM) also supports SYSTEM A (SUPPORTED SYSTEM). SYSTEM B (SUPPORT SYSTEM) continues to remain INOPERABLE through its Completion Time T = 3 days.

4. Once SYSTEM C (SUPPORT SYSTEM) becomes INOPERABLE concurrent with SYSTEM B, Method 2 is applied at T=1, the Most is as follows:

Method 2a: Original MOST ( SYSTEM A +B) + 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months = 7days, OR Method 2b: New MOST ( SYSTEM A + C ) = 10 days measured from T = 0.

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TRM Appendix C SFDP ATTACHMENT 3 SFDP TRACKING WORKSHEET INSTRUCTIONS The Safety Function Determination (SFD) Worksheet is used to document the supported systems of an INOPERABLE SUPPORT SYSTEM, track their Maximum Out Of Service Time (MOST), and document whether or not a loss of safety function exists. It is also the mechanism for documenting the reevaluation of safety function determinations that are necessary when subsequent LCOs are entered.

1. Enter the noun name of the INOPERABLE SUPPORT SYSTEM / component.

2. SUPPORT SYSTEM Tech Spec Condition / Required Action.

3. Date and time of entry into LCO Conditions and Required Actions for the SUPPORT SYSTEM.

4. Completion time allowed for the Required Action of the SUPPORT SYSTEM Tech Spec.

5. Enter the noun name of each Tech Spec system supported by the INOPERABLE SUPPORT SYSTEM.

6. For each supported system, list the Tech Spec Condition / Required Action.

7. Record the allowed completion time for the supported system Required Action.

8. Perform a cross train check (ATTACHMENT 1/ Method 1 and TABLE 1) to verify operability of the INOPERABLE supported systems redundant equipment, as well as the support features for the redundant equipment. Block 8 is filled in with yes or no.

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TRM Appendix C SFDP ATTACHMENT 3 (Continued)

SFDP TRACKING WORKSHEET

9. Based on the results of the cross train check performed in step 8 of the worksheet, determine whether or not the safety function of the supported system has been lost. If the cross train check, ATTACHMENT 1/ Method 1 has failed or can not be performed, Methods 2 or 3 may be used to assess the status of the safety function in question. If the safety function has been lost, then enter the appropriate Conditions and Required Actions for that system or component using the following guidance: 1. SINGLE SUPPORT SYSTEM INOPERABILITY-When a LOSF is solely due to a single T.S. SUPPORT SYSTEM ( e.g., loss of a pump suction source due to low tank level ) the appropriate LCO is the LCO for the SUPPORT SYSTEM. The Actions for the SUPPORT SYSTEM LCO adequately address the inoperabilities of that system without reliance upon the Actions of the SUPPORTED SYSTEM. 2. MULTIPLE SUPPORT SYSTEM INOPERABILITY- When a LOSF is due to multiple T.S. SUPPORT SYSTEM inoperabilities, the appropriate LCO is the LCO for the SUPPORTED SYSTEMS.

10. If the safety function has not been lost or LOSF is solely due to a single T.S. support system, calculate the Maximum Out of Service Time for the supported system. If ATTACHMENT 2 Method 1 is used, this will be the sum of block 4 and block 7. If Method 2 is used, see ATTACHMENT 2.

11. Expiration time: Time determined in either Method 1 or 2 ATTACHMENT 2 measured from the time in step 3 (Date/Time Entered) in HR: MIN on the MM/DD/YR.

12. The comment block can be used to record any notes or other references.

13. Preparer sign and date.

14. Sign and date for Verification of the SFD, indicating that you concur with the listed results.

15. As subsequent inoperabilities occur, all existing SFDs must be reviewed to determine their validity. Record the new LCO Condition and Required Actions and initial and date indicating either yes, the SFD is still valid, or no the SFD is no longer valid. If the SFD is no longer valid based on the new LCO Conditions and Required Actions, a new SFD must be performed. Attach the new SFD to the now invalid SFD.

16. The SFD may be closed out when the INOPERABLE SUPPORT SYSTEM and SUPPORTED SYSTEM(S) listed on the SFDP Tracking Sheet are returned to OPERABLE STATUS. Enter the Time and Date when the SUPPORT SYSTEM and SUPPORTED SYSTEM(S) are returned to OPERABLE STATUS and sign the Worksheet.

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TRM Appendix C SFDP ATTACHMENT 3 (Continued)

SFDP TRACKING WORKSHEET SUPPORT SYSTEM INOPERABLE

1. System Name / Component 2. Tech Spec Condition / Required Action

3. Date / Time Entered 4. Completion Time SUPPORTED SYSTEMS / COMPONENTS

5. Supported 6. T.S. Condition / 7. Completion 8. Redundant 9. Loss of Safety 10. M.O.S.T. 11. Expiration 12. Comments System Name Required Action Time Inoperability? Function? Time

13. Prepared by: 14. Verified by:

sign and date sign and date

15. REVIEW FOR SUBSEQUENT INOPERABILITIES (See Attached Worksheet)

16. SFD CLOSE OUT: The Support Systems and Supported System(s) listed above have been returned to OPERABLE status Time / Date / Signature Quad Cities 1 & 2 C-28 Revision 0

TRM Appendix C SFDP ATTACHMENT 3 (Continued)

SFDP TRACKING WORKSHEET SFDP REVIEW FOR SUBSEQUENT INOPERABILITIES SFDPs VALID VERIFIED BY NEW LCO CONDITION # (Y / N) (INITIAL / DATE)

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TRM Appendix C SFDP TABLE 1 CROSS TRAIN CHECK GUIDANCE Guidelines for Performing Cross Train Checks The following matrix is meant to list possible SUPPORT to SUPPORTED LCO relationships for the purpose of implementing the cross train checks as required by LCO 3.0.6. and 5.5.11.

This matrix does NOT:

Cover all possible combinations or permutations of SUPPORT / SUPPORTED LCO relationships.

Cover SUPPORT / SUPPORTED relationships for items outside of Tech Spec (i.e., room coolers or snubbers).

Cover SUPPORT / SUPPORTED relationships for LCOs that are NOT applicable in a given mode

Cover Technical Requirement Manual LCOs or features.

Include Support Features and Supported Systems if the Required Actions for the INOPERABLE Support Feature direct the entry into the TS ACTIONS for the Supported System.

The purpose behind this matrix is to provide guidance when assessing a LOSF on based on SUPPORTED system LCOs, due to inoperability of a SUPPORT SYSTEM LCO.

The following minimum items should be considered when evaluating the redundant train:

Panel Walkdown

DEL Review

Schedule Review

Current Outage Reports

Physical walkdown as needed by the US

OOS Review

TMOD

Operability Evaluations Each situation should be assessed on its own merit, to determine LCO impact.

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TRM Appendix C SFDP TABLE 1 (Continued)

CROSS TRAIN CHECK GUIDANCE Support Supported Feature TS System TS Number Support Feature Number Supported System 3.3.5.1 Emergency Core Cooling 3.5.1 ECCS - Operating System (ECCS) Instrumentation 3.5.2 ECCS - Shutdown 3.8.1 AC Sources - Operating 3.8.2 AC Sources - Shutdown 3.3.5.2 Reactor Core Isolation Cooling 3.5.3 RCIC System (RCIC) System Instrumentation 3.3.6.1 Primary Containment Isolation 3.1.7 Standby Liquid Control (SLC) System Instrumentation 3.4.7 Residual Heat Removal (RHR)

Shutdown Cooling System - Hot Shutdown 3.4.8 Residual Heat Removal (RHR)

Shutdown Cooling System - Cold Shutdown 3.6.1.3 Primary Containment Isolation Valves (PCIVs) Residual Heat Removal (RHR) 3.9.8 Residual Heat Removal (RHR) - High Water Level 3.9.9 Residual Heat Removal (RHR) - Low Water Level 3.3.6.2 Secondary Containment 3.6.4.2 Secondary Containment Isolation Valves Isolation Instrumentation (SCIVs) 3.6.4.3 Standby Gas Treatment (SGT) System 3.3.6.3 Relief Valve Instrumentation 3.4.3 Safety and Relief Valves 3.6.1.6 Low Set Relief Valves Quad Cities 1 & 2 C-31 Revision 0

TRM Appendix C SFDP Support Supported Feature TS System TS Number Support Feature Number Supported System 3.3.7.1 Control Room Emergency 3.7.4 Control Room Emergency Ventilation Ventilation (CREV) System (CREV) System Instrumentation 3.3.8.1 Loss of Power (LOP) System 3.3.5.1 Emergency Core Cooling System Instrumentation (ECCS) Instrumentation 3.8.1 AC Sources - Operating 3.8.2 AC Sources - Shutdown 3.6.1.7 Reactor Building-to- 3.6.1.1 Primary Containment Suppression Chamber Vacuum Breakers 3.6.1.8 Suppression Chamber-to- 3.6.1.1 Primary Containment Drywell Vacuum Breakers Secondary Containment Isolation Valves (SCIVs) 3.6.4.2 Secondary Containment 3.6.4.1 Secondary Containment Isolation Valves (SCIVs) 3.6.4.3 Standby Gas Treatment (SGT) 3.6.4.1 Secondary Containment System Quad Cities 1 & 2 C-32 Revision 0

TRM Appendix C SFDP TABLE 1 (Continued)

CROSS TRAIN CHECK GUIDANCE Support Supported Feature TS System TS Number Support Feature Number Supported System 3.7.1 Residual Heat Removal Service 3.4.7 Residual Heat Removal (RHR)

Water (RHRSW) System Shutdown Cooling System - Hot Shutdown 3.4.8 Residual Heat Removal (RHR)

Shutdown Cooling System - Cold Shutdown 3.6.2.3 Residual Heat Removal (RHR)

Suppression Pool Cooling 3.6.2.4 Residual Heat Removal (RHR)

Suppression Pool Spray 3.7.5 Control Room Emergency Ventilation Air Conditioning (AC) System 3.9.8 Residual Heat Removal (RHR) - High Water Level 3.9.9 Residual Heat Removal (RHR) - Low Water Level 3.7.2 Diesel Generator Cooling Water 3.5.1 ECCS - Operating (DGCW) System 3.5.2 ECCS - Shutdown 3.8.1 AC Sources - Operating 3.8.2 AC Sources - Shutdown 3.7.3 Ultimate Heat Sink (UHS) 3.7.1 Residual Heat Removal Service Water (RHRSW) System 3.7.2 Diesel Generator Cooling Water (DGCW) System 3.8.1 AC Sources - Operating 3.8.7 Distribution System - Shutdown (AC Portion Only) 3.8.2 AC Sources - Shutdown 3.8.8 Distribution System - Shutdown (AC Portion Only) 3.8.4 DC Sources - Operating 3.8.7 Distribution System - Shutdown (DC Portion Only) 3.8.5 DC Sources - Shutdown 3.8.8 Distribution System - Shutdown (DC Portion Only)

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TRM Appendix C SFDP TABLE 1 (Continued)

CROSS TRAIN CHECK GUIDANCE Support Supported Feature TS System TS Number Support Feature Number Supported System 3.8.7 Distribution System - 3.1.7 Standby Liquid Control (SLC)

(AC Only) Operating (AC portion Only) System 3.3.3.1 Post Accident Monitoring (PAM)

Instrumentation 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation 3.3.5.2 Isolation Condenser (IC) System Instrumentation (17 & 20 valves) 3.3.6.1 Primary Containment Isolation Instrumentation 3.3.6.2 Secondary Containment Isolation Instrumentation 3.3.7.1 Control Room Emergency Ventilation (CREV) System Instrumentation 3.4.4 RCS Operational Leakage 3.4.5 RCS Leakage Detection Instrumentation 3.4.7 Residual Heat Removal (RHR)

Shutdown Cooling System - Hot Shutdown 3.5.1 Emergency Core Cooling System (ECCS) - Operating 3.5.3 RCIC System Quad Cities 1 & 2 C-34 Revision 0

TRM Appendix C SFDP TABLE 1 (Continued)

CROSS TRAIN CHECK GUIDANCE Support Supported Feature TS System TS Number Support Feature Number Supported System 3.8.7 Distribution System - 3.6.1.3 Primary Containment Isolation (continued) Operating (AC portion Only) Valves (PCIVs)

(AC Only) 3.6.2.3 Residual Heat Removal (RHR)

Suppression Pool Cooling 3.6.2.4 Residual Heat Removal (RHR)

Suppression Pool Spray 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) 3.6.4.3 Standby Gas Treatment (SGT)

System 3.7.1 Residual Heat Removal Service Water (RHRSW) System 3.7.2 Diesel Generator Cooling Water (DGCW) System 3.7.4 Control Room Emergency Ventilation (CREV) System 3.7.5 Control Room Emergency Ventilation Air Conditioning (AC) System 3.7.9 Safe Shutdown Makeup Pump (SSMP) System 3.8.1 AC Sources - Operating 3.8.3 Diesel Fuel Oil and Starting Air 3.8.4 DC Sources - Operating Quad Cities 1 & 2 C-35 Revision 0

TRM Appendix C SFDP TABLE 1 (Continued)

CROSS TRAIN CHECK GUIDANCE Support Supported Feature TS System TS Number Support Feature Number Supported System 3.8.7 Distribution Systems - 3.3.3.1 Post Accident Monitoring (DC Only) Operating (Pam) Instrumentation (DC Only) 3.3.4.1 Anticipated Transient Without SCRAM Recirculation Pump Trip (ATWS-RPT)

Instrumentation 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation 3.3.6.1 Primary Containment Isolation Instrumentation 3.3.8.1 Loss of Power (LOP) System Instrumentation 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring 3.4.3 Safety and Relief Valves 3.4.7 Residual Heat Removal (RHR)

Shutdown Cooling System -

Hot Shutdown 3.5.1 Emergency Core Cooling System (ECCS) - Operating Quad Cities 1 & 2 C-36 Revision 0

TRM Appendix C SFDP TABLE 1 (Continued)

CROSS TRAIN CHECK GUIDANCE Support Supported Feature TS System TS Number Support Feature Number Supported System 3.8.7 Distribution Systems - 3.5.3 RCIC System (continued) Operating (DC Only) (DC Portion Only) 3.6.1.3 Primary Containment Isolation Valves (PCIVs) 3.6.2.3 Residual Heat Removal (RHR)

Suppression Pool Cooling 3.6.2.4 Residual Heat Removal (RHR)

Suppression Pool Spray 3.7.1 Residual Heat Removal Service 3.7.2 Diesel Generator Cooling Water (DGCW) System 3.8.1 AC Sources - Operating Quad Cities 1 & 2 C-37 Revision 0

TRM Appendix C SFDP TABLE 1 (Continued)

CROSS TRAIN CHECK GUIDANCE Support Supported Feature TS System TS Number Support Feature Number Supported System 3.8.8 Distribution Systems - 3.3.5.1 Emergency Core Cooling (AC Only) Shutdown System (ECCS) Instrumentation (AC Portion Only) 3.3.6.1 Primary Containment Isolation Instrumentation 3.3.6.2 Secondary Containment Isolation Instrumentation 3.3.7.1 Control Room Air Filtration (CREV) System Instrumentation 3.4.8 Residual Heat Removal (RHR)

Shutdown Cooling System Cold Shutdown 3.5.2 Emergency Core Cooling System (ECCS) - Shutdown 3.6.1.3 Primary Containment Isolation Valves (PCIVs) 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

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TRM Appendix C SFDP TABLE 1 (Continued)

CROSS TRAIN CHECK GUIDANCE Support Supported Feature TS System TS Number Support Feature Number Supported System 3.8.8 Distribution Systems - 3.6.4.3 Standby Gas Treatment (SGT) System (continued) Shutdown (AC Only) (AC Portion Only) 3.7.1 Residual Heat Removal Service Water (RHRSW) System 3.7.2 Diesel Generator Cooling Water (DGCW) System 3.7.4 Control Room Emergency Ventilation (CREV) System 3.7.5 Control Room Emergency Ventilation Air Conditioning (AC) System 3.8.2 AC Sources - Shutdown 3.8.3 Diesel Fuel Oil and Starting Air 3.8.5 DC Sources - Shutdown 3.9.8 Residual Heat Removal (RHR) - High Water Level 3.9.9 Residual Heat Removal (RHR) - Low Water Level Quad Cities 1 & 2 C-39 Revision 0

TRM Appendix C SFDP TABLE 1 (Continued)

CROSS TRAIN CHECK GUIDANCE Support Supported Feature TS System TS Number Support Feature Number Supported System 3.8.8 Distribution Systems - 3.3.5.1 Emergency Core Cooling (DC Only) Shutdown System (ECCS) Instrumentation (DC Portion Only) 3.3.6.1 Primary Containment Isolation Instrumentation 3.3.8.1 Loss of Power (LOP) System Instrumentation 3.3.8.2 Reactor Protective System (RPS) Electric Power Monitoring 3.4.8 Residual Heat Removal (RHR)

Shutdown Cooling System -

Cold Shutdown 3.5.2 ECCS - Shutdown 3.6.1.3 Primary Containment Isolation Valves (PCIVs) 3.8.2 AC Sources - Shutdown 3.9.8 Residual Heat Removal (RHR)-

High Water Level 3.9.9 Residual Heat Removal (RHR)-

Low Water Level Quad Cities 1 & 2 C-40 Revision 0

TRM TS Bases Control Program Appendix D TECHNICAL SPECIFICATIONS BASES CONTROL PROGRAM TABLE OF CONTENTS SECTION TITLE 1.1 PURPOSE

1.2 REFERENCES

1.3 DEFINITIONS AND/OR ACRONYMS 1.4 PROGRAM DESCRIPTION 1.5 PROGRAM IMPLEMENTATION 1.6 ACCEPTANCE CRITERIA 1.7 LCOARS/COMPENSATORY MEASURES 1.8 REPORTING REQUIREMENTS 1.9 CHANGE CONTROL Quad Cities Units 1 & 2 1 of 8 Revision QC-TRM-21-001 Technical Requirements Manual

TRM TS Bases Control Program Appendix D 1.1 PURPOSE The purpose of this Program is to provide guidance for identifying, processing, and implementing changes to the Technical Specifications (TS) Bases. This Program implements and satisfies the requirements of TS 5.5.10, "Technical Specifications (TS)

Bases Control Program."

This Program is applicable to the preparation, review, implementation, and distribution of changes to the TS Bases. This Program also provides guidance for preparing TS Bases Change Packages for distribution.

1.2 REFERENCES

1. TS 5.5.10, "Technical Specifications (TS) Bases Control Program"

2. 10 CFR 50.4, "Written Communications"

3. 10 CFR 50.59, "Changes, Tests and Experiments"

4. 10 CFR 50.71, "Maintenance of Records, Making of Reports"

5. 10 CFR 50.90, "Application for Amendment of License or Construction Permit" 1.3 DEFINITIONS AND/OR ACRONYMS

1. 10 CFR 50.59 REVIEW - A written regulatory evaluation which provides the basis for the determination that a change does, or does not, require NRC approval pursuant to 10 CFR 50.59.

The scope of the evaluation should be commensurate with the potential safety significance of the change, but must address the relevant safety concerns included in the Safety Analysis Report and other owner controlled documents. The depth of the evaluation must be sufficient to determine whether or not NRC approval is required prior to implementation. Depending upon the significance of the change, the evaluation may be brief; however, a simple statement of conclusion is not sufficient.

2. EDITORIAL CHANGE - Editorial changes include correction of punctuation, insignificant word or title changes, style or format changes, typographical errors, or correction of reference errors that do not change the intent, outcome, results, functions, processes, responsibilities, or performance requirements of the item being changed. Changes in numerical values shall not be considered as editorial Quad Cities Units 1 & 2 2 of 8 Revision QC-TRM-21-001 Technical Requirements Manual

TRM TS Bases Control Program Appendix D changes. Editorial changes do not constitute a change to the TRM and therefore do not require further 10 CFR 50.59 Reviews. If the full scope of this proposed change is encompassed by one or more of the below, then the change is considered editorial.

- Rewording or format changes that do not result in changing actions to be accomplished.

- Deletion of cycle-specific information that is no longer applicable.

- Addition of clarifying information, such as:

- Spelling, grammar, or punctuation changes

- Changes to references

- Name or title references 1.4 PROGRAM DESCRIPTION

1. A Licensee may make changes to the TS Bases without prior NRC approval provided the changes do not require either of the following:

a. A change in the TS as currently incorporated in the license; or

b. A change to the Updated Final Safety Analysis Report (UFSAR) or TS Bases that requires NRC approval pursuant to 10 CFR 50.59.

2. Changes that meet the above criteria (i.e., 1.4.1.a or 1.4.1.b) shall be submitted to the NRC pursuant to 10 CFR 50.90 and reviewed and approved by the NRC prior to implementation.

3. The TS Bases shall be maintained consistent with the UFSAR.

4. If a change to the TS Bases is not consistent with the UFSAR, then the cognizant Engineer shall prepare and submit a UFSAR Change Package when the TS Bases Change Request is submitted to Regulatory Assurance (RA) for processing.

5. Changes to the TS Bases that do not require prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e), as modified by approved exemptions.

6. TS Bases changes associated with a TS Amendment shall be implemented consistent with the implementation requirements of the TS Amendment.

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TRM TS Bases Control Program Appendix D

7. Corporate Licensing (CL) is responsible for the control and distribution of the TS Bases. In order to prevent distribution errors (i.e., omissions or duplications), CL shall maintain the master TS Bases distribution list.

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TRM TS Bases Control Program Appendix D 1.5 PROGRAM IMPLEMENTATION

1. TS Bases Change Requestor identifies the need for a revision to the TS Bases and notifies the RA Licensing Engineer (i.e., hereafter referred to as RA LE). A TS Bases change can be initiated through any Stations' RA. TS Bases Change Requestor notifies their counterparts on the need for a change.

2. RA LE notifies their counterparts of identified need for revision to the TS Bases.

3. RA LE obtains concurrence from CL on the need for a change.

4. CL reviews the agreed upon TS Bases wording changes for consistency with format, rules of usage, and technical adequacy and provides final concurrence.

5. After concurrence of the TS Bases wording changes is obtained, CL makes an electronic version available in a working directory for use in the preparation of the 10 CFR 50.59 REVIEW and Station Qualified Review (SQR) process. CL shall ensure that the master electronic TS Bases files are revised per step 15 below upon receiving SQR approval. The Revision number in the footer should be a sequential number (i.e., 1, 2, etc.).

NOTE *

If the TS Bases changes are applicable to more than one *

Station, the following steps should be performed *

concurrently for each Station. *

6. TS Bases Change Requestor provides a 10 CFR 50.59 REVIEW for the TS Bases changes in accordance with appropriate plant procedures. An exception to this requirement applies when the changes are being requested in order to reflect an approved NRC Safety Evaluation (SE) associated with a site specific Operating License or TS change. The NRC SE is sufficient to support the changes provided it has been determined that the changes are consistent with and entirely bounded by the NRC SE. A 10 CFR 50.59 REVIEW shall be performed for TS Bases changes that reflect generic industry approval by an NRC SE to determine site specific applicability. A 10 CFR 50.59 REVIEW is not required for an EDITORIAL CHANGE.

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TRM TS Bases Control Program Appendix D

7. TS Bases Change Requestor completes Attachment A, "Technical Specifications Bases Change Request Form," as follows:

a. Identifies the affected sections, and includes a copy of the proposed TS Bases changes;

b. Briefly summarizes the changes including the LCO, Action, or Surveillance Requirement to which the changes apply;

c. Briefly summarizes the reason for the changes and attaches all supporting documentation;

d. Identifies any schedule requirements and proposed implementation date that apply (i.e., describe any time limitations that might apply which would require expedited processing). If the changes are outage related, then checks "yes" and lists the applicable outage identifier;

e. Identifies any known implementation requirements such as procedure changes, UFSAR changes, Passport changes, Reportability Manual revisions, pre-implementation training requirements, etc.;

f. If a 10 CFR 50.59 REVIEW was prepared to support the TS Bases changes, the Requestor then checks the appropriate box, lists the associated 10 CFR 50.59 REVIEW Number, and attaches the original. If a NRC SE (safety evaluation) covers the scope of the change, the requestor then checks the appropriate box, and identifies the applicable NRC SE by date, revision, and subject.

g. If the changes to the TS Bases are EDITORIAL CHANGES, then the Requestor checks the appropriate box and no 10 CFR 50.59 REVIEW is required;

h. Signs and dates as Requestor and identifies the originating department;

i. Obtains approval to proceed from Department Supervisor (or designee); and

j. Returns Attachment A to the RA LE.

8. RA LE reviews the TS Bases Change Request Form, including supporting documentation, and documents the review by signing Attachment A. The review verifies that the Quad Cities Units 1 & 2 6 of 8 Revision QC-TRM-21-001 Technical Requirements Manual

TRM TS Bases Control Program Appendix D following information or documentation is included:

a. Completed 10 CFR 50.59 REVIEW. If the changes are related to an approved NRC SE associated with a site specific Operating License or TS change and determined to be entirely bounded by the NRC SE, then only a copy of the SE is required to be attached and no 10 CFR 50.59 REVIEW is required. A 10 CFR 50.59 REVIEW is not required for an EDITORIAL CHANGE;

b. Identification of known documents requiring revisions; and

c. Completed UFSAR Change Request with supporting documentation, in accordance with appropriate plant procedures, if applicable.

9. If the TS Bases change is not an EDITORIAL CHANGE, the RA LE/TS Bases Change Requestor obtains SQR approval of the TS Bases changes by performing the following:

a. RA LE prepares the TS Bases Change SQR package. The SQR package shall include Attachment A (including completed 10 CFR 50.59 REVIEW or NRC SE) and the revised TS Bases pages. Attachment A is provided for the purpose of reviewing and finalizing the implementation requirements and ensuring the necessary actions have been initiated. RA LE shall assign Action Tracking (AT) items, as necessary, to track implementation requirements;

b. TS Bases Change Requestor submits the TS Bases Change SQR package to the SQR Committee members for a preliminary review. The SQR composition shall include RA and Operating Departments in all cases; and

c. TS Bases Change Requestor resolves preliminary review comments and finalizes the TS Bases Change SQR package.

10. The RAM shall determine the need for Plant Operations Review Committee (PORC) approval. The need for PORC approval shall be documented on Attachment A.

11. RA LE/TS Bases Change Requestor obtains PORC approval, if necessary.

12. RA LE notifies CL of approval of the TS Bases changes by forwarding a copy of the approved SQR/PORC Change package to CL.

13. After approval of the TS Bases changes by SQR/PORC, CL Quad Cities Units 1 & 2 7 of 8 Revision QC-TRM-21-001 Technical Requirements Manual

TRM TS Bases Control Program Appendix D ensures that the controlled master electronic files are updated.

14. CL/RA processes the TS Bases changes using the forms and instructions in LS-AA-100-1000.

15. CLE creates a TS Bases Change Package. The TS Bases Change Package shall consist of:

a. TS Bases Change Instruction Form;

b. Revised Affected Page List; and

c. Revised TS Bases pages; and

d. 50.59 screening or evaluation if applicable.

One CL individual shall assemble and approve the TS Bases Change Package for distribution and a second CL individual shall perform a peer check to verify completeness of the TS Bases Change Package.

16. After the RA LE notifies CL that SQR/PORC approval of the TS Bases changes has been obtained and that all AT items assigned to track implementation requirements have been completed, CL forwards the TS Bases Change Package to the RA LE as notification of the need to update the onsite TS Bases controlled copies and EDMS, if applicable.

17. RA LE forwards the TS Bases Change Package to Station Records Management as notification of the need to update the onsite TS Bases controlled copies and EDMS, if applicable.

18. Upon completion of updating the onsite TS Bases controlled copies and EDMS (if applicable), Station Records Management Supervisor signs and dates the applicable instruction sheets and returns to corporate licensing per the instructions.

19. RA LE ensures that the documentation required to be maintained as a quality record is provided to Station Records Management for the purpose of record retention.

1.6 ACCEPTANCE CRITERIA Not applicable.

1.7 LCOARS/COMPENSATORY MEASURES Quad Cities Units 1 & 2 8 of 8 Revision QC-TRM-21-001 Technical Requirements Manual

TRM TS Bases Control Program Appendix D An Issue Report may need to be generated to provide proper tracking and resolution of noted problems associated with the implementation of this Program.

The RAM will be responsible for ensuring that Program failures have been resolved.

1.8 REPORTING REQUIREMENTS

NOTE *

TS Bases changes requiring prior NRC approval shall be *

submitted in accordance with Reference 5.

TS Bases changes not requiring prior NRC approval, as described in Section 1.4 of this Program, shall be submitted to the NRC in accordance with 10 CFR 50.71(e).

1.9 CHANGE CONTROL Changes to this Program, other than EDITORIAL CHANGES, shall include a 10 CFR 50.59 REVIEW and a SQR. The SQR composition shall include RA Department in all cases. For a change to this Program, PORC approval from all Stations is required. The concurrence shall be that the other Stations are implementing the same changes or that the changes have been reviewed and determined not to be applicable to the other Stations.

Quad Cities Units 1 & 2 9 of 8 Revision QC-TRM-21-001 Technical Requirements Manual

TRM TS Bases Control Program Appendix D ATTACHMENT A TECHNICAL SPECIFICATIONS BASES CHANGE REQUEST FORM

1. Change Request #: _____________ Affected Bases Section(s): ________________________

2. Description of changes: __________________________________________________________

3. Reason for changes (attach all supporting documentation): _____________________

4. Schedule Requirements:

Outage Related (check one) No Yes, Outage # ___________

Other (explain) ____________________________________________________________________

5. Implementation Requirements (attach additional pages, as necessary):

Identify the impact of the changes on the following:

Affected Aff N/A UFSAR ______________________________________________________________

TS _________________________________________________________________

Technical Requirements Manual ______________________________________

NRC Safety Evaluation ______________________________________________

Fire Protection Report _____________________________________________

NRC Commitments ____________________________________________________

Vendor Documentation _______________________________________________

Special Permits/Licenses ___________________________________________

Procedures _________________________________________________________

Environmental Qualification ________________________________________

Design Basis Documentation _________________________________________

Engineering Calculations ___________________________________________

Drawings/Prints ____________________________________________________

PRA Information ____________________________________________________

Programs ___________________________________________________________

Reportability Manual _______________________________________________

QA Topical Report __________________________________________________

Passport ___________________________________________________________

Pre-Implementation Training Required _______________________________

Maintenance Rule ___________________________________________________

Offsite Dose Calculation Manual ____________________________________

Other ______________________________________________________________

6. Check Che one:

10 CFR 50.59 REVIEW Attached, 10 CFR 50.59 REVIEW #:_________________________

NRC SE Attached, Changes consistent with and entirely bounded by NRC SE EDITORIAL CHANGE, No 10 CFR 50.59 REVIEW required

7. Requestor: ______________________/______________________/________________________

(Signature) (Date) (Department)

8. Requesting Supervisor Approval: _______________________/________________________

(Signature) (Date)

9. PORC Approval Required: Yes No

10. Licensing Engineer Review: _______________________/________________________

(Signature) (Date)

Quad Cities Units 1 & 2 10 of 8 Revision QC-TRM-21-001 Technical Requirements Manual

COLR Quad Cities 1 Revision 16 Core Operating Limits Report For Quad Cities Unit 1 Cycle 27 It,~ 1/....&..- 2021.03.28

'/" 11 :37:38 -05'00' Prepared By: Date: -----

Ryan Pullara - Nuclear Fuels Date: _ _ __

Digitally signed by Staum, Christopher J.

Staum, Christopher J. DN:cn=Staum,ChristopherJ.

Date: 2021.03.28 12:25:21 -05'00' Reviewed By: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ __

Christopher Staum - Engineering Safety Analysis

Iao J*Iay*I Digitally signed by Diao, Jiayi Reviewed By:

D I DN: cn=Diao, Jiayi Date: 2021.03.28 17:51 :23 -os*oo* Date:

Jiayi Diao - Reactor Engineering

(},J,JJ., , i... ].( Digitally signed by Kovacs, Ashley vvo ,. "'cJ 1l ~ DN: cn=Kovacs, Ashley Approved By: Date:2021.03.2820:29:06-05'00' Date:-----

Ashley Kovacs - NF Senior Manager, BWR Cycle Management JOh nSon , NI.Ch OIaS S* Digitally signed by Johnson, Nicholas s.

Date: 2021.03.28 21 :05:57 -05'00' SOR By: Date: _ _ _ __

Station Qualified Reviewer Page 1 of 43

COLR Quad Cities 1 Revision 16 Table of Contents Page Record of Quad Cities 1 Cycle 27 COLR Revisions ........................................................ 3

1. Terms and Definitions ................................................................................................. 5

2. General Information..................................................................................................... 7

3. Average Planar Linear Heat Generation Rate ............................................................. 8

4. Operating Limit Minimum Critical Power Ratio .......................................................... 10

4.1. Manual Flow Control MCPR Limits...................................................................... 10

4.1.1. Power-Dependent MCPR .............................................................................. 10

4.1.2. Flow-Dependent MCPR ................................................................................ 10

4.2. Scram Time ......................................................................................................... 11

4.3. Exposure Dependent MCPR Limits ..................................................................... 12

4.4. Recirculation Pump ASD Settings ....................................................................... 12

5. Linear Heat Generation Rate .................................................................................... 33

6. Control Rod Block Setpoints ..................................................................................... 36

7. Stability Protection Setpoints ..................................................................................... 37

8. Modes of Operation ................................................................................................... 38

9. Methodology .............................................................................................................. 41

10. References .............................................................................................................. 43

Page 2 of 43

COLR Quad Cities 1 Revision 16 Record of Quad Cities 1 Cycle 27 COLR Revisions Revision Description 16 Incorporates MCPR penalties due to Issue Report 04410817 15 Initial issuance for Q1C27 Page 3 of 43

COLR Quad Cities 1 Revision 16 List of Tables Page Table 3-1: MAPLHGR SLO Multipliers.......................................................................................................... 8

Table 3-2: MAPLHGR for ATRIUM 10XM - All but Special Lattices ............................................................ 8

Table 3-3: MAPLHGR for ATRIUM 10XM - Special Lattices ....................................................................... 9

Table 4-1: Scram Times .............................................................................................................................. 11

Table 4-2: Exposure Basis for Transient Analysis ...................................................................................... 12

Table 4-3: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for NSS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX) ........................................................................................... 13

Table 4-4: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for NSS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX) .................................................................. 14

Table 4-5: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for ISS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX) ........................................................................................... 15

Table 4-6: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for ISS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX) .................................................................. 16

Table 4-7: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for TSSS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX) ........................................................................................... 17

Table 4-8: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for TSSS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX) .................................................................. 18

Table 4-9: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for NSS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX) ............................................................................................. 19

Table 4-10: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for NSS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX) .............................................................. 20

Table 4-11: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for ISS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX) ............................................................................................. 21

Table 4-12: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for ISS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX) .............................................................. 22

Table 4-13: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for TSSS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX) ......................................................................................... 23

Table 4-14: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for TSSS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX) ............................................... 24

Table 4-15: ATRIUM 10XM Interior Fuel Bundles SLO MCPRp Limits for NSS Insertion Times, All Exposures ...................................................................................................................................... 25

Table 4-16: ATRIUM 10XM Peripheral Fuel Bundles SLO MCPRp Administrative Values for NSS Insertion Times, All Exposures ..................................................................................................................... 26

Table 4-17: ATRIUM 10XM Interior Fuel Bundles SLO MCPRp Limits for ISS Insertion Times, All Exposures ...................................................................................................................................... 27

Table 4-18: ATRIUM 10XM Peripheral Fuel Bundles SLO MCPRp Administrative Values for ISS Insertion Times, All Exposures ..................................................................................................................... 28

Table 4-19: ATRIUM 10XM Interior Fuel Bundles SLO MCPRp Limits for TSSS Insertion Times, All Exposures ...................................................................................................................................... 29

Table 4-20: ATRIUM 10XM Peripheral Fuel Bundles SLO MCPRp Administrative Values for TSSS Insertion Times, All Exposures ...................................................................................................... 30

Table 4-21: ATRIUM 10XM Interior Fuel Bundles MCPRf Limits ............................................................... 31

Table 4-22: ATRIUM 10XM Peripheral Fuel Bundles MCPRf Administrative Values ................................. 32

Table 5-1: LHGR Limits for ATRIUM 10XM ................................................................................................ 33

Table 5-2: ATRIUM 10XM LHGRFACp Multipliers for All Scram Insertion Times, All Exposures .............. 34

Table 5-3: ATRIUM 10XM LHGRFACf Multipliers for All Cycle 27 Exposures, All EOOS ......................... 35

Table 6-1: Rod Block Monitor Allowable Values ......................................................................................... 36

Table 7-1: OPRM PBDA Trip Settings ........................................................................................................ 37

Table 8-1: Modes of Operation ................................................................................................................... 38

Table 8-2: Core Operational Restrictions for EOOS Conditions ................................................................. 39

Page 4 of 43

COLR Quad Cities 1 Revision 16

1. Terms and Definitions AOO Anticipated operational occurrence ASD Adjustable Speed Drive BOC Beginning of cycle CAVEX Core average exposure CPR Critical power ratio CRWE Control rod withdrawal error EFPD Effective full power day EFPH Effective full power hour EOCLB End of cycle licensing basis EOFPL End of full power life EOFPLB End of full power licensing basis EOOS Equipment out of service FHOOS Feedwater heater out of service FWT Feedwater temperature FRV Feedwater Regulating Valve ICF Increased core flow Interior Fuel Fuel bundles located on the interior of the core indicated by the letter C in Bundles the core map of Reference 10 ISS Intermediate scram speed kW/ft KiloWatts per foot LHGR Linear heat generation rate LHGRFACf Flow dependent LHGR multiplier LHGRFACp Power dependent LHGR multiplier LPRM Local power range monitor MAPLHGR Maximum average planar linear heat generation rate MANFRV1 Manual feedwater regulating valve scenario 1 (1 FRV in manual mode and the position is no more than 3% further open than the position of the FRV in automatic mode)

MANFRV2 Manual feedwater regulating valve scenario 2 (1 FRV in manual mode and the position is greater than 3% further open than the position of the FRV in automatic mode)

MCPR Minimum critical power ratio MCPRf Flow dependent MCPR MCPRp Power dependent MCPR MELLLA Maximum extended load line limit analysis MSIVOOS Main steam isolation valve out of service MWd/MTU MegaWatt days per metric ton Uranium NRC Nuclear Regulatory Commission NSS Nominal scram speed OLMCPR Operating limit minimum critical power ratio OOS Out of service OPRM Oscillation power range monitor PBDA Period based detection algorithm Pbypass Power below which direct scram on TSV/TCV closure is bypassed PCOOS Pressure controller out of service Peripheral Fuel Fuel bundles located on the outer ring of the core indicated by the letter P in Bundles the core map of Reference 10 PLUOOS Power load unbalance out of service SLMCPR Safety limit minimum critical power ratio SLO Single loop operation SRVOOS Safety relief valve out of service TBV Turbine bypass valve TBVOOS Turbine bypass valves out of service TCV Turbine control valve TCV SLOW C TCV slow closure TIP Traversing incore probe TLO Two loop operation TMOL Thermal mechanical operating limit Page 5 of 43

COLR Quad Cities 1 Revision 16 TRM Technical Requirements Manual TSSS Technical Specification scram speed TSV Turbine stop valve Page 6 of 43

COLR Quad Cities 1 Revision 16

2. General Information This report is prepared in accordance with Technical Specification 5.6.5. The Quad Cities Unit 1 Cycle 27 (Q1C27) reload is licensed by Framatome.

Licensed rated thermal power is 2957 MWth. Rated core flow is 98 Mlb/hr. Operation up to 108% rated core flow is licensed for this cycle. For allowed operating regions, see applicable power/flow map.

The licensing analysis supports full power operation to EOCLB (38,023 MWd/MTU CAVEX). Note that this value includes coastdown, where full power operation is not expected. The transient analysis limits are provided for operation up to specific CAVEX exposures as defined in Section 4.3.

Coastdown is defined as operation beyond EOFPL with the plant power gradually reducing as available core reactivity diminishes. The Q1C27 reload analyses do not credit this reduced power during coastdown and the EOCLB limits remain valid for operation up to rated power.

Power and flow dependent limits are listed for various power and flow levels. Linear interpolation on power and flow (as applicable) is to be used to find intermediate values. Linear interpolation is also to be used for table items intentionally left blank, as indicated by boxes which are grayed out.

MCPRp varies with scram speed. All other thermal limits are analyzed to remain valid with NSS, ISS, and TSSS.

LHGRFACf is independent of feedwater temperature and EOOS conditions.

For thermal limit monitoring above 100% rated power or 108% rated core flow, the 100% rated power and the 108% core flow thermal limit values, respectively, shall be used. Steady state operation is not allowed in this region. Limits are provided for transient conditions only.

Page 7 of 43

COLR Quad Cities 1 Revision 16

3. Average Planar Linear Heat Generation Rate Technical Specification Sections 3.2.1 and 3.4.1 Table 3-1 provides the MAPLHGR SLO multipliers for ATRIUM 10XM fuel.

For ATRIUM 10XM fuel, the lattice-specific MAPLHGR limits for TLO can be found in Tables 3-2 and 3-3.

During SLO, the limits in Tables 3-2 and 3-3 are multiplied by the SLO multiplier listed in Table 3-1.

Table 3-1: MAPLHGR SLO Multipliers (References 2 and 7)

Fuel Type Multiplier ATRIUM 10XM 0.80 Table 3-2: MAPLHGR for ATRIUM 10XM - All but Special Lattices (References 2 and 7)

Lattices All Cycle 25 Lattices Cycle 26 Lattices:

XMLCP-0720L-0G0a, XMLCB-0720L-0G0a, XMLCB-4538L-17GV80A, XMLCB-4538L-17GV80, XMLCB-4538L-17G80, XMLCB-4561L-16GV80, XMLCB-4556L-17G80, XMLCB-4642L-13G80, XMLCT-0720L-0G0da, XMLCT-0720L-0G0a, XMLCT-4602L-16GV65A, XMLCT-4602L-16GV65, XMLCT-4721L-12G65 Cycle 27 Lattices:

XMLCP-0720L-0G0a, XMLCB-0720L-0G0a, XMLCB-4430L-16G80, XMLCB-4425L-14GV80, XMLCB-4638L-12G80, XMLCTP-4386L-16G80, XMLCT-4386L-16G80, XMLCT-4401L-14G80, XMLCT-4401L-14G60, XMLCT-4680L-13G60, XMLCT-0720L-0G0a, XMLCT-0720L-0G0a-MOD Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 12.20 20,000 12.20 67,000 7.30 Page 8 of 43

COLR Quad Cities 1 Revision 16 Table 3-3: MAPLHGR for ATRIUM 10XM - Special Lattices (References 2 and 7)

Lattices Cycle 26 Lattices:

XMLCTP-4596L-17G80, XMLCT-4596L-17G80, XMLCTP-4715L-13G80, XMLCT-4715L-13G80 Cycle 27 Lattices:

XMLCTP-4458L-14G80, XMLCT-4458L-14G80, XMLCT-4458L-14G60, XMLCTP-4681L-13G80, XMLCT-4681L-13G80 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 12.20 15,000 12.20 67,000 7.30 Page 9 of 43

COLR Quad Cities 1 Revision 16

4. Operating Limit Minimum Critical Power Ratio Technical Specification Sections 3.2.2, 3.4.1, and 3.7.7 The OLMCPRs for Q1C27 are established so that less than 0.1% of the fuel rods in the core are expected to experience boiling transition during an AOO initiated from rated or off-rated conditions and support current Technical Specifications SLMCPR values (Reference 2).

Tables 4-3, 4-5, 4-7, 4-9, 4-11, 4-13, 4-15, 4-17, 4-19, and 4-21 include MCPR limits for the interior fuel bundles for various specified EOOS conditions. Tables 4-4, 4-6, 4-8, 4-10, 4-12, 4-14, 4-16, 4-18, 4-20, and 4-22 include administrative MCPR values for peripheral fuel bundles for various specified EOOS conditions. The administrative MCPR values are determined by the cycle-specific analyses contained in References 2 and 9. The EOOS conditions separated by / in these tables represent single EOOS conditions and not any combination of conditions. Refer to Section 8 for a detailed explanation of allowable EOOS conditions.

The administrative MCPRp and MCPRf values generated in the tables identified above were calculated using the bounding administrative MFLCPR value found in Table 9 of Reference 9 for all power and flow conditions.

4.1. Manual Flow Control MCPR Limits The OLMCPR is determined for a given power and flow condition by evaluating the power-dependent MCPR and the flow-dependent MCPR and selecting the greater of the two.

4.1.1. Power-Dependent MCPR The OLMCPR as a function of core thermal power (MCPRp) is shown in Tables 4-3 through 4-20. MCPRp limits are dependent on scram times as described in Section 4.2, exposure as described in Section 4.3, FWT, fuel bundle core location, and whether the plant is in TLO or SLO. TLO limits and administrative values for ATRIUM 10XM fuel are given in Tables 4-3 through 4-14 and SLO limits and administrative values for ATRIUM 10XM fuel are given in Tables 4-15 through 4-20.

4.1.2. Flow-Dependent MCPR Table 4-21 gives the OLMCPR limit as a function of the flow (MCPRf) for interior fuel bundles based on the applicable plant condition for ATRIUM 10XM fuel. Table 4-22 gives the OLMCPR administrative values as a function of the flow (MCPRf) for peripheral fuel bundles based on the applicable plant condition for ATRIUM 10XM fuel.

Page 10 of 43

COLR Quad Cities 1 Revision 16 4.2. Scram Time TSSS, ISS, and NSS refer to scram speeds. The scram time values associated with these speeds are shown in Table 4-1. The TSSS scram times shown in Table 4-1 are the same as those specified in the Technical Specifications (Reference 4).

To utilize the OLMCPR limits and administrative values for NSS in Tables 4-3, 4-4, 4-9, 4-10, 4-15, and 4-16, the average control rod insertion time at each control rod insertion fraction must be equal to or less than the NSS time shown in Table 4-1 below.

To utilize the OLMCPR limits and administrative values for ISS in Tables 4-5, 4-6, 4-11, 4-12, 4-17 and 4-18, the average control rod insertion time at each control rod insertion fraction must be equal to or less than the ISS time shown in Table 4-1 below.

The Average Control Rod Insertion Time is defined as the sum of the control rod insertion times of all operable control rods divided by the number of operable control rods. Conservative adjustments to the NSS and ISS scram speeds were made to the analysis inputs to appropriately account for the effects of 1 stuck control rod and one additional control rod that is assumed to fail to scram (Reference 2).

To utilize the OLMCPR limits and administrative values for TSSS in Tables 4-7, 4-8, 4-13, 4-14, 4-19 and 4-20, the control rod insertion time of each operable control rod at each control rod insertion fraction must be less than or equal to the TSSS time shown in Table 4-1. The Technical Specifications allow operation with up to 12 slow and 1 stuck control rod. One additional control rod is assumed to fail to scram for the system transient analyses performed to establish MCPRp limits (Reference 2). Conservative adjustments to the TSSS scram speeds were made to the analysis inputs to appropriately account for the effects of the slow and stuck rods on scram reactivity (Reference 2).

For cases below 38.5% power (Pbypass), the results are relatively insensitive to scram speed, and only TSSS analyses were performed (Reference 2).

Table 4-1: Scram Times (References 2 and 4)

Control Rod Insertion Fraction NSS (seconds) ISS (seconds) TSSS (seconds)

(%)

5 0.324 0.360 0.48 20 0.694 0.720 0.89 50 1.510 1.580 1.98 90 2.670 2.800 3.44 Page 11 of 43

COLR Quad Cities 1 Revision 16 4.3. Exposure Dependent MCPR Limits Exposure-dependent MCPRp limits and administrative values were established to support operation for the entire cycle duration. Note that the thermal limits and administrative values are based on CAVEX. The CAVEX values at which point the MCPRp limits and administrative values are required to be changed are shown in Table 4-2 below. The limits and administrative values at a later exposure range can be used earlier in the cycle as they are the same or more conservative.

Table 4-2: Exposure Basis for Transient Analysis (Reference 2)

Core Average Exposure Description (MWd/MTU)

Design basis rod patterns to EOFPL 37,346

+ 25 EFPD (EOFPLB)

EOCLB - Maximum licensing core 38,023 exposure, including coastdown 4.4. Recirculation Pump ASD Settings Technical Requirement Manual 2.1.a.1 Quad Cities 1 Cycle 27 was analyzed with a slow flow excursion event assuming a failure of the recirculation flow control system such that the core flow increases slowly to the maximum flow physically permitted by the equipment, assumed to be 112% of rated core flow (Reference 2);

therefore the recirculation pump ASD must be set to maintain core flow less than 112%

(109.76 Mlb/hr) for all runout events.

Page 12 of 43

COLR Quad Cities 1 Revision 16 Table 4-3: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for NSS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX)

(References 2 and 7)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.57 2.57 2.24 1.93 1.43 Closed/MSIVOOS/MANFRV1* > 60 2.68 2.68 2.26 60 3.41 3.41 2.62 TBVOOS 1.95 1.43

> 60 3.50 3.50 2.79 60 2.57 2.57 2.24 MANFRV2* 2.03 1.43

> 60 2.68 2.68 2.26 TCV Slow Closure/ 60 2.57 2.57 2.24 2.24 1.72 1.43 PLUOOS/PCOOS > 60 2.68 2.68 2.26 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.76 2.76 2.35 2.08 1.43 Closed/MSIVOOS > 60 2.76 2.76 2.35 60 3.56 3.56 2.74 TBVOOS 2.08 1.43

> 60 3.62 3.62 2.88 TCV Slow Closure/ 60 2.76 2.76 2.35 2.24 1.72 1.43 PLUOOS/PCOOS > 60 2.76 2.76 2.35

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 13 of 43

COLR Quad Cities 1 Revision 16 Table 4-4: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for NSS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX)

(References 2, 7, and 9)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 7.57 7.57 6.60 5.68 4.21 Closed/MSIVOOS/MANFRV1* > 60 7.89 7.89 6.66 60 10.04 10.04 7.72 TBVOOS 5.74 4.21

> 60 10.31 10.31 8.22 60 7.57 7.57 6.60 MANFRV2* 5.98 4.21

> 60 7.89 7.89 6.66 TCV Slow Closure/ 60 7.57 7.57 6.60 6.60 5.07 4.21 PLUOOS/PCOOS > 60 7.89 7.89 6.66 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 8.13 8.13 6.92 6.13 4.21 Closed/MSIVOOS > 60 8.13 8.13 6.92 60 10.49 10.49 8.07 TBVOOS 6.13 4.21

> 60 10.66 10.66 8.48 TCV Slow Closure/ 60 8.13 8.13 6.92 6.60 5.07 4.21 PLUOOS/PCOOS > 60 8.13 8.13 6.92

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 14 of 43

COLR Quad Cities 1 Revision 16 Table 4-5: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for ISS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX)

(References 2 and 7)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.57 2.57 2.24 1.95 1.43 Closed/MSIVOOS/MANFRV1* > 60 2.68 2.68 2.26 60 3.41 3.41 2.62 TBVOOS 1.95 1.43

> 60 3.50 3.50 2.79 60 2.57 2.57 2.24 MANFRV2* 2.03 1.43

> 60 2.68 2.68 2.26 TCV Slow Closure/ 60 2.57 2.57 2.25 2.25 1.72 1.43 PLUOOS/PCOOS > 60 2.68 2.68 2.26 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.76 2.76 2.35 2.09 1.43 Closed/MSIVOOS > 60 2.76 2.76 2.35 60 3.56 3.56 2.74 TBVOOS 2.09 1.43

> 60 3.62 3.62 2.88 TCV Slow Closure/ 60 2.76 2.76 2.35 2.25 1.72 1.43 PLUOOS/PCOOS > 60 2.76 2.76 2.35

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 15 of 43

COLR Quad Cities 1 Revision 16 Table 4-6: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for ISS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX)

(References 2, 7, and 9)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 7.57 7.57 6.60 5.74 4.21 Closed/MSIVOOS/MANFRV1* > 60 7.89 7.89 6.66 60 10.04 10.04 7.72 TBVOOS 5.74 4.21

> 60 10.31 10.31 8.22 60 7.57 7.57 6.60 MANFRV2* 5.98 4.21

> 60 7.89 7.89 6.66 TCV Slow Closure/ 60 7.57 7.57 6.63 6.63 5.07 4.21 PLUOOS/PCOOS > 60 7.89 7.89 6.66 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 8.13 8.13 6.92 6.16 4.21 Closed/MSIVOOS > 60 8.13 8.13 6.92 60 10.49 10.49 8.07 TBVOOS 6.16 4.21

> 60 10.66 10.66 8.48 TCV Slow Closure/ 60 8.13 8.13 6.92 6.63 5.07 4.21 PLUOOS/PCOOS > 60 8.13 8.13 6.92

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 16 of 43

COLR Quad Cities 1 Revision 16 Table 4-7: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for TSSS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX)

(References 2 and 7)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.57 2.57 2.24 2.02 1.43 Closed/MSIVOOS/MANFRV1* > 60 2.68 2.68 2.26 60 3.41 3.41 2.62 TBVOOS 2.04 1.43

> 60 3.50 3.50 2.79 60 2.57 2.57 2.24 MANFRV2* 2.03 1.46

> 60 2.68 2.68 2.26 TCV Slow Closure/ 60 2.57 2.57 2.26 2.26 1.76 1.43 PLUOOS/PCOOS > 60 2.68 2.68 2.26 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.76 2.76 2.35 2.17 1.43 Closed/MSIVOOS > 60 2.76 2.76 2.35 60 3.56 3.56 2.74 TBVOOS 2.18 1.44

> 60 3.62 3.62 2.88 TCV Slow Closure/ 60 2.76 2.76 2.35 2.26 1.76 1.43 PLUOOS/PCOOS > 60 2.76 2.76 2.35

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 17 of 43

COLR Quad Cities 1 Revision 16 Table 4-8: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for TSSS Insertion Times, BOC to EOFPLB (37,346 MWd/MTU CAVEX)

(References 2, 7, and 9)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 7.57 7.57 6.60 5.95 4.21 Closed/MSIVOOS/MANFRV1* > 60 7.89 7.89 6.66 60 10.04 10.04 7.72 TBVOOS 6.01 4.21

> 60 10.31 10.31 8.22 60 7.57 7.57 6.60 MANFRV2* 5.98 4.30

> 60 7.89 7.89 6.66 TCV Slow Closure/ 60 7.57 7.57 6.66 6.66 5.18 4.21 PLUOOS/PCOOS > 60 7.89 7.89 6.66 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 8.13 8.13 6.92 6.39 4.21 Closed/MSIVOOS > 60 8.13 8.13 6.92 60 10.49 10.49 8.07 TBVOOS 6.42 4.24

> 60 10.66 10.66 8.48 TCV Slow Closure/ 60 8.13 8.13 6.92 6.66 5.18 4.21 PLUOOS/PCOOS > 60 8.13 8.13 6.92

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 18 of 43

COLR Quad Cities 1 Revision 16 Table 4-9: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for NSS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX)

(References 2 and 7)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.57 2.57 2.24 1.93 1.43 Closed/MSIVOOS/MANFRV1* > 60 2.68 2.68 2.26 60 3.41 3.41 2.62 TBVOOS 1.95 1.43

> 60 3.50 3.50 2.79 60 2.57 2.57 2.24 MANFRV2* 2.03 1.43

> 60 2.68 2.68 2.26 TCV Slow Closure/ 60 2.57 2.57 2.24 2.24 1.72 1.43 PLUOOS/PCOOS > 60 2.68 2.68 2.26 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.76 2.76 2.35 2.08 1.43 Closed/MSIVOOS > 60 2.76 2.76 2.35 60 3.56 3.56 2.74 TBVOOS 2.08 1.43

> 60 3.62 3.62 2.88 TCV Slow Closure/ 60 2.76 2.76 2.35 2.24 1.72 1.43 PLUOOS/PCOOS > 60 2.76 2.76 2.35

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 19 of 43

COLR Quad Cities 1 Revision 16 Table 4-10: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for NSS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX)

(References 2, 7, and 9)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 7.57 7.57 6.60 5.68 4.21 Closed/MSIVOOS/MANFRV1* > 60 7.89 7.89 6.66 60 10.04 10.04 7.72 TBVOOS 5.74 4.21

> 60 10.31 10.31 8.22 60 7.57 7.57 6.60 MANFRV2* 5.98 4.21

> 60 7.89 7.89 6.66 TCV Slow Closure/ 60 7.57 7.57 6.60 6.60 5.07 4.21 PLUOOS/PCOOS > 60 7.89 7.89 6.66 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 8.13 8.13 6.92 6.13 4.21 Closed/MSIVOOS > 60 8.13 8.13 6.92 60 10.49 10.49 8.07 TBVOOS 6.13 4.21

> 60 10.66 10.66 8.48 TCV Slow Closure/ 60 8.13 8.13 6.92 6.60 5.07 4.21 PLUOOS/PCOOS > 60 8.13 8.13 6.92

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 20 of 43

COLR Quad Cities 1 Revision 16 Table 4-11: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for ISS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX)

(References 2 and 7)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.57 2.57 2.24 1.95 1.43 Closed/MSIVOOS/MANFRV1* > 60 2.68 2.68 2.26 60 3.41 3.41 2.62 TBVOOS 1.95 1.43

> 60 3.50 3.50 2.79 60 2.57 2.57 2.24 MANFRV2* 2.03 1.43

> 60 2.68 2.68 2.26 TCV Slow Closure/ 60 2.57 2.57 2.25 2.25 1.72 1.43 PLUOOS/PCOOS > 60 2.68 2.68 2.26 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.76 2.76 2.35 2.09 1.43 Closed/MSIVOOS > 60 2.76 2.76 2.35 60 3.56 3.56 2.74 TBVOOS 2.09 1.43

> 60 3.62 3.62 2.88 TCV Slow Closure/ 60 2.76 2.76 2.35 2.25 1.72 1.43 PLUOOS/PCOOS > 60 2.76 2.76 2.35

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 21 of 43

COLR Quad Cities 1 Revision 16 Table 4-12: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for ISS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX)

(References 2, 7, and 9)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 7.57 7.57 6.60 5.74 4.21 Closed/MSIVOOS/MANFRV1* > 60 7.89 7.89 6.66 60 10.04 10.04 7.72 TBVOOS 5.74 4.21

> 60 10.31 10.31 8.22 60 7.57 7.57 6.60 MANFRV2* 5.98 4.21

> 60 7.89 7.89 6.66 TCV Slow Closure/ 60 7.57 7.57 6.63 6.63 5.07 4.21 PLUOOS/PCOOS > 60 7.89 7.89 6.66 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 8.13 8.13 6.92 6.16 4.21 Closed/MSIVOOS > 60 8.13 8.13 6.92 60 10.49 10.49 8.07 TBVOOS 6.16 4.21

> 60 10.66 10.66 8.48 TCV Slow Closure/ 60 8.13 8.13 6.92 6.63 5.07 4.21 PLUOOS/PCOOS > 60 8.13 8.13 6.92

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 22 of 43

COLR Quad Cities 1 Revision 16 Table 4-13: ATRIUM 10XM Interior Fuel Bundles TLO MCPRp Limits for TSSS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX)

(References 2 and 7)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.57 2.57 2.24 2.02 1.43 Closed/MSIVOOS/MANFRV1* > 60 2.68 2.68 2.26 60 3.41 3.41 2.62 TBVOOS 2.04 1.43

> 60 3.50 3.50 2.79 60 2.57 2.57 2.24 MANFRV2* 2.03 1.46

> 60 2.68 2.68 2.26 TCV Slow Closure/ 60 2.57 2.57 2.26 2.26 1.76 1.43 PLUOOS/PCOOS > 60 2.68 2.68 2.26 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 2.76 2.76 2.35 2.17 1.43 Closed/MSIVOOS > 60 2.76 2.76 2.35 60 3.56 3.56 2.74 TBVOOS 2.18 1.44

> 60 3.62 3.62 2.88 TCV Slow Closure/ 60 2.76 2.76 2.35 2.26 1.76 1.43 PLUOOS/PCOOS > 60 2.76 2.76 2.35

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 23 of 43

COLR Quad Cities 1 Revision 16 Table 4-14: ATRIUM 10XM Peripheral Fuel Bundles TLO MCPRp Administrative Values for TSSS Insertion Times, EOFPLB to EOCLB (38,023 MWd/MTU CAVEX)

(References 2, 7, and 9)

Nominal FWT Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 7.57 7.57 6.60 5.95 4.21 Closed/MSIVOOS/MANFRV1* > 60 7.89 7.89 6.66 60 10.04 10.04 7.72 TBVOOS 6.01 4.21

> 60 10.31 10.31 8.22 60 7.57 7.57 6.60 MANFRV2* 5.98 4.30

> 60 7.89 7.89 6.66 TCV Slow Closure/ 60 7.57 7.57 6.66 6.66 5.18 4.21 PLUOOS/PCOOS > 60 7.89 7.89 6.66 FHOOS Core Core Power (% rated)

Flow EOOS Condition

(% 0 25 38.5 > 38.5 75 100 rated)

Base/TCV Stuck 60 8.13 8.13 6.92 6.39 4.21 Closed/MSIVOOS > 60 8.13 8.13 6.92 60 10.49 10.49 8.07 TBVOOS 6.42 4.24

> 60 10.66 10.66 8.48 TCV Slow Closure/ 60 8.13 8.13 6.92 6.66 5.18 4.21 PLUOOS/PCOOS > 60 8.13 8.13 6.92

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 24 of 43

COLR Quad Cities 1 Revision 16 Table 4-15: ATRIUM 10XM Interior Fuel Bundles SLO MCPRp Limits for NSS Insertion Times, All Exposures (Reference 2)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.59 2.59 2.26 2.13 2.10 Closed/MSIVOOS TBVOOS 3.43 3.43 2.64 2.13 2.10 TCV Slow Closure/ 2.59 2.59 2.26 2.26 2.10 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.78 2.78 2.37 2.13 2.10 Closed/MSIVOOS TBVOOS 3.58 3.58 2.76 2.13 2.10 TCV Slow Closure/ 2.78 2.78 2.37 2.26 2.10 PLUOOS/PCOOS Page 25 of 43

COLR Quad Cities 1 Revision 16 Table 4-16: ATRIUM 10XM Peripheral Fuel Bundles SLO MCPRp Administrative Values for NSS Insertion Times, All Exposures (References 2 and 9)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 7.63 7.63 6.66 6.27 6.19 Closed/MSIVOOS TBVOOS 10.10 10.10 7.78 6.27 6.19 TCV Slow Closure/ 7.63 7.63 6.66 6.66 6.19 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 8.19 8.19 6.98 6.27 6.19 Closed/MSIVOOS TBVOOS 10.54 10.54 8.13 6.27 6.19 TCV Slow Closure/ 8.19 8.19 6.98 6.66 6.19 PLUOOS/PCOOS Page 26 of 43

COLR Quad Cities 1 Revision 16 Table 4-17: ATRIUM 10XM Interior Fuel Bundles SLO MCPRp Limits for ISS Insertion Times, All Exposures (Reference 2)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.59 2.59 2.26 2.13 2.10 Closed/MSIVOOS TBVOOS 3.43 3.43 2.64 2.13 2.10 TCV Slow Closure/ 2.59 2.59 2.27 2.27 2.11 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.78 2.78 2.37 2.13 2.10 Closed/MSIVOOS TBVOOS 3.58 3.58 2.76 2.13 2.10 TCV Slow Closure/ 2.78 2.78 2.37 2.27 2.11 PLUOOS/PCOOS Page 27 of 43

COLR Quad Cities 1 Revision 16 Table 4-18: ATRIUM 10XM Peripheral Fuel Bundles SLO MCPRp Administrative Values for ISS Insertion Times, All Exposures (References 2 and 9)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 7.63 7.63 6.66 6.27 6.19 Closed/MSIVOOS TBVOOS 10.10 10.10 7.78 6.27 6.19 TCV Slow Closure/ 7.63 7.63 6.69 6.69 6.21 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 8.19 8.19 6.98 6.27 6.19 Closed/MSIVOOS TBVOOS 10.54 10.54 8.13 6.27 6.19 TCV Slow Closure/ 8.19 8.19 6.98 6.69 6.21 PLUOOS/PCOOS Page 28 of 43

COLR Quad Cities 1 Revision 16 Table 4-19: ATRIUM 10XM Interior Fuel Bundles SLO MCPRp Limits for TSSS Insertion Times, All Exposures (Reference 2)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.59 2.59 2.26 2.13 2.10 Closed/MSIVOOS TBVOOS 3.43 3.43 2.64 2.13 2.10 TCV Slow Closure/ 2.59 2.59 2.28 2.28 2.13 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.78 2.78 2.37 2.19 2.10 Closed/MSIVOOS TBVOOS 3.58 3.58 2.76 2.20 2.10 TCV Slow Closure/ 2.78 2.78 2.37 2.28 2.13 PLUOOS/PCOOS Page 29 of 43

COLR Quad Cities 1 Revision 16 Table 4-20: ATRIUM 10XM Peripheral Fuel Bundles SLO MCPRp Administrative Values for TSSS Insertion Times, All Exposures (References 2 and 9)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 7.63 7.63 6.66 6.27 6.19 Closed/MSIVOOS TBVOOS 10.10 10.10 7.78 6.27 6.19 TCV Slow Closure/ 7.63 7.63 6.72 6.72 6.27 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 8.19 8.19 6.98 6.45 6.19 Closed/MSIVOOS TBVOOS 10.54 10.54 8.13 6.48 6.19 TCV Slow Closure/ 8.19 8.19 6.98 6.72 6.27 PLUOOS/PCOOS Page 30 of 43

COLR Quad Cities 1 Revision 16 Table 4-21: ATRIUM 10XM Interior Fuel Bundles MCPRf Limits (References 2 and 7)

EOOS Condition* Core Flow (% rated) MCPRf Limit Base Case / FHOOS / PCOOS / 0 1.64 PLUOOS / TCV Slow Closure /

35 1.64 PLUOOS and PCOOS in TLO and SLO / MANFRV1 / MANFRV2 108 1.18 0 1.72 Any Scenario** with One MSIVOOS 35 1.72 108 1.18 0 1.82 Any Scenario** with TBVOOS 35 1.82 108 1.35 0 1.64 Any Scenario** with 1 Stuck 35 1.64 Closed TCV/TSV 108 1.18

See Section 8 for further operating restrictions.

- Any Scenario includes any other combination of allowable EOOS conditions that is not otherwise covered by this table.

Note that the MCPRf limits for any scenario with 1 stuck closed TCV/TSV are identical to base case MCPRf limits. This is reflected in the thermal limit sets presented in Table 8-1.

Page 31 of 43

COLR Quad Cities 1 Revision 16 Table 4-22: ATRIUM 10XM Peripheral Fuel Bundles MCPRf Administrative Values (References 2, 7, and 9)

EOOS Condition* Core Flow (% rated) MCPRf Limit Base Case / FHOOS / PCOOS / 0 4.83 PLUOOS / TCV Slow Closure /

35 4.83 PLUOOS and PCOOS in TLO and SLO / MANFRV1 / MANFRV2 108 3.48 0 5.07 Any Scenario** with One MSIVOOS 35 5.07 108 3.48 0 5.36 Any Scenario** with TBVOOS 35 5.36 108 3.98 0 4.83 Any Scenario** with 1 Stuck 35 4.83 Closed TCV/TSV 108 3.48

See Section 8 for further operating restrictions.

- Any Scenario includes any other combination of allowable EOOS conditions that is not otherwise covered by this table.

Note that the MCPRf limits for any scenario with 1 stuck closed TCV/TSV are identical to base case MCPRf limits. This is reflected in the thermal limit sets presented in Table 8-1.

Page 32 of 43

COLR Quad Cities 1 Revision 16

5. Linear Heat Generation Rate Technical Specification Sections 3.2.3, 3.4.1, and 3.7.7 The TMOL at rated conditions for the ATRIUM 10XM fuel is established in terms of the maximum LHGR as a function of peak pellet exposure. The LHGR limits for ATRIUM 10XM fuel are presented in Table 5-1.

The power- and flow-dependent LHGR multipliers (LHGRFACp and LHGRFACf) are applied directly to the LHGR limits to protect against fuel melting and overstraining of the cladding during an AOO (Reference 2). In all conditions, the margin to the LHGR limits is determined by applying the lowest multiplier from the applicable LHGRFACp and LHGRFACf multipliers for the power/flow statepoint of interest to the steady state LHGR limit (Reference 2).

LHGRFACp and LHGRFACf multipliers were established to support base case and EOOS conditions for all Cycle 27 exposures and scram speeds. The LHGRFACp multipliers for ATRIUM 10XM are presented in Table 5-2. The LHGRFACf multipliers for ATRIUM 10XM are presented in Table 5-3. The LHGRFACp and LHGRFACf multipliers are applicable in both TLO and SLO.

The EOOS conditions separated by / in these tables represent single EOOS conditions and not any combination of conditions.

Table 5-1: LHGR Limits for ATRIUM 10XM (References 2 and 7)

Peak Pellet Exposure LHGR Limit (MWd/MTU) (kW/ft) 0 14.1 18,900 14.1 74,400 7.4 Page 33 of 43

COLR Quad Cities 1 Revision 16 Table 5-2: ATRIUM 10XM LHGRFACp Multipliers for All Scram Insertion Times, All Exposures (References 2 and 7)

Nominal FWT Core Core Power (% rated)

EOOS Condition Flow (%

rated) 0 25 38.5 > 38.5 50 80 100 Base/TCV Stuck 60 0.52 0.52 0.58 0.64 0.66 0.88 1.00 Closed/MSIVOOS > 60 0.50 0.50 0.58 60 0.38 0.38 0.52 TBVOOS 0.64 0.66 0.88 1.00

> 60 0.36 0.36 0.50 TCV Slow 60 0.52 0.52 0.58 Closure/ 0.64 0.66 0.88 1.00 PLUOOS/PCOOS > 60 0.50 0.50 0.58 60 0.52 0.52 0.58 MANFRV1* 0.62 0.64 0.84 1.00

> 60 0.50 0.50 0.58 60 0.52 0.52 0.58 MANFRV2* 0.60 0.64 0.80 0.96

> 60 0.50 0.50 0.58 FHOOS Core Core Power (% rated)

EOOS Condition Flow (%

rated) 0 25 38.5 > 38.5 50 80 100 Base/TCV Stuck 60 0.48 0.48 0.52 0.64 0.66 0.88 1.00 Closed/MSIVOOS > 60 0.46 0.46 0.52 60 0.36 0.36 0.49 TBVOOS 0.64 0.66 0.88 1.00

> 60 0.34 0.34 0.46 TCV Slow 60 0.48 0.48 0.52 Closure/ 0.64 0.66 0.88 1.00 PLUOOS/PCOOS > 60 0.46 0.46 0.52

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%.

Page 34 of 43

COLR Quad Cities 1 Revision 16 Table 5-3: ATRIUM 10XM LHGRFACf Multipliers for All Cycle 27 Exposures, All EOOS (References 2 and 7)

Core Flow (% rated) LHGRFACf 0.0 0.57 30.0 0.57 80.0 1.00 108.0 1.00 Page 35 of 43

COLR Quad Cities 1 Revision 16

6. Control Rod Block Setpoints Technical Specification Sections 3.3.2.1 and 3.4.1 The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown in Table 6-1.

Table 6-1: Rod Block Monitor Allowable Values (Reference 3)

ROD BLOCK MONITOR UPSCALE TRIP FUNCTION ALLOWABLE VALUE Two Recirculation Loop 0.65 Wd + 56.1%

Operation Single Recirculation Loop 0.65 Wd + 51.4%

Operation Wd - percent of recirculation loop drive flow required to produce a rated core flow of 98.0 Mlb/hr.

The setpoint may be lower/higher and will still comply with the CRWE analysis because CRWE is analyzed unblocked (Reference 2).

Page 36 of 43

COLR Quad Cities 1 Revision 16

7. Stability Protection Setpoints Technical Specifications Section 3.3.1.3 The OPRM PBDA Trip Settings are provided in Table 7-1.

Table 7-1: OPRM PBDA Trip Settings (References 2 and 8)

Corresponding Maximum PBDA Trip Amplitude Setpoint (Sp)

Confirmation Count Setpoint (Np) 1.10 13 The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system (Methodology 2).

The OPRM PBDA trip settings are based, in part, on the cycle specific OLMCPR and the power/flow-dependent MCPR limits. Any change to the OLMCPR values and/or the power/flow-dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA trip settings.

The OPRM PBDA trip settings are applicable when the OPRM system is declared operable, and the associated Technical Specifications are implemented.

Page 37 of 43

COLR Quad Cities 1 Revision 16

8. Modes of Operation The allowed modes of operation with combinations of equipment out-of-service are as described in Table 8-1. The EOOS conditions separated by / in these tables represent single EOOS conditions and not combinations of conditions.

Note that the following EOOS options have operational restrictions: all SLO, all EOOS options with 1 TCV/TSV stuck closed, MSIVOOS, MANFRV1, and MANFRV2. See Table 8-2 for specific restrictions.

Table 8-1: Modes of Operation (References 2 and 7)

EOOS Option Thermal Limit Set BASE CASE Base Case 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS TBVOOS due to Main Generator Load Reject PLUOOS/TCV SLOW C Trip Relays OOS 3/4 TLO for Nominal FWT*

TBVOOS TBVOOS 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS BASE CASE 1 TCV/TSV Stuck Closed 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS MSIVOOS One MSIVOOS 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS PLUOOS/TCV SLOW C TCV Slow Closure 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS PLUOOS/TCV SLOW C PLUOOS 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS PLUOOS/TCV SLOW C PCOOS 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS PLUOOS/TCV SLOW C PLUOOS and 1 TCV/TSV Stuck Closed 3/4 TLO for Nominal FWT or FHOOS 3/4 SLO for Nominal FWT**

PLUOOS/TCV SLOW C PCOOS and PLUOOS 3/4 TLO for Nominal FWT or FHOOS 3/4 SLO for Nominal FWT**

PLUOOS/TCV SLOW C PCOOS and 1 TCV/TSV Stuck Closed 3/4 TLO for Nominal FWT or FHOOS 3/4 SLO for Nominal FWT**

MANFRV1 MANFRV1 3/4 TLO for Nominal FWT***

MANFRV2 MANFRV2 3/4 TLO for Nominal FWT***

SLO and FHOOS cannot be applied for the case of TBVOOS due to main generator load reject trip relays OOS.

- FHOOS cannot be applied to SLO for the cases of PLUOOS and 1 TCV/TSV Stuck Closed, for the case of PCOOS and PLUOOS, or for the case of PCOOS and 1 TCV/TSV Stuck Closed.

- - SLO and FHOOS cannot be applied for the case of MANFRV1 or MANFRV2.

Page 38 of 43

COLR Quad Cities 1 Revision 16 Table 8-2: Core Operational Restrictions for EOOS Conditions (References 2 and 7)

Core Flow (% of Core Thermal Power (%

EOOS Condition Rod Line (%)

Rated) of Rated Power) 1 TCV/TSV Stuck Closed PCOOS and 1 TCV/TSV Stuck Closed N/A < 75 < 80 PLUOOS and 1 TCV/TSV Stuck Closed One MSIVOOS N/A < 75 N/A SLO < 51 < 50 N/A MANFRV1/MANFRV2 N/A >38.5 (Pbypass) N/A All requirements for all applicable conditions listed in Table 8-2 MUST be met.

Page 39 of 43

COLR Quad Cities 1 Revision 16 Common Notes:

1. All modes are allowed for operation at MELLLA, ICF (up to 108% rated core flow), and coastdown subject to the power restrictions in Table 8-2 (Reference 2). The licensing analysis supports full power operation to EOCLB (38,023 MWd/MTU CAVEX). Note that this value includes coastdown, where full power operation is not expected. Each OOS Option may be combined with each of the following conditions (Reference 2):

a. Up to 40% of the TIP channels OOS

b. Up to 50% of the LPRMs OOS

c. An LPRM calibration frequency of up to 2500 EFPH

2. Nominal FWT results are valid for application within a +10°F/-30ºF temperature band around the nominal FWT curve (Reference 2). For operation outside of nominal FWT, a FWT reduction of up to 120°F is supported for all FHOOS conditions listed in Table 8-1 for cycle operation through EOCLB (Reference 2). At lower power levels, the feedwater temperature reduction is less (Reference 2). Per Reference 6, there is a restriction which requires that for a FWT reduction greater than 100°F, operation needs to be restricted to less than the 100% load line. For a feedwater temperature reduction of between 30ºF and 120°F, the FHOOS limits should be applied.

3. The base case and EOOS limits and multipliers support operation with 8 of the 9 turbine bypass valves operational (i.e., one bypass valve out of service) with the exception of the TBVOOS condition in which all bypass valves are inoperable (Reference 2). Use of the response curve in TRM Appendix H supports operation with any single TBV OOS. TRM Appendix H facilitates analysis with one valve OOS in that the capacity at 0.45 seconds from start of TSV closure is equivalent to the total capacity with eight out of the nine valves in service (Reference 5). The analyses also support Turbine Bypass flow of 29.6% of vessel rated steam flow (Reference 5), equivalent to one TBV OOS (or partially closed TBVs equivalent to one closed TBV), if the assumed opening profile for the remaining TBVs is met. If the opening profile is NOT met, or if the TBV system CANNOT pass an equivalent of 29.6% of vessel rated steam flow, utilize the TBVOOS condition.

4. For the TBVOOS condition, analyses assume zero TBVs trip open and zero TBVs are available for pressure control during the slow portion of the transient analysis (Reference 5). Steam relief capacity is defined in Reference 5.

5. Failure of the main generator load reject trip relays to actuate (e.g., main generator load reject trip relays OOS) will render the turbine bypass valve system inoperable during load reject events (Reference 2). Operation with the main generator load reject trip relays out of service in TLO is supported by the TCV slow closure limits (Reference 2), meaning that, in accordance with Table 8-1, the PLUOOS/TCV SLOW C thermal limit set should be applied. This is applicable between 25% and 50% of rated thermal power.

6. Additional operating restrictions apply for both the MANFRV1 and MANFRV2 EOOS options as outlined in Section 1 of Reference 7. These operating restrictions apply when a Feedwater Regulating Valve is placed in manual for conditions as described in the terms and definitions. Only one Feedwater Regulating Valve can be placed in manual. The additional EOOS conditions that are supported with MANFRV1 and MANFRV2 consist of 1 SRVOOS, 40% of TIP channels OOS and 50%

of the LPRMs out-of-service. Other conditions associated with base case conditions, such as the feedwater temperature band, the pressure band, single and three-element level control, dome and turbine pressure control, and operation with 1 TBV OOS, are supported as discussed in section 5.1 of Reference 2.

7. The operating administrative values for MCPRp and MCPRf are generated to support the recent lost part documented in IR 04410817. If operation will occur using the lost part penalty on limits not listed in the COLR, prior consultation with Nuclear Fuels should occur. Furthermore, this penalty may be removed if all risk of flow blockage from this lost part is removed.

Page 40 of 43

COLR Quad Cities 1 Revision 16

9. Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. GE Topical Report NEDE-24011-P-A, Revision 14, General Electric Standard Application for Reactor Fuel (GESTAR), June 2000.

2. GE Topical Report NEDO-32465-A, Revision 0, Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications, August 1996.

3. Westinghouse Topical Report CENPD-300-P-A, Revision 0, Reference Safety Report for Boiling Water Reactor Reload Fuel, July 1996.

4. Westinghouse Report WCAP-16081-P-A, Revision 0, 10x10 SVEA Fuel Critical Power Experiments and CPR Correlation: SVEA-96 Optima2, March 2005.

5. Westinghouse Report WCAP-15682-P-A, Revision 0, Westinghouse BWR ECCS Evaluation Model:

Supplement 2 to Code Description, Qualification and Application, April 2003.

6. Westinghouse Report WCAP-16078-P-A, Revision 0, Westinghouse BWR ECCS Evaluation Model:

Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel, November 2004.

7. Westinghouse Topical Report WCAP-15836-P-A, Revision 0, Fuel Rod Design Methods for Boiling Water Reactors - Supplement 1, April 2006.

8. Westinghouse Topical Report WCAP-15942-P-A, Revision 0, Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors Supplement 1 to CENPD-287, March 2006.

9. Westinghouse Topical Report CENPD-390-P-A, Revision 0, The Advanced PHOENIX and POLCA Codes for Nuclear Design of Boiling Water Reactors, December 2000.

10. Westinghouse Report WCAP-16865-P-A, Revision 1, "Westinghouse BWR ECCS Evaluation Model Updates: Supplement 4 to Code Description, Qualification and Application," October 2011.

11. Exxon Nuclear Company Report XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, March 1984.

12. Advanced Nuclear Fuels Corporation Report ANF-89-98(P)(A), Revision 1 and Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Designs, May 1995.

13. Siemens Power Corporation Report EMF-85-74(P), Revision 0 Supplement 1 (P)(A) and Supplement 2 (P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model, February 1998.

14. AREVA NP Topical Report BAW-10247PA, Revision 0, Realistic Thermal-Mechanical Fuel Rod Methodology for Boiling Water Reactors, February 2008.

15. Exxon Nuclear Company Topical Report XN-NF-80-19(P)(A), Volume 1 Revision 0 and Supplements 1 and 2, Exxon Nuclear Methodology for Boiling Water Reactors - Neutronic Methods for Design and Analysis, March 1983.

Page 41 of 43

COLR Quad Cities 1 Revision 16

16. Exxon Nuclear Company Topical Report XN-NF-80-19(P)(A), Volume 4 Revision 1, Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology for BWR Reloads, June 1986.

17. Exxon Nuclear Company Topical Report XN-NF-80-19(P)(A), Volume 3 Revision 2, Exxon Nuclear Methodology for Boiling Water Reactors, THERMEX: Thermal Limits Methodology Summary Description, January 1987.

18. Siemens Power Corporation Topical Report EMF-2158(P)(A), Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, October 1999.

19. Siemens Power Corporation Report EMF-2245(P)(A), Revision 0, Application of Siemens Power Corporations Critical Power Correlations to Co-Resident Fuel, August 2000.

20. AREVA NP Report EMF-2209(P)(A), Revision 3, SPCB Critical Power Correlation, September 2009.

21. AREVA Topical Report ANP-10298P-A, Revision 1, ACE/ATRIUM 10XM Critical Power Correlation, March 2014.

22. AREVA NP Topical Report ANP-10307PA, Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, June 2011.

23. Exxon Nuclear Company Report XN-NF-84-105(P)(A), Volume 1 Revision 0 and Volume 1 Supplements 1 and 2, XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis, February 1987.

24. Advanced Nuclear Fuels Corporation Report ANF-913(P)(A), Volume 1 Revision 1 and Volume 1 Supplements 2, 3, and 4, COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses, August 1990.

25. Framatome ANP Report EMF-2361(P)(A), Revision 0, EXEM BWR-2000 ECCS Evaluation Model, May 2001.

26. Siemens Power Corporation Report EMF-2292 (P)(A), Revision 0, ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients, September 2000.

27. Framatome ANP Topical Report ANF-1358(P)(A), Revision 3, The Loss of Feedwater Heating Transient in Boiling Water Reactors, September 2005.

28. Siemens Power Corporation Topical Report EMF-CC-074(P)(A), Volume 4 Revision 0, BWR Stability Analysis: Assessment of STAIF with Input from MICROBURN-B2, August 2000.

Page 42 of 43

COLR Quad Cities 1 Revision 16

10. References

1. Exelon Generation Company, LLC and MidAmerican Energy Company, Docket No. 50-254, Quad Cities Nuclear Power Station, Unit 1, Renewed Facility Operating License, No. DPR-29.

2. Framatome Report, ANP-3896P, Revision 0, Quad Cities Unit 1 Cycle 27 Reload Safety Analysis, January 2021.

3. GE Document, GE DRF C51-00217-01, Instrument Setpoint Calculation Nuclear Instrumentation, Rod Block Monitor, Commonwealth Edison Company, Quad Cities 1 & 2, December 14, 1999. (Attachment A to Exelon Design Analysis, QDC-0700-I-1419, Revision 0).

4. Exelon Technical Specifications for Quad Cities 1 and 2, Table 3.1.4-1, Control Rod Scram Times.

5. Exelon TODI, NF205719, Revision 0, Quad Cities Unit 1 Cycle 27 Plant Parameters Document, July 10, 2020.

6. Exelon Letter, NF-MW:02-0081, Approval of GE Evaluation of Dresden and Quad Cities Extended Final Feedwater Temperature Reduction, Carlos de la Hoz to Doug Wise and Alex Misak, August 27, 2002.

7. Framatome Document, FS1-0054583, Revision 1.0, Supplemental Information for QCI1-27 Reload Safety Analysis Report - Operation with 1 Manual FRV, February 2, 2021.

8. Exelon TODI, NF210042, Revision 0, Q1C27 OPRM Setpoint Analysis Request, January 20, 2021.

9. Exelon Technical Evaluation, EC #633922-000, Q1R26 Lost Parts Evaluation for IR 04410817, March 27, 2021.

10. Exelon TODI, NF210212, Revision 0, Quad Cities Unit 1 Central and Peripheral Orifice Locations, March 27, 2021.

Page 43 of 43

COLR Quad Cities 2 Revision 14 Core Operating Limits Report For Quad Cities Unit 2 Cycle 26 Prepared By: ~ ~~ Date: 4/10/2020 R~lara - Nuclear Fuels

~~

Reviewed By: _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date: 4/10/2020 Ann Hopkins - Nuclear Fuels

~=___>________

Reviewed By: _ _ __ _ _

Christopher Staum - Engineering Safety Analysis Date: 4/10/2020 Reviewed By: ~ ~---- Date: 4/10/2020 Nicholas J o h n s ~ r Engineering Approved By: ~ A~

Kristin McCoske~ Manager, BWR Cycle Management Date: 4/10/2020 SQR By: Date: 4/11/2020 Station Q u a l i f ~ e r Page 1 of 72

COLR Quad Cities 2 Revision 14 Table of Contents Page Record of Quad Cities 2 Cycle 26 COLR Revisions ..................................................................................... 3

1. Terms and Definitions ............................................................................................................................... 6

2. General Information .................................................................................................................................. 7

3. Average Planar Linear Heat Generation Rate .......................................................................................... 8

4. Operating Limit Minimum Critical Power Ratio ....................................................................................... 37

4.1. Manual Flow Control MCPR Limits .................................................................................................. 37

4.1.1. Power-Dependent MCPR .......................................................................................................... 37

4.1.2. Flow-Dependent MCPR ............................................................................................................. 37

4.2. Scram Time ...................................................................................................................................... 38

4.3. Exposure Dependent MCPR Limits.................................................................................................. 39

4.4. Recirculation Pump ASD Settings .................................................................................................... 39

5. Linear Heat Generation Rate .................................................................................................................. 59

6. Control Rod Block Setpoints ................................................................................................................... 65

7. Stability Protection Setpoints .................................................................................................................. 66

8. Modes of Operation................................................................................................................................. 67

9. Methodology ............................................................................................................................................ 70

10. References ............................................................................................................................................ 72

Page 2 of 72

COLR Quad Cities 2 Revision 14 Record of Quad Cities 2 Cycle 26 COLR Revisions Revision Description 14 Revised to account for changes due to the core redesign which replaces fuel bundle QBF166 with QBE010.

13 Initial issuance for Q2C26 Page 3 of 72

COLR Quad Cities 2 Revision 14 List of Tables Page Table 3-1: MAPLHGR SLO Multipliers.......................................................................................................... 8

Table 3-2: MAPLHGR for OPTIMA2 Lattices 91 and 98 .............................................................................. 8

Table 3-3: MAPLHGR for OPTIMA2 Lattice 152 .......................................................................................... 9

Table 3-4: MAPLHGR for OPTIMA2 Lattice 153 ........................................................................................ 10

Table 3-5: MAPLHGR for OPTIMA2 Lattice 154 ........................................................................................ 11

Table 3-6: MAPLHGR for OPTIMA2 Lattice 155 ........................................................................................ 12

Table 3-7: MAPLHGR for OPTIMA2 Lattice 156 ........................................................................................ 13

Table 3-8: MAPLHGR for OPTIMA2 Lattice 157 ........................................................................................ 14

Table 3-9: MAPLHGR for OPTIMA2 Lattice 158 ........................................................................................ 15

Table 3-10: MAPLHGR for OPTIMA2 Lattice 171 ...................................................................................... 16

Table 3-11: MAPLHGR for OPTIMA2 Lattice 172 ...................................................................................... 17

Table 3-12: MAPLHGR for OPTIMA2 Lattice 173 ...................................................................................... 18

Table 3-13: MAPLHGR for OPTIMA2 Lattice 174 ...................................................................................... 19

Table 3-14: MAPLHGR for OPTIMA2 Lattice 175 ...................................................................................... 20

Table 3-15: MAPLHGR for OPTIMA2 Lattice 176 ...................................................................................... 21

Table 3-16: MAPLHGR for OPTIMA2 Lattice 177 ...................................................................................... 22

Table 3-17: MAPLHGR for OPTIMA2 Lattice 178 ...................................................................................... 23

Table 3-18: MAPLHGR for OPTIMA2 Lattice 179 ...................................................................................... 24

Table 3-19: MAPLHGR for OPTIMA2 Lattice 180 ...................................................................................... 25

Table 3-20: MAPLHGR for OPTIMA2 Lattice 181 ...................................................................................... 26

Table 3-21: MAPLHGR for OPTIMA2 Lattice 182 ...................................................................................... 27

Table 3-22: MAPLHGR for OPTIMA2 Lattice 183 ...................................................................................... 28

Table 3-23: MAPLHGR for OPTIMA2 Lattice 184 ...................................................................................... 29

Table 3-24: MAPLHGR for OPTIMA2 Lattice 185 ...................................................................................... 30

Table 3-25: MAPLHGR for OPTIMA2 Lattice 186 ...................................................................................... 31

Table 3-26: MAPLHGR for OPTIMA2 Lattice 187 ...................................................................................... 32

Table 3-27: MAPLHGR for OPTIMA2 Lattice 188 ...................................................................................... 33

Table 3-28: MAPLHGR for OPTIMA2 Lattice 189 ...................................................................................... 34

Table 3-29: MAPLHGR for OPTIMA2 Lattice 190 ...................................................................................... 35

Table 3-30: MAPLHGR for ATRIUM 10XM Except for Special Lattices ..................................................... 36

Table 3-31: MAPLHGR for ATRIUM 10XM Special Lattices ...................................................................... 36

Table 4-1: Scram Times .............................................................................................................................. 38

Table 4-2: Exposure Basis for Transient Analysis ...................................................................................... 39

Table 4-3: ATRIUM 10XM TLO MCPRp Limits for NSS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX)........................................................................................................................ 40

Table 4-4: ATRIUM 10XM TLO MCPRp Limits for ISS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX)........................................................................................................................ 41

Table 4-5: ATRIUM 10XM TLO MCPRp Limits for TSSS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX)........................................................................................................................ 42

Table 4-6: ATRIUM 10XM TLO MCPRp Limits for NSS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)........................................................................................................................ 43

Table 4-7: ATRIUM 10XM TLO MCPRp Limits for ISS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)........................................................................................................................ 44

Table 4-8: ATRIUM 10XM TLO MCPRp Limits for TSSS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)........................................................................................................................ 45

Table 4-9: OPTIMA2 TLO MCPRp Limits for NSS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX) .......................................................................................................................................... 46

Table 4-10: OPTIMA2 TLO MCPRp Limits for ISS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX) .......................................................................................................................................... 47

Table 4-11: OPTIMA2 TLO MCPRp Limits for TSSS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX) .......................................................................................................................................... 48

Table 4-12: OPTIMA2 TLO MCPRp Limits for NSS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)........................................................................................................................ 49

Page 4 of 72

COLR Quad Cities 2 Revision 14 Table 4-13: OPTIMA2 TLO MCPRp Limits for ISS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)........................................................................................................................ 50

Table 4-14: OPTIMA2 TLO MCPRp Limits for TSSS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)........................................................................................................................ 51

Table 4-15: ATRIUM 10XM SLO MCPRp Limits for NSS Insertion Times, All Exposures ......................... 52

Table 4-16: ATRIUM 10XM SLO MCPRp Limits for ISS Insertion Times, All Exposures ........................... 53

Table 4-17: ATRIUM 10XM SLO MCPRp Limits for TSSS Insertion Times, All Exposures ....................... 54

Table 4-18: OPTIMA2 SLO MCPRp Limits for NSS Insertion Times, All Exposures .................................. 55

Table 4-19: OPTIMA2 SLO MCPRp Limits for ISS Insertion Times, All Exposures ................................... 56

Table 4-20: OPTIMA2 SLO MCPRp Limits for TSSS Insertion Times, All Exposures ................................ 57

Table 4-21: ATRIUM 10XM and OPTIMA2 MCPRf Limits, All Insertion Times, All Exposures .................. 58

Table 5-1: LHGR Limits for OPTIMA2 Lattices 91, 98, 152, 153, 154, 155, 171, 172, 173, 174, 178, 179, 180, 181, 185, 186, 187, 188, 189, and 190 .................................................................................. 60

Table 5-2: LHGR Limits for OPTIMA2 Lattices 156, 157, and 158 ............................................................. 60

Table 5-3: LHGR Limits for OPTIMA2 Lattices 176, 177, 183 and 184 ...................................................... 60

Table 5-4: LHGR Limits for OPTIMA2 Lattices 175 and 182 ...................................................................... 61

Table 5-5: LHGR Limits for ATRIUM 10XM ................................................................................................ 61

Table 5-6: ATRIUM 10XM LHGRFACp Multipliers, All Insertion Times, All Exposures .............................. 62

Table 5-7: OPTIMA2 LHGRFACp Multipliers, All Insertion Times, All Exposures ...................................... 63

Table 5-8: ATRIUM 10XM LHGRFACf Multipliers, All Insertion Times, All Exposures, All EOOS ............. 64

Table 5-9: OPTIMA2 LHGRFACf Multipliers, All Insertion Times, All Exposures, All EOOS ..................... 64

Table 6-1: Rod Block Monitor Upscale Instrumentation Setpoints ............................................................. 65

Table 7-1: OPRM PBDA Trip Settings ........................................................................................................ 66

Table 8-1: Modes of Operation ................................................................................................................... 67

Table 8-2: Core Operational Restrictions for EOOS Conditions ................................................................. 68

Page 5 of 72

COLR Quad Cities 2 Revision 14

1. Terms and Definitions AOO Anticipated operational occurrence ASD Adjustable Speed Drive BOC Beginning of cycle CAVEX Core average exposure CPR Critical power ratio CRWE Control rod withdrawal error EFPD Effective full power day EFPH Effective full power hour EOCLB End of cycle licensing basis EOFPL End of full power life EOFPLB End of full power licensing basis EOOS Equipment out of service FHOOS Feedwater heater out of service FWT Feedwater temperature ICF Increased core flow ISS Intermediate scram speed kW/ft KiloWatts per foot LHGR Linear heat generation rate LHGRFACf Flow dependent LHGR multiplier LHGRFACp Power dependent LHGR multiplier LPRM Local power range monitor MAPLHGR Maximum average planar linear heat generation rate MANFRV1 Manual feedwater regulating valve scenario 1 (1 FRV in manual mode and the position is no more than 3% further open than the position of the FRV in automatic mode)

MANFRV2 Manual feedwater regulating valve scenario 2 (1 FRV in manual mode and the position is greater than 3% further open than the position of the FRV in automatic mode)

MCPR Minimum critical power ratio MCPRf Flow dependent MCPR MCPRp Power dependent MCPR MELLLA Maximum extended load line limit analysis MSIVOOS Main steam isolation valve out of service MWd/MTU MegaWatt days per metric ton Uranium NRC Nuclear Regulatory Commission NSS Nominal scram speed OLMCPR Operating limit minimum critical power ratio OOS Out of service OPRM Oscillation power range monitor PBDA Period based detection algorithm Pbypass Power below which direct scram on TSV/TCV closure is bypassed PCOOS Pressure controller out of service PLUOOS Power load unbalance out of service SLMCPR Safety limit minimum critical power ratio SLO Single loop operation SRVOOS Safety relief valve out of service TBV Turbine bypass valve TBVOOS Turbine bypass valves out of service TCV Turbine control valve TIP Traversing incore probe TLO Two loop operation TMOL Thermal mechanical operating limit TRM Technical Requirements Manual TSSS Technical Specification scram speed TSV Turbine stop valve Page 6 of 72

COLR Quad Cities 2 Revision 14

2. General Information This report is prepared in accordance with Technical Specification 5.6.5. The Q2C26 reload is licensed by Framatome. However, some legacy analyses by Westinghouse are still applicable for OPTIMA2 fuel as described in Reference 2.

Licensed rated thermal power is 2957 MWth. Rated core flow is 98 Mlb/hr. Operation up to 108% rated core flow is licensed for this cycle. For allowed operating regions, see applicable power/flow map.

The licensing analysis supports full power operation to EOCLB (38,401 MWd/MTU CAVEX). Note that this value includes coastdown, where full power operation is not expected. The transient analysis limits are provided for operation up to specific CAVEX exposures as defined in Section 4.3.

Coastdown is defined as operation beyond EOFPL (37,679 MWd/MTU CAVEX) with the plant power gradually reducing as available core reactivity diminishes. The Q2C26 reload analyses do not credit this reduced power during coastdown and the EOCLB limits remain valid for operation up to rated power.

Power and flow dependent limits are listed for various power and flow levels. Linear interpolation on power and flow (as applicable) is to be used to find intermediate values. Linear interpolation is also to be used for table items intentionally left blank, as indicated by boxes which are grayed out.

MCPRp for both fuel types varies with scram speed. All other thermal limits are analyzed to remain valid with NSS, ISS, and TSSS.

LHGRFACf is independent of feedwater temperature and EOOS conditions.

For thermal limit monitoring above 100% rated power or 108% rated core flow, the 100% rated power or the 108% core flow thermal limit values, respectively, shall be used. Steady state operation is not allowed in this region. Limits are provided for transient conditions only.

Page 7 of 72

COLR Quad Cities 2 Revision 14

3. Average Planar Linear Heat Generation Rate Technical Specifications Sections 3.2.1 and 3.4.1 Table 3-1 provides the MAPLHGR SLO multipliers for ATRIUM 10XM and OPTIMA2 fuel. For OPTIMA2 natural uranium lattices, TLO and SLO MAPLHGR values are provided in Table 3-2. The limits provided in Table 3-2 were selected to be the more limiting of the limits provided in References 5 and 13. For all other OPTIMA2 lattices, lattice-specific MAPLHGR values for TLO are provided in Tables 3-3 through 3-29.

For ATRIUM 10XM fuel, the lattice-specific MAPLHGR values for TLO can be found in Tables 3-30 through 3-31.

During SLO, the limits in Tables 3-3 through 3-31 are multiplied by the fuel-specific SLO multiplier listed in Table 3-1. The ATRIUM 10XM multiplier may be applied to OPTIMA2 for SLO conditions, as the ATRIUM 10XM multiplier is more limiting.

Table 3-1: MAPLHGR SLO Multipliers (References 2, 5, 13, and 16)

Fuel Type Multiplier ATRIUM 10XM 0.80 OPTIMA2 0.86 Table 3-2: MAPLHGR for OPTIMA2 Lattices 91 and 98 (References 5, 6, 13, and 14)

All OPTIMA2 Bundles Lattices 91: Opt2-B0.71 98: Opt2-T0.71 Average Planar Exposure TLO and SLO MAPLHGR (MWd/MTU) (kW/ft) 0 7.50 75,000 7.50 Page 8 of 72

COLR Quad Cities 2 Revision 14 Table 3-3: MAPLHGR for OPTIMA2 Lattice 152 (References 13 and 14)

Bundle Opt2-3.97-14GZ7.50/5.50-4GZ5.50 (UK23)

Lattice 152: Opt2-B4.26-14G7.50-4G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 8.89 2,500 9.17 5,000 9.26 7,500 9.39 10,000 9.72 12,000 9.88 15,000 9.93 17,000 9.92 20,000 9.95 22,000 9.97 24,000 9.98 30,000 9.72 36,000 9.59 42,000 9.48 50,000 9.40 60,000 9.54 72,000 9.81 75,000 9.81 Page 9 of 72

COLR Quad Cities 2 Revision 14 Table 3-4: MAPLHGR for OPTIMA2 Lattice 153 (References 13 and 14)

Bundle Opt2-3.97-14GZ7.50/5.50-4GZ5.50 (UK23)

Lattice 153: Opt2-B4.40-14G7.50-4G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 8.84 2,500 9.13 5,000 9.17 7,500 9.25 10,000 9.39 12,000 9.46 15,000 9.56 17,000 9.62 20,000 9.73 22,000 9.69 24,000 9.65 30,000 9.60 36,000 9.54 42,000 9.51 50,000 9.51 60,000 9.60 72,000 9.85 75,000 9.85 Page 10 of 72

COLR Quad Cities 2 Revision 14 Table 3-5: MAPLHGR for OPTIMA2 Lattice 154 (References 13 and 14)

Bundle Opt2-3.97-14GZ7.50/5.50-4GZ5.50 (UK23)

Lattice 154: Opt2-BE4.49-14G7.50-4G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.05 2,500 9.40 5,000 9.38 7,500 9.34 10,000 9.50 12,000 9.57 15,000 9.68 17,000 9.74 20,000 9.84 22,000 9.80 24,000 9.76 30,000 9.69 36,000 9.66 42,000 9.58 50,000 9.56 60,000 9.60 72,000 9.89 75,000 9.89 Page 11 of 72

COLR Quad Cities 2 Revision 14 Table 3-6: MAPLHGR for OPTIMA2 Lattice 155 (References 13 and 14)

Bundle Opt2-3.97-14GZ7.50/5.50-4GZ5.50 (UK23)

Lattice 155: Opt2-M4.49-14G7.50-4G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.02 2,500 9.37 5,000 9.41 7,500 9.35 10,000 9.52 12,000 9.59 15,000 9.69 17,000 9.76 20,000 9.84 22,000 9.80 24,000 9.75 30,000 9.69 36,000 9.65 42,000 9.58 50,000 9.51 60,000 9.58 72,000 9.90 75,000 9.90 Page 12 of 72

COLR Quad Cities 2 Revision 14 Table 3-7: MAPLHGR for OPTIMA2 Lattice 156 (References 13 and 14)

Bundle Opt2-3.97-14GZ7.50/5.50-4GZ5.50 (UK23)

Lattice 156: Opt2-ME4.45-14G7.50-4G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.16 2,500 9.52 5,000 9.52 7,500 9.51 10,000 9.68 12,000 9.76 15,000 9.88 17,000 10.00 20,000 9.98 22,000 9.98 24,000 9.93 30,000 9.88 36,000 9.83 42,000 9.72 50,000 9.64 60,000 9.63 72,000 10.16 75,000 10.16 Page 13 of 72

COLR Quad Cities 2 Revision 14 Table 3-8: MAPLHGR for OPTIMA2 Lattice 157 (References 13 and 14)

Bundle Opt2-3.97-14GZ7.50/5.50-4GZ5.50 (UK23)

Lattice 157: Opt2-T4.45-18G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.28 2,500 9.63 5,000 9.46 7,500 9.53 10,000 9.66 12,000 9.87 15,000 10.18 17,000 10.05 20,000 9.99 22,000 9.97 24,000 9.93 30,000 9.88 36,000 9.79 42,000 9.76 50,000 9.65 60,000 9.71 72,000 10.20 75,000 10.20 Page 14 of 72

COLR Quad Cities 2 Revision 14 Table 3-9: MAPLHGR for OPTIMA2 Lattice 158 (References 13 and 14)

Bundle Opt2-3.97-14GZ7.50/5.50-4GZ5.50 (UK23)

Lattice 158: Opt2-T4.47-14G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.96 2,500 10.26 5,000 10.10 7,500 10.01 10,000 9.92 12,000 10.01 15,000 10.06 17,000 10.03 20,000 10.02 22,000 10.01 24,000 9.97 30,000 9.93 36,000 9.87 42,000 9.76 50,000 9.65 60,000 9.70 72,000 10.22 75,000 10.22 Page 15 of 72

COLR Quad Cities 2 Revision 14 Table 3-10: MAPLHGR for OPTIMA2 Lattice 171 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50-2G5.50 (UN24)

Lattice 171: Opt2-B4.30-16G7.50-2G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.15 2,500 9.49 5,000 9.44 7,500 9.58 10,000 9.81 12,000 9.96 15,000 10.19 17,000 10.33 20,000 10.54 22,000 10.55 24,000 10.56 30,000 10.27 36,000 10.14 42,000 10.02 50,000 9.92 75,000 9.92 Page 16 of 72

COLR Quad Cities 2 Revision 14 Table 3-11: MAPLHGR for OPTIMA2 Lattice 172 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50-2G5.50 (UN24)

Lattice 172: Opt2-B4.43-16G7.50-2G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.08 2,500 9.43 5,000 9.35 7,500 9.31 10,000 9.44 12,000 9.53 15,000 9.69 17,000 9.77 20,000 9.93 22,000 10.06 24,000 10.18 30,000 10.15 36,000 10.11 42,000 10.06 50,000 10.04 75,000 10.04 Page 17 of 72

COLR Quad Cities 2 Revision 14 Table 3-12: MAPLHGR for OPTIMA2 Lattice 173 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50-2G5.50 (UN24)

Lattice 173: Opt2-BE4.52-16G7.50-2G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.11 2,500 9.43 5,000 9.36 7,500 9.34 10,000 9.51 12,000 9.61 15,000 9.78 17,000 9.87 20,000 10.03 22,000 10.19 24,000 10.30 30,000 10.24 36,000 10.20 42,000 10.13 50,000 10.07 75,000 10.07 Page 18 of 72

COLR Quad Cities 2 Revision 14 Table 3-13: MAPLHGR for OPTIMA2 Lattice 174 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50-2G5.50 (UN24)

Lattice 174: Opt2-M4.52-16G7.50-2G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.09 2,500 9.43 5,000 9.34 7,500 9.34 10,000 9.52 12,000 9.63 15,000 9.79 17,000 9.88 20,000 10.05 22,000 10.21 24,000 10.29 30,000 10.23 36,000 10.19 42,000 10.12 50,000 10.03 75,000 10.03 Page 19 of 72

COLR Quad Cities 2 Revision 14 Table 3-14: MAPLHGR for OPTIMA2 Lattice 175 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50-2G5.50 (UN24)

Lattice 175: Opt2-ME4.48-16G7.50-2G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.22 2,500 9.57 5,000 9.47 7,500 9.49 10,000 9.66 12,000 9.78 15,000 9.95 17,000 10.07 20,000 10.39 22,000 10.53 24,000 10.48 30,000 10.43 36,000 10.37 42,000 10.26 50,000 10.13 75,000 10.13 Page 20 of 72

COLR Quad Cities 2 Revision 14 Table 3-15: MAPLHGR for OPTIMA2 Lattice 176 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50-2G5.50 (UN24)

Lattice 176: Opt2-T4.48-16G7.50-2G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.27 2,500 9.60 5,000 9.49 7,500 9.47 10,000 9.61 12,000 9.76 15,000 9.92 17,000 10.06 20,000 10.42 22,000 10.50 24,000 10.46 30,000 10.42 36,000 10.36 42,000 10.22 50,000 10.10 75,000 10.10 Page 21 of 72

COLR Quad Cities 2 Revision 14 Table 3-16: MAPLHGR for OPTIMA2 Lattice 177 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50-2G5.50 (UN24)

Lattice 177: Opt2-T4.48-18G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.35 2,500 9.70 5,000 9.61 7,500 9.58 10,000 9.75 12,000 9.96 15,000 10.29 17,000 10.50 20,000 10.53 22,000 10.51 24,000 10.47 30,000 10.42 36,000 10.34 42,000 10.31 50,000 10.18 75,000 10.18 Page 22 of 72

COLR Quad Cities 2 Revision 14 Table 3-17: MAPLHGR for OPTIMA2 Lattice 178 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50 (UO24)

Lattice 178: Opt2-B4.30-16G7.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.44 2,500 9.71 5,000 9.58 7,500 9.71 10,000 9.88 12,000 9.99 15,000 10.21 17,000 10.33 20,000 10.48 22,000 10.50 24,000 10.52 30,000 10.26 36,000 10.12 42,000 10.01 50,000 9.92 75,000 9.92 Page 23 of 72

COLR Quad Cities 2 Revision 14 Table 3-18: MAPLHGR for OPTIMA2 Lattice 179 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50 (UO24)

Lattice 179: Opt2-B4.43-16G7.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.38 2,500 9.62 5,000 9.50 7,500 9.44 10,000 9.52 12,000 9.57 15,000 9.69 17,000 9.77 20,000 9.92 22,000 10.05 24,000 10.16 30,000 10.13 36,000 10.08 42,000 10.04 50,000 10.03 75,000 10.03 Page 24 of 72

COLR Quad Cities 2 Revision 14 Table 3-19: MAPLHGR for OPTIMA2 Lattice 180 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50 (UO24)

Lattice 180: Opt2-BE4.53-16G7.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.42 2,500 9.70 5,000 9.56 7,500 9.49 10,000 9.60 12,000 9.65 15,000 9.79 17,000 9.87 20,000 10.02 22,000 10.17 24,000 10.28 30,000 10.23 36,000 10.19 42,000 10.12 50,000 10.06 75,000 10.06 Page 25 of 72

COLR Quad Cities 2 Revision 14 Table 3-20: MAPLHGR for OPTIMA2 Lattice 181 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50 (UO24)

Lattice 181: Opt2-M4.53-16G7.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.40 2,500 9.71 5,000 9.59 7,500 9.51 10,000 9.62 12,000 9.67 15,000 9.80 17,000 9.88 20,000 10.04 22,000 10.19 24,000 10.28 30,000 10.22 36,000 10.19 42,000 10.11 50,000 10.03 75,000 10.03 Page 26 of 72

COLR Quad Cities 2 Revision 14 Table 3-21: MAPLHGR for OPTIMA2 Lattice 182 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50 (UO24)

Lattice 182: Opt2-ME4.49-16G7.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.55 2,500 9.86 5,000 9.73 7,500 9.66 10,000 9.76 12,000 9.82 15,000 9.96 17,000 10.06 20,000 10.36 22,000 10.51 24,000 10.47 30,000 10.42 36,000 10.37 42,000 10.25 50,000 10.10 75,000 10.10 Page 27 of 72

COLR Quad Cities 2 Revision 14 Table 3-22: MAPLHGR for OPTIMA2 Lattice 183 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50 (UO24)

Lattice 183: Opt2-T4.49-16G7.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.61 2,500 9.89 5,000 9.74 7,500 9.65 10,000 9.72 12,000 9.81 15,000 9.92 17,000 10.05 20,000 10.39 22,000 10.47 24,000 10.45 30,000 10.42 36,000 10.35 42,000 10.21 50,000 10.09 75,000 10.09 Page 28 of 72

COLR Quad Cities 2 Revision 14 Table 3-23: MAPLHGR for OPTIMA2 Lattice 184 (References 5 and 6)

Bundle Opt2-4.00-16GZ7.50/5.50 (UO24)

Lattice 184: Opt2-T4.49-16G5.50 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.69 2,500 10.00 5,000 9.87 7,500 9.76 10,000 9.86 12,000 10.01 15,000 10.28 17,000 10.48 20,000 10.55 22,000 10.54 24,000 10.50 30,000 10.45 36,000 10.39 42,000 10.31 50,000 10.17 75,000 10.17 Page 29 of 72

COLR Quad Cities 2 Revision 14 Table 3-24: MAPLHGR for OPTIMA2 Lattice 185 (References 5 and 6)

Bundle Opt2-4.17-2GZ6.00-10G6.00 (UP24)

Lattice 185: Opt2-B4.59-12G6.00 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.71 2,500 9.89 5,000 9.80 7,500 9.77 10,000 9.77 12,000 9.82 15,000 9.87 17,000 9.92 20,000 10.00 22,000 10.07 24,000 10.09 30,000 10.12 36,000 10.12 42,000 10.13 50,000 10.12 75,000 10.12 Page 30 of 72

COLR Quad Cities 2 Revision 14 Table 3-25: MAPLHGR for OPTIMA2 Lattice 186 (References 5 and 6)

Bundle Opt2-4.17-2GZ6.00-10G6.00 (UP24)

Lattice 186: Opt2-BE4.67-12G6.00 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.75 2,500 9.96 5,000 9.82 7,500 9.86 10,000 9.99 12,000 9.91 15,000 9.96 17,000 10.03 20,000 10.11 22,000 10.18 24,000 10.20 30,000 10.25 36,000 10.27 42,000 10.20 50,000 10.15 75,000 10.15 Page 31 of 72

COLR Quad Cities 2 Revision 14 Table 3-26: MAPLHGR for OPTIMA2 Lattice 187 (References 5 and 6)

Bundle Opt2-4.17-2GZ6.00-10G6.00 (UP24)

Lattice 187: Opt2-M4.67-12G6.00 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.74 2,500 9.97 5,000 9.80 7,500 9.89 10,000 10.01 12,000 9.92 15,000 9.98 17,000 10.04 20,000 10.18 22,000 10.18 24,000 10.21 30,000 10.26 36,000 10.28 42,000 10.20 50,000 10.15 75,000 10.15 Page 32 of 72

COLR Quad Cities 2 Revision 14 Table 3-27: MAPLHGR for OPTIMA2 Lattice 188 (References 5 and 6)

Bundle Opt2-4.17-2GZ6.00-10G6.00 (UP24)

Lattice 188: Opt2-ME4.65-12G6.00 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 9.96 2,500 10.19 5,000 10.03 7,500 10.06 10,000 10.15 12,000 10.10 15,000 10.19 17,000 10.29 20,000 10.41 22,000 10.47 24,000 10.47 30,000 10.50 36,000 10.50 42,000 10.44 50,000 10.28 75,000 10.28 Page 33 of 72

COLR Quad Cities 2 Revision 14 Table 3-28: MAPLHGR for OPTIMA2 Lattice 189 (References 5 and 6)

Bundle Opt2-4.17-2GZ6.00-10G6.00 (UP24)

Lattice 189: Opt2-T4.65-12G6.00 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 10.02 2,500 10.25 5,000 10.09 7,500 10.11 10,000 10.09 12,000 10.07 15,000 10.18 17,000 10.27 20,000 10.43 22,000 10.47 24,000 10.48 30,000 10.51 36,000 10.49 42,000 10.42 50,000 10.24 75,000 10.24 Page 34 of 72

COLR Quad Cities 2 Revision 14 Table 3-29: MAPLHGR for OPTIMA2 Lattice 190 (References 5 and 6)

Bundle Opt2-4.17-2GZ6.00-10G6.00 (UP24)

Lattice 190: Opt2-T4.64-10G6.00 Avg. Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 10.42 2,500 10.60 5,000 10.39 7,500 10.48 10,000 10.30 12,000 10.27 15,000 10.28 17,000 10.32 20,000 10.41 22,000 10.46 24,000 10.46 30,000 10.48 36,000 10.49 42,000 10.43 50,000 10.28 75,000 10.28 Page 35 of 72

COLR Quad Cities 2 Revision 14 Table 3-30: MAPLHGR for ATRIUM 10XM Except for Special Lattices (References 2, 10, 11, and 16)

Bundles All Cycle 25 and Cycle 26 Bundles Lattices All Cycle 25 Lattices XMLCP-0720L-0G0a, XMLCB-0720L-0G0a, XMLCB-4494L-15G80, XMLCB-4491L-13G80, XMLCB-4491L-13G70, XMLCB-4633L-13G80, XMLCT-0720L-0G0a-MOD, XMLCT-0720L-0G0a, XMLCT-4428L-13G50, XMLCT-4399L-17GV80, XMLCTP-4399L-17GV80, XMLCT-4711L-12G70 Average Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 12.20 20,000 12.20 67,000 7.30 Table 3-31: MAPLHGR for ATRIUM 10XM Special Lattices (References 2, 10, 11, and 16)

Bundles XMLC-3988B-15GV80, XMLC-4160B-13GV80 Lattices XMLCT-4424L-15G70, XMLCT-4424L-15G80, XMLCTP-4424L-15G80, XMLCT-4705L-13G80, XMLCTP-4705L-13G80 Average Planar Exposure TLO MAPLHGR (MWd/MTU) (kW/ft) 0 12.20 15,000 12.20 67,000 7.30 Page 36 of 72

COLR Quad Cities 2 Revision 14

4. Operating Limit Minimum Critical Power Ratio Technical Specification Sections 3.2.2, 3.4.1, and 3.7.7 The OLMCPRs for Q2C26 were established so that less than 0.1% of the fuel rods in the core are expected to experience boiling transition during an AOO initiated from rated or off-rated conditions and are based on the Technical Specifications SLMCPR values (Reference 2).

Tables 4-3 through 4-21 include MCPR limits for various specified EOOS conditions. The EOOS conditions separated by / in these tables represent single EOOS conditions and not any combination of conditions.

Refer to Section 8 for a detailed explanation of allowable combined EOOS conditions.

4.1. Manual Flow Control MCPR Limits The OLMCPR is determined for a given power and flow condition by evaluating the power-dependent MCPR and the flow-dependent MCPR and selecting the greater of the two.

4.1.1. Power-Dependent MCPR The OLMCPR as a function of core thermal power (MCPRp) is shown in Tables 4-3 through 4-20. MCPRp limits are dependent on scram times as described in Section 4.2, exposure as described in Section 4.3, fuel type, FWT, and whether the plant is in TLO or SLO. TLO limits for ATRIUM 10XM fuel are given in Tables 4-3 through 4-8 and SLO limits for ATRIUM 10XM are given in Tables 4-15 through 4-17. TLO limits for OPTIMA2 fuel are given in Tables 4-9 through 4-14 and SLO limits for OPTIMA2 fuel are given in Tables 4-18 through 4-20.

4.1.2. Flow-Dependent MCPR Table 4-21 gives the OLMCPR limit as a function of the flow (MCPRf) based on the applicable plant condition. These values are applicable to both ATRIUM 10XM and OPTIMA2 fuel.

Page 37 of 72

COLR Quad Cities 2 Revision 14 4.2. Scram Time TSSS, ISS, and NSS refer to scram speeds. The scram time values associated with these speeds are shown in Table 4-1. The TSSS scram times shown in Table 4-1 are the same as those specified in the Technical Specifications (Reference 4).

To utilize the OLMCPR limits for NSS in Tables 4-3, 4-6, 4-9, 4-12, 4-15, and 4-18, the average control rod insertion time at each control rod insertion fraction must be equal to or less than the NSS time shown in Table 4-1 below.

To utilize the OLMCPR limits for ISS in Tables 4-4, 4-7, 4-10, 4-13, 4-16, and 4-19, the average control rod insertion time at each control rod insertion fraction must be equal to or less than the ISS time shown in Table 4-1 below.

The Average Control Rod Insertion Time is defined as the sum of the control rod insertion times of all operable control rods divided by the number of operable control rods. Conservative adjustments to the NSS and ISS scram speeds were made to the analysis inputs to appropriately account for the effects of 1 stuck control rod and one additional control rod that is assumed to fail to scram (Reference 2).

To utilize the OLMCPR limits for TSSS in Tables 4-5, 4-8, 4-11, 4-14, 4-17, and 4-20, the control rod insertion time of each operable control rod at each control rod insertion fraction must be less than or equal to the TSSS time shown in Table 4-1 below. The Technical Specifications allow operation with up to 12 slow and 1 stuck control rod. One additional control rod is assumed to fail to scram for the system transient analyses performed to establish MCPRp limits (Reference 2).

Conservative adjustments to the TSSS scram speeds were made to the analysis inputs to appropriately account for the effects of the slow and stuck rods on scram reactivity (Reference 2).

For cases below 38.5% power (Pbypass), the results are relatively insensitive to scram speed, and only TSSS analyses were performed (Reference 2).

Table 4-1: Scram Times (References 2 and 4)

Control Rod Insertion NSS (seconds) ISS (seconds) TSSS (seconds)

Fraction (%)

5 0.324 0.36 0.48 20 0.694 0.72 0.89 50 1.510 1.58 1.98 90 2.670 2.80 3.44 Page 38 of 72

COLR Quad Cities 2 Revision 14 4.3. Exposure Dependent MCPR Limits Exposure-dependent MCPRp limits were established to support operation for the entire cycle duration. Note that the thermal limits are based on CAVEX. The CAVEX values at which point the MCPRp limits are required to be changed are shown in Table 4-2 below. The limits at a later exposure range can be used earlier in the cycle as they are the same or more conservative.

Although MCPRp values are the same for each CAVEX breakpoint, the values are split up based on CAVEX to maintain consistency with previous cycles format.

Table 4-2: Exposure Basis for Transient Analysis (Reference 2)

CAVEX Description (MWd/MTU)

Design basis rod patterns to EOFPL 37,679

+ 25 EFPD (EOFPLB)

EOCLB - Maximum licensing core 38,401 exposure, including coastdown 4.4. Recirculation Pump ASD Settings Technical Requirement Manual 2.1.a.1 Quad Cities 2 Cycle 26 was analyzed with a slow flow excursion event assuming a failure of the recirculation flow control system such that the core flow increases slowly to the maximum flow physically permitted by the equipment, assumed to be 112% of rated core flow (Reference 2);

therefore, the recirculation pump ASD must be set to maintain core flow less than 112%

(109.76 Mlb/hr) for all runout events.

Page 39 of 72

COLR Quad Cities 2 Revision 14 Table 4-3: ATRIUM 10XM TLO MCPRp Limits for NSS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.51 2.51 2.20 1.88 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.66 2.66 2.28 60 3.38 3.38 2.62 TBVOOS 1.94 1.45

> 60 3.48 3.48 2.71 60 2.51 2.51 2.20 MANFRV2* 1.99 1.45

> 60 2.66 2.66 2.28 TCV Slow Closure/ 60 2.51 2.51 2.26 2.26 1.89 1.45 PLUOOS/PCOOS > 60 2.66 2.66 2.28 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.70 2.70 2.31 2.03 1.45 Closed/MSIVOOS > 60 2.70 2.70 2.31 60 3.50 3.50 2.68 TBVOOS 2.03 1.45

> 60 3.58 3.58 2.79 TCV Slow Closure/ 60 2.70 2.70 2.31 2.26 1.89 1.45 PLUOOS/PCOOS > 60 2.70 2.70 2.31

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 40 of 72

COLR Quad Cities 2 Revision 14 Table 4-4: ATRIUM 10XM TLO MCPRp Limits for ISS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.51 2.51 2.20 1.89 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.66 2.66 2.28 60 3.38 3.38 2.62 TBVOOS 1.94 1.45

> 60 3.48 3.48 2.71 60 2.51 2.51 2.20 MANFRV2* 1.99 1.45

> 60 2.66 2.66 2.28 TCV Slow Closure/ 60 2.51 2.51 2.27 2.27 1.90 1.45 PLUOOS/PCOOS > 60 2.66 2.66 2.28 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.70 2.70 2.31 2.03 1.45 Closed/MSIVOOS > 60 2.70 2.70 2.31 60 3.50 3.50 2.68 TBVOOS 2.03 1.45

> 60 3.58 3.58 2.79 TCV Slow Closure/ 60 2.70 2.70 2.31 2.27 1.90 1.45 PLUOOS/PCOOS > 60 2.70 2.70 2.31

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 41 of 72

COLR Quad Cities 2 Revision 14 Table 4-5: ATRIUM 10XM TLO MCPRp Limits for TSSS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.51 2.51 2.20 1.95 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.66 2.66 2.28 60 3.38 3.38 2.62 TBVOOS 1.96 1.45

> 60 3.48 3.48 2.71 60 2.51 2.51 2.20 MANFRV2* 1.99 1.47

> 60 2.66 2.66 2.28 TCV Slow Closure/ 60 2.51 2.51 2.28 2.28 1.91 1.45 PLUOOS/PCOOS > 60 2.66 2.66 2.28 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.70 2.70 2.31 2.09 1.45 Closed/MSIVOOS > 60 2.70 2.70 2.31 60 3.50 3.50 2.68 TBVOOS 2.09 1.46

> 60 3.58 3.58 2.79 TCV Slow Closure/ 60 2.70 2.70 2.31 2.28 1.91 1.45 PLUOOS/PCOOS > 60 2.70 2.70 2.31

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 42 of 72

COLR Quad Cities 2 Revision 14 Table 4-6: ATRIUM 10XM TLO MCPRp Limits for NSS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.51 2.51 2.20 1.88 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.66 2.66 2.28 60 3.38 3.38 2.62 TBVOOS 1.94 1.45

> 60 3.48 3.48 2.71 60 2.51 2.51 2.20 MANFRV2* 1.99 1.45

> 60 2.66 2.66 2.28 TCV Slow Closure/ 60 2.51 2.51 2.26 2.26 1.89 1.45 PLUOOS/PCOOS > 60 2.66 2.66 2.28 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.70 2.70 2.31 2.03 1.45 Closed/MSIVOOS > 60 2.70 2.70 2.31 60 3.50 3.50 2.68 TBVOOS 2.03 1.45

> 60 3.58 3.58 2.79 TCV Slow Closure/ 60 2.70 2.70 2.31 2.26 1.89 1.45 PLUOOS/PCOOS > 60 2.70 2.70 2.31

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 43 of 72

COLR Quad Cities 2 Revision 14 Table 4-7: ATRIUM 10XM TLO MCPRp Limits for ISS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.51 2.51 2.20 1.89 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.66 2.66 2.28 60 3.38 3.38 2.62 TBVOOS 1.94 1.45

> 60 3.48 3.48 2.71 60 2.51 2.51 2.20 MANFRV2* 1.99 1.45

> 60 2.66 2.66 2.28 TCV Slow Closure/ 60 2.51 2.51 2.27 2.27 1.90 1.45 PLUOOS/PCOOS > 60 2.66 2.66 2.28 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.70 2.70 2.31 2.03 1.45 Closed/MSIVOOS > 60 2.70 2.70 2.31 60 3.50 3.50 2.68 TBVOOS 2.03 1.45

> 60 3.58 3.58 2.79 TCV Slow Closure/ 60 2.70 2.70 2.31 2.27 1.90 1.45 PLUOOS/PCOOS > 60 2.70 2.70 2.31

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 44 of 72

COLR Quad Cities 2 Revision 14 Table 4-8: ATRIUM 10XM TLO MCPRp Limits for TSSS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.51 2.51 2.20 1.95 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.66 2.66 2.28 60 3.38 3.38 2.62 TBVOOS 1.96 1.45

> 60 3.48 3.48 2.71 60 2.51 2.51 2.20 MANFRV2* 1.99 1.47

> 60 2.66 2.66 2.28 TCV Slow Closure/ 60 2.51 2.51 2.28 2.28 1.91 1.45 PLUOOS/PCOOS > 60 2.66 2.66 2.28 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.70 2.70 2.31 2.09 1.45 Closed/MSIVOOS > 60 2.70 2.70 2.31 60 3.50 3.50 2.68 TBVOOS 2.09 1.46

> 60 3.58 3.58 2.79 TCV Slow Closure/ 60 2.70 2.70 2.31 2.28 1.91 1.45 PLUOOS/PCOOS > 60 2.70 2.70 2.31

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 45 of 72

COLR Quad Cities 2 Revision 14 Table 4-9: OPTIMA2 TLO MCPRp Limits for NSS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.46 2.46 2.06 1.97 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.78 2.78 2.36 60 3.29 3.29 2.46 TBVOOS 1.97 1.45

> 60 3.66 3.66 2.84 60 2.46 2.46 2.06 MANFRV2* 1.97 1.45

> 60 2.78 2.78 2.36 TCV Slow Closure/ 60 2.46 2.46 2.34 2.34 1.94 1.45 PLUOOS/PCOOS > 60 2.78 2.78 2.36 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.64 2.64 2.16 2.14 1.45 Closed/MSIVOOS > 60 2.82 2.82 2.36 60 3.43 3.43 2.54 TBVOOS 2.14 1.46

> 60 3.77 3.77 2.91 TCV Slow Closure/ 60 2.64 2.64 2.34 2.34 1.94 1.45 PLUOOS/PCOOS > 60 2.82 2.82 2.36

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 46 of 72

COLR Quad Cities 2 Revision 14 Table 4-10: OPTIMA2 TLO MCPRp Limits for ISS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.46 2.46 2.06 1.97 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.78 2.78 2.36 60 3.29 3.29 2.46 TBVOOS 1.97 1.45

> 60 3.66 3.66 2.84 60 2.46 2.46 2.06 MANFRV2* 1.97 1.46

> 60 2.78 2.78 2.36 TCV Slow Closure/ 60 2.46 2.46 2.34 2.34 1.95 1.45 PLUOOS/PCOOS > 60 2.78 2.78 2.36 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.64 2.64 2.16 2.15 1.45 Closed/MSIVOOS > 60 2.82 2.82 2.36 60 3.43 3.43 2.54 TBVOOS 2.15 1.46

> 60 3.77 3.77 2.91 TCV Slow Closure/ 60 2.64 2.64 2.34 2.34 1.95 1.45 PLUOOS/PCOOS > 60 2.82 2.82 2.36

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 47 of 72

COLR Quad Cities 2 Revision 14 Table 4-11: OPTIMA2 TLO MCPRp Limits for TSSS Insertion Times, BOC to EOFPLB (37,679 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.46 2.46 2.06 2.02 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.78 2.78 2.36 60 3.29 3.29 2.46 TBVOOS 2.04 1.47

> 60 3.66 3.66 2.84 60 2.46 2.46 2.06 MANFRV2* 2.02 1.49

> 60 2.78 2.78 2.36 TCV Slow Closure/ 60 2.46 2.46 2.36 2.36 1.96 1.49 PLUOOS/PCOOS > 60 2.78 2.78 2.36 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.64 2.64 2.18 2.18 1.45 Closed/MSIVOOS > 60 2.82 2.82 2.36 60 3.43 3.43 2.54 TBVOOS 2.20 1.49

> 60 3.77 3.77 2.91 TCV Slow Closure/ 60 2.64 2.64 2.36 2.36 1.96 1.49 PLUOOS/PCOOS > 60 2.82 2.82 2.36

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 48 of 72

COLR Quad Cities 2 Revision 14 Table 4-12: OPTIMA2 TLO MCPRp Limits for NSS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.46 2.46 2.06 1.97 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.78 2.78 2.36 60 3.29 3.29 2.46 TBVOOS 1.97 1.45

> 60 3.66 3.66 2.84 60 2.46 2.46 2.06 MANFRV2* 1.97 1.45

> 60 2.78 2.78 2.36 TCV Slow Closure/ 60 2.46 2.46 2.34 2.34 1.94 1.45 PLUOOS/PCOOS > 60 2.78 2.78 2.36 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.64 2.64 2.16 2.14 1.45 Closed/MSIVOOS > 60 2.82 2.82 2.36 60 3.43 3.43 2.54 TBVOOS 2.14 1.46

> 60 3.77 3.77 2.91 TCV Slow Closure/ 60 2.64 2.64 2.34 2.34 1.94 1.45 PLUOOS/PCOOS > 60 2.82 2.82 2.36

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 49 of 72

COLR Quad Cities 2 Revision 14 Table 4-13: OPTIMA2 TLO MCPRp Limits for ISS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.46 2.46 2.06 1.97 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.78 2.78 2.36 60 3.29 3.29 2.46 TBVOOS 1.97 1.45

> 60 3.66 3.66 2.84 60 2.46 2.46 2.06 MANFRV2* 1.97 1.46

> 60 2.78 2.78 2.36 TCV Slow Closure/ 60 2.46 2.46 2.34 2.34 1.95 1.45 PLUOOS/PCOOS > 60 2.78 2.78 2.36 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.64 2.64 2.16 2.15 1.45 Closed/MSIVOOS > 60 2.82 2.82 2.36 60 3.43 3.43 2.54 TBVOOS 2.15 1.46

> 60 3.77 3.77 2.91 TCV Slow Closure/ 60 2.64 2.64 2.34 2.34 1.95 1.45 PLUOOS/PCOOS > 60 2.82 2.82 2.36

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 50 of 72

COLR Quad Cities 2 Revision 14 Table 4-14: OPTIMA2 TLO MCPRp Limits for TSSS Insertion Times, EOFPLB to EOCLB (38,401 MWd/MTU CAVEX)

(References 2, 12, and 16)

Nominal FWT Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.46 2.46 2.06 2.02 1.45 Closed/MSIVOOS/MANFRV1* > 60 2.78 2.78 2.36 60 3.29 3.29 2.46 TBVOOS 2.04 1.47

> 60 3.66 3.66 2.84 60 2.46 2.46 2.06 MANFRV2* 2.02 1.49

> 60 2.78 2.78 2.36 TCV Slow Closure/ 60 2.46 2.46 2.36 2.36 1.96 1.49 PLUOOS/PCOOS > 60 2.78 2.78 2.36 FHOOS Core Flow Core Power (% rated)

EOOS Condition

(% rated) 0 25 38.5 > 38.5 75 100 Base/TCV Stuck 60 2.64 2.64 2.18 2.18 1.45 Closed/MSIVOOS > 60 2.82 2.82 2.36 60 3.43 3.43 2.54 TBVOOS 2.20 1.49

> 60 3.77 3.77 2.91 TCV Slow Closure/ 60 2.64 2.64 2.36 2.36 1.96 1.49 PLUOOS/PCOOS > 60 2.82 2.82 2.36

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 51 of 72

COLR Quad Cities 2 Revision 14 Table 4-15: ATRIUM 10XM SLO MCPRp Limits for NSS Insertion Times, All Exposures (References 2 and 16)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.53 2.53 2.22 2.05 2.02 Closed/MSIVOOS TBVOOS 3.40 3.40 2.64 2.05 2.02 TCV Slow Closure/

2.53 2.53 2.28 2.28 2.17 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.72 2.72 2.33 2.05 2.02 Closed/MSIVOOS TBVOOS 3.52 3.52 2.70 2.05 2.02 TCV Slow Closure/

2.72 2.72 2.33 2.28 2.17 PLUOOS/PCOOS Page 52 of 72

COLR Quad Cities 2 Revision 14 Table 4-16: ATRIUM 10XM SLO MCPRp Limits for ISS Insertion Times, All Exposures (References 2 and 16)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.53 2.53 2.22 2.05 2.02 Closed/MSIVOOS TBVOOS 3.40 3.40 2.64 2.05 2.02 TCV Slow Closure/

2.53 2.53 2.29 2.29 2.18 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.72 2.72 2.33 2.05 2.02 Closed/MSIVOOS TBVOOS 3.52 3.52 2.70 2.05 2.02 TCV Slow Closure/

2.72 2.72 2.33 2.29 2.18 PLUOOS/PCOOS Page 53 of 72

COLR Quad Cities 2 Revision 14 Table 4-17: ATRIUM 10XM SLO MCPRp Limits for TSSS Insertion Times, All Exposures (References 2 and 16)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.53 2.53 2.22 2.05 2.02 Closed/MSIVOOS TBVOOS 3.40 3.40 2.64 2.05 2.02 TCV Slow Closure/

2.53 2.53 2.30 2.30 2.19 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.72 2.72 2.33 2.11 2.02 Closed/MSIVOOS TBVOOS 3.52 3.52 2.70 2.11 2.02 TCV Slow Closure/

2.72 2.72 2.33 2.30 2.19 PLUOOS/PCOOS Page 54 of 72

COLR Quad Cities 2 Revision 14 Table 4-18: OPTIMA2 SLO MCPRp Limits for NSS Insertion Times, All Exposures (References 2 and 16)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.48 2.48 2.08 2.06 2.03 Closed/MSIVOOS TBVOOS 3.31 3.31 2.48 2.06 2.03 TCV Slow Closure/

2.48 2.48 2.36 2.36 2.24 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.66 2.66 2.18 2.16 2.04 Closed/MSIVOOS TBVOOS 3.45 3.45 2.56 2.16 2.04 TCV Slow Closure/

2.66 2.66 2.36 2.36 2.24 PLUOOS/PCOOS Page 55 of 72

COLR Quad Cities 2 Revision 14 Table 4-19: OPTIMA2 SLO MCPRp Limits for ISS Insertion Times, All Exposures (References 2 and 16)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.48 2.48 2.08 2.06 2.03 Closed/MSIVOOS TBVOOS 3.31 3.31 2.48 2.06 2.03 TCV Slow Closure/

2.48 2.48 2.36 2.36 2.24 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.66 2.66 2.18 2.17 2.04 Closed/MSIVOOS TBVOOS 3.45 3.45 2.56 2.17 2.05 TCV Slow Closure/

2.66 2.66 2.36 2.36 2.24 PLUOOS/PCOOS Page 56 of 72

COLR Quad Cities 2 Revision 14 Table 4-20: OPTIMA2 SLO MCPRp Limits for TSSS Insertion Times, All Exposures (References 2 and 16)

Nominal FWT EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.48 2.48 2.08 2.06 2.03 Closed/MSIVOOS TBVOOS 3.31 3.31 2.48 2.06 2.03 TCV Slow Closure/

2.48 2.48 2.38 2.38 2.26 PLUOOS/PCOOS FHOOS EOOS Condition Core Power (% rated)

(all include SLO) 0 25 38.5 > 38.5 50 Base/TCV Stuck 2.66 2.66 2.20 2.20 2.07 Closed/MSIVOOS TBVOOS 3.45 3.45 2.56 2.22 2.09 TCV Slow Closure/

2.66 2.66 2.38 2.38 2.26 PLUOOS/PCOOS Page 57 of 72

COLR Quad Cities 2 Revision 14 Table 4-21: ATRIUM 10XM and OPTIMA2 MCPRf Limits, All Insertion Times, All Exposures (References 2, 12, and 16)

EOOS Condition* Core Flow (% rated) MCPRf Limit 0 1.67 Base Case / FHOOS / PCOOS / PLUOOS /

TCV Slow Closure / PLUOOS + PCOOS in 35 1.67 TLO and SLO / MANFRV1 / MANFRV2 108 1.18 0 1.78 Any Scenario** with One MSIVOOS 35 1.78 108 1.18 0 1.87 Any Scenario** with TBVOOS 35 1.87 108 1.35 0 1.67 Any Scenario** with 1 Stuck Closed 35 1.67 TCV/TSV 108 1.18

See Section 8 for further operating restrictions.

- Any Scenario implies any other combination of allowable EOOS conditions that is not otherwise covered by this table.

Note that the MCPRf limits for any scenario with 1 stuck closed TCV/TSV are identical to base case MCPRf limits. This is reflected in the thermal limit sets presented in Table 8-1.

Page 58 of 72

COLR Quad Cities 2 Revision 14

5. Linear Heat Generation Rate Technical Specification Sections 3.2.3, 3.4.1, and 3.7.7 The TMOL at rated conditions for the OPTIMA2 and ATRIUM 10XM fuel is established in terms of the maximum LHGR as a function of peak pellet (rod nodal) exposure. The LHGR limits for OPTIMA2 fuel are presented in Tables 5-1 through 5-4. The limits in Table 5-1 apply to OPTIMA2 lattices that do not require Gadolinia set down penalties as well as any natural blanket segments in OPTIMA2 fuel (lattice types 91 and 98). The limits in Tables 5-2 through 5-4 apply to OPTIMA2 lattices that do require Gadolinia set down penalties. The LHGR limits for ATRIUM 10XM fuel are presented in Table 5-5.

The power- and flow-dependent LHGR multipliers (LHGRFACp and LHGRFACf) are applied directly to the LHGR limits to protect against fuel melting and overstraining of the cladding during an AOO (Reference 2).

In all conditions, the margin to the LHGR limits is determined by applying the lowest multiplier from the applicable LHGRFACp and LHGRFACf multipliers for the power/flow statepoint of interest to the steady state LHGR limit (Reference 2).

LHGRFACp and LHGRFACf multipliers were established to support base case and all EOOS conditions for all Cycle 26 exposures and scram speeds. The LHGRFACp multipliers for ATRIUM 10XM and OPTIMA2 are presented in Table 5-6 and 5-7, respectively. The LHGRFACf multipliers for ATRIUM 10XM and OPTIMA2 are presented in Table 5-8 and Table 5-9, respectively. The LHGRFACp and LHGRFACf multipliers are applicable in both TLO and SLO.

The EOOS conditions separated by / in these tables represent single EOOS conditions and not any combination of conditions.

Page 59 of 72

COLR Quad Cities 2 Revision 14 Table 5-1: LHGR Limits for OPTIMA2 Lattices 91, 98, 152, 153, 154, 155, 171, 172, 173, 174, 178, 179, 180, 181, 185, 186, 187, 188, 189, and 190 (References 3 and 15)

Rod Nodal Exposure LHGR Limit (MWd/MTU) (kW/ft) 0 13.72 14,000 13.11 23,000 12.22 57,000 8.87 62,000 8.38 75,000 3.43 Table 5-2: LHGR Limits for OPTIMA2 Lattices 156, 157, and 158 (Reference 15)

Rod Nodal Exposure LHGR Limit (MWd/MTU) (kW/ft) 0 13.72 14,000 13.11 19,999 12.51 20,000 12.38 35,000 10.92 35,001 11.04 62,000 8.38 75,000 3.43 Table 5-3: LHGR Limits for OPTIMA2 Lattices 176, 177, 183 and 184 (Reference 3)

Rod Nodal Exposure LHGR Limit (MWd/MTU) (kW/ft) 0 13.72 14,000 13.11 20,000 12.52 20,001 12.39 23,000 12.10 37,000 10.73 37,001 10.84 57,000 8.87 62,000 8.38 75,000 3.43 Page 60 of 72

COLR Quad Cities 2 Revision 14 Table 5-4: LHGR Limits for OPTIMA2 Lattices 175 and 182 (Reference 3)

Rod Nodal Exposure LHGR Limit (MWd/MTU) (kW/ft) 0 13.72 14,000 13.11 14,001 12.84 23,000 11.98 34,000 10.92 34,001 11.14 57,000 8.87 62,000 8.38 75,000 3.43 Table 5-5: LHGR Limits for ATRIUM 10XM (References 2 and 16)

Peak Pellet Exposure LHGR Limit (MWd/MTU) (kW/ft) 0 14.1 18,900 14.1 74,400 7.4 Page 61 of 72

COLR Quad Cities 2 Revision 14 Table 5-6: ATRIUM 10XM LHGRFACp Multipliers, All Insertion Times, All Exposures (References 2, 12, and 16)

Nominal FWT Core Flow Core Power (%rated)

EOOS Condition

(% rated) 0 25 < 38.5 > 38.5 50 80 100 Base/TCV Stuck 60 0.55 0.55 0.57 0.64 0.67 0.89 1.00 Closed/MSIVOOS > 60 0.51 0.51 0.57 60 0.39 0.39 0.52 TBVOOS 0.64 0.67 0.89 1.00

> 60 0.37 0.37 0.47 TCV Slow Closure/ 60 0.49 0.49 0.57 0.64 0.67 0.89 1.00 PLUOOS/PCOOS > 60 0.49 0.49 0.57 60 0.55 0.55 0.56 MANFRV1* 0.56 0.62 0.83 1.00

> 60 0.51 0.51 0.56 60 0.55 0.55 0.56 MANFRV2* 0.56 0.60 0.78 0.90

> 60 0.51 0.51 0.56 FHOOS Core Flow Core Power (%rated)

EOOS Condition

(% rated) 0 25 < 38.5 > 38.5 50 80 100 Base/TCV Stuck 60 0.49 0.49 0.53 0.64 0.67 0.88 1.00 Closed/MSIVOOS > 60 0.47 0.47 0.53 60 0.37 0.37 0.48 TBVOOS 0.64 0.67 0.88 1.00

> 60 0.35 0.35 0.45 TCV Slow Closure/ 60 0.49 0.49 0.53 0.64 0.67 0.88 1.00 PLUOOS/PCOOS > 60 0.47 0.47 0.53

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 62 of 72

COLR Quad Cities 2 Revision 14 Table 5-7: OPTIMA2 LHGRFACp Multipliers, All Insertion Times, All Exposures (References 2, 12, and 16)

Nominal FWT Core Flow Core Power (%rated)

EOOS Condition

(% rated) 0 25 < 38.5 > 38.5 50 60 75 80 100 Base/TCV Stuck 60 0.62 0.62 0.65 0.70 0.76 0.82 0.88 1.00 Closed/MSIVOOS > 60 0.54 0.54 0.61 60 0.44 0.44 0.55 TBVOOS 0.69 0.72 0.73 0.76 1.00

> 60 0.41 0.41 0.50 TCV Slow Closure/ 60 0.61 0.61 0.61 0.61 0.67 0.72 0.85 1.00 PLUOOS/PCOOS > 60 0.54 0.54 0.61 60 0.62 0.62 0.65 MANFRV1* 0.66 0.72 0.80 0.88 1.00

> 60 0.54 0.54 0.61 60 0.62 0.62 0.65 MANFRV2* 0.65 0.68 0.71 0.85 1.00

> 60 0.54 0.54 0.61 FHOOS Core Flow Core Power (%rated)

EOOS Condition

(% rated) 0 25 < 38.5 > 38.5 50 60 75 80 100 Base/TCV Stuck 60 0.58 0.58 0.62 0.65 0.72 0.75 0.85 1.00 Closed/MSIVOOS > 60 0.54 0.54 0.61 60 0.43 0.43 0.52 TBVOOS 0.64 0.71 0.73 0.76 1.00

> 60 0.41 0.41 0.49 TCV Slow Closure/ 60 0.58 0.58 0.61 0.61 0.67 0.72 0.85 1.00 PLUOOS/PCOOS > 60 0.54 0.54 0.61

EOOS conditions MANFRV1 and MANFRV2 are not applicable at power levels below Pbypass ( 38.5%).

Page 63 of 72

COLR Quad Cities 2 Revision 14 Table 5-8: ATRIUM 10XM LHGRFACf Multipliers, All Insertion Times, All Exposures, All EOOS (References 2 and 16)

Core Flow (% rated) LHGRFACf 0.0 0.57 35.0 0.57 80.0 1.00 108.0 1.00 Table 5-9: OPTIMA2 LHGRFACf Multipliers, All Insertion Times, All Exposures, All EOOS (References 2 and 16)

Core Flow (% rated) LHGRFACf 0.0 0.27 20.0 0.43 40.0 0.60 80.0 1.00 100.0 1.00 108.0 1.00 Page 64 of 72

COLR Quad Cities 2 Revision 14

6. Control Rod Block Setpoints Technical Specification Sections 3.3.2.1 and 3.4.1 The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown in Table 6-1.

Table 6-1: Rod Block Monitor Upscale Instrumentation Setpoints (Reference 8)

ROD BLOCK MONITOR UPSCALE TRIP FUNCTION ALLOWABLE VALUE Two Recirculation Loop 0.65 Wd + 56.1%

Operation Single Recirculation Loop 0.65 Wd + 51.4%

Operation Wd - percent of recirculation loop drive flow required to produce a rated core flow of 98.0 Mlb/hr.

The setpoint may be lower/higher and will still comply with the CRWE analysis because CRWE is analyzed unblocked (Reference 2).

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COLR Quad Cities 2 Revision 14

7. Stability Protection Setpoints Technical Specifications Section 3.3.1.3 The OPRM PBDA Trip Settings are provided in Table 7-1.

Table 7-1: OPRM PBDA Trip Settings (References 2 and 16)

Corresponding Maximum PBDA Trip Amplitude Setpoint (Sp)

Confirmation Count Setpoint (Np) 1.13 15 The PBDA is the only OPRM setting credited in the safety analysis as documented in the licensing basis for the OPRM system (Methodology 2).

The OPRM PBDA trip settings are based, in part, on the cycle specific OLMCPR and the power/flow dependent MCPR limits. Any change to the OLMCPR values and/or the power/flow dependent MCPR limits should be evaluated for potential impact on the OPRM PBDA trip settings.

The OPRM PBDA trip settings are applicable when the OPRM system is declared operable and the associated Technical Specifications are implemented.

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COLR Quad Cities 2 Revision 14

8. Modes of Operation The allowed modes of operation with combinations of EOOS are as described in Table 8-1. The EOOS conditions separated by / in these tables represent single EOOS conditions and not combinations of conditions.

Note that the following EOOS options have operational restrictions: all SLO, all EOOS options with 1 TCV/TSV stuck closed, MSIVOOS, MANFRV1, and MANFRV2. See Table 8-2 for specific restrictions.

Table 8-1: Modes of Operation (References 2, 12, and 16)

EOOS Option Thermal Limit Set BASE CASE Base Case 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS TBVOOS due to Main Generator Load Reject PLUOOS/TCV SLOW C Trip Relays OOS 3/4 TLO for Nominal FWT*

TBVOOS TBVOOS 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS BASE CASE 1 TCV/TSV Stuck Closed 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS MSIVOOS One MSIVOOS 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS PLUOOS/TCV SLOW C TCV Slow Closure 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS PLUOOS/TCV SLOW C PLUOOS 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS PLUOOS/TCV SLOW C PCOOS 3/4 TLO or SLO 3/4 Nominal FWT or FHOOS PLUOOS/TCV SLOW C PLUOOS and 1 TCV/TSV Stuck Closed 3/4 TLO for Nominal FWT or FHOOS 3/4 SLO for Nominal FWT**

PLUOOS/TCV SLOW C PCOOS and PLUOOS 3/4 TLO for Nominal FWT or FHOOS 3/4 SLO for Nominal FWT**

PLUOOS/TCV SLOW C PCOOS and 1 TCV/TSV Stuck Closed 3/4 TLO for Nominal FWT or FHOOS 3/4 SLO for Nominal FWT**

MANFRV1 MANFRV1 3/4 TLO for Nominal FWT***

MANFRV2 MANFRV2 3/4 TLO for Nominal FWT***

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COLR Quad Cities 2 Revision 14

SLO and FHOOS cannot be applied for the case of TBVOOS due to main generator load reject trip relays OOS.

- FHOOS cannot be applied to SLO for the cases of PLUOOS and 1 TCV/TSV Stuck Closed, for the case of PCOOS and PLUOOS, or for the case of PCOOS and 1 TCV/TSV Stuck Closed.

- - SLO and FHOOS cannot be applied for the case of MANFRV1 or MANFRV2.

Table 8-2: Core Operational Restrictions for EOOS Conditions (References 2 and 12)

Core Flow (% of Core Thermal Power (%

EOOS Condition Rod Line (%)

Rated) of Rated Power) 1 TCV/TSV Stuck Closed PCOOS and 1 TCV/TSV N/A < 75 < 80 Stuck Closed PLUOOS and 1 TCV/TSV Stuck Closed One MSIVOOS N/A < 75 N/A SLO < 51 < 50 N/A MANFRV1/MANFRV2 N/A > 38.5 (Pbypass) N/A All requirements for all applicable conditions listed in Table 8-2 MUST be met.

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COLR Quad Cities 2 Revision 14 Common Notes:

1. All modes are allowed for operation at MELLLA, ICF (up to 108% rated core flow), and coastdown subject to the power restrictions in Table 8-2 (Reference 2). The licensing analysis supports full power operation to EOCLB (38,401 MWd/MTU CAVEX). Note that this value includes coastdown, where full power operation is not expected. Each OOS Option may be combined with each of the following conditions (Reference 2):

a. Up to 40% of the TIP channels OOS

b. Up to 50% of the LPRMs OOS

c. An LPRM calibration frequency of up to 2500 EFPH

2. Nominal FWT results are valid for application within a +10°F/-30°F temperature band around the nominal FWT curve (Reference 2). For operation outside of nominal FWT, a FWT reduction of up to 120ºF is supported for all FHOOS conditions listed in Table 8-1 for cycle operation through EOCLB (Reference 2). At lower power levels, the feedwater temperature reduction is less (Reference 2). Per Reference 9, there is a restriction which requires that for a FWT reduction greater than 100ºF, operation needs to be restricted to less than the 100% rod line. For a feedwater temperature reduction of between 30ºF and 120ºF, the FHOOS limits should be applied.

3. The base case and EOOS limits and multipliers support operation with 8 of 9 turbine bypass valves operational (i.e., one bypass valve out of service) with the exception of the TBVOOS condition in which all bypass valves are inoperable (Reference 2). Use of the response curve in TRM Appendix H supports operation with any single TBV OOS. TRM Appendix H facilitates analysis with one valve OOS in that the capacity at 0.45 seconds from start of TSV closure is equivalent to the total capacity with eight out of the nine valves in service (Reference 7). The analyses also support Turbine Bypass flow of 29.6% of vessel rated steam flow (Reference 7), equivalent to one TBV OOS (or partially closed TBVs equivalent to one closed TBV), if the assumed opening profile for the remaining TBVs is met. If the opening profile is NOT met, or if the TBV system CANNOT pass an equivalent of 29.6% of vessel rated steam flow, utilize the TBVOOS condition.

4. For the TBVOOS condition, analyses assume zero TBVs trip open and zero TBVs are available for pressure control during the slow portion of the transient analysis (Reference 7). Steam relief capacity is defined in Reference 7.

5. Failure of the main generator load reject trip relays to actuate (e.g., main generator load reject trip relays OOS) will render the turbine bypass valve system inoperable during load reject events (Reference 2). Operation with the main generator load reject trip relays out of service in TLO is supported by the TCV slow closure limits (Reference 2), meaning that, in accordance with Table 8-1, the PLUOOS/TCV SLOW C thermal limit set should be applied. This is applicable between 25% and 50% of rated thermal power.

6. Additional operating restrictions apply for both the MANFRV1 and MANFRV2 EOOS options as outlined in Section 1 of Reference 12. These operating restrictions apply when a Feedwater Regulating Valve is placed in manual for the conditions as described in the terms and definitions. Only one Feedwater Regulating Valve can be placed in manual. The additional EOOS conditions that are supported with MANFRV1 and MANFRV2 consist of 1 SRVOOS, 40% of TIP channels OOS and 50% of the LPRMs out-of-service. Other conditions associated with base case conditions, such as the feedwater temperature band, the pressure band, single and three-element level control, dome and turbine pressure control, and operation with 1 TBV OOS, are supported as discussed in Section 5.1 of Reference 2.

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