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COL Appendix a, Tech Specs
	ML17088A314
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Site:	Turkey Point
Issue date:	04/12/2018
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	Hoellman J P/NRO/DNRL/LB4/301-415-5481
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APPENDIX A

Turkey Point Unit 7

Technical Specifications Technical Specifications Turkey Point Unit 7 i TABLE OF CONTENTS Page 1.0 USE AND APPLICATION

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 2.0 SAFETY LIMITS (SLs) 2.1 SLs ........................................................................................................................ 2.0-1 2.2 SL Violations

.......................................................................................................... 2.0-1

3.0 LIMITING

CONDITIONS FOR OPERATION (LCO) APPLICABILITY ......................... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .......................................... 3.0-4

3.1 REACTIVITY

CONTROL SYSTEMS

3.1.1 SHUTDOWN

MARGIN (SDM)

...................................................................... 3.1.1-1 3.1.2 Core Reactivity ............................................................................................. 3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC) ................................................... 3.1.3-1 3.1.4 Rod Group Alignment Limits ......................................................................... 3.1.4-1

3.1.5 Shutdown

Bank Insertion Limits ................................................................... 3.1.5-1

3.1.6 Control

Bank Insertion Limits

........................................................................ 3.1.6-1 3.1.7 Rod Position Indication ................................................................................. 3.1.7-1 3.1.8 PHYSICS TESTS Exceptions - MODE 2 ..................................................... 3.1.8-1

3.1.9 Chemical

and Volume Control System (CVS) Demineralized Water Isolation Valves and Makeup Line Isolation Valves ...................... 3.1.9-1

3.2 POWER

DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (F Q (Z)) (F Q Methodology) ............................. 3.2.1-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (N H F) ........................................ 3.2.2-1 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) ............................................................... 3.2.3-1 3.2.4 QUADRANT POWER TILT RATIO (QPTR) .................................................. 3.2.4-1 3.2.5 OPDMS-Monitored Parameters.................................................................... 3.2.5-1

3.3 INSTRUMENTATION

3.3.1 Reactor

Trip System (RTS) Instrumentation ................................................. 3.3.1-1

3.3.2 Engineered

Safety Feature Actuation System (ESFAS) Instrumentation ....................................................................................... 3.3.2-1 3.3.3 Post Accident Monitoring (PAM) Instrumentation ......................................... 3.3.3-1

3.3.4 Remote

Shutdown Workstation (RSW) ........................................................ 3.3.4-1

3.3.5 Diverse

Actuation System (DAS) Manual Controls

....................................... 3.3.5-1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits ................................................................ 3.4.1-1 3.4.2 RCS Minimum Temperature for Criticality .................................................... 3.4.2-1 3.4.3 RCS Pressure and Temperature (P/T) Limits ............................................... 3.4.3-1 Technical Specifications Turkey Point Unit 7 ii TABLE OF CONTENTS Page

3.4 REACTOR

COOLANT SYSTEM (continued) 3.4.4 RCS Loops ................................................................................................... 3.4.4-1 3.4.5 Pressurizer ................................................................................................... 3.4.5-1 3.4.6 Pressurizer Safety Valves

............................................................................. 3.4.6-1 3.4.7 RCS Operational LEAKAGE......................................................................... 3.4.7-1 3.4.8 Minimum RCS Flow ...................................................................................... 3.4.8-1 3.4.9 RCS Leakage Detection Instrumentation ..................................................... 3.4.9-1 3.4.10 RCS Specific Activity .................................................................................. 3.4.10-1 3.4.11 Automatic Depressurization System (ADS) - Operating ............................ 3.4.11-1 3.4.12 Automatic Depressurization System (ADS) - Shutdown, RCS Intact ........ 3.4.12-1 3.4.13 Automatic Depressurization System (ADS) - Shutdown, RCS Open ........ 3.4.13-1 3.4.14 Low Temperature Overpressure Protection (LTOP) System ...................... 3.4.14-1 3.4.15 RCS Pressure Isolation Valve (PIV) Integrity ............................................. 3.4.15-1 3.4.16 Reactor Vessel Head Vent (RVHV) ............................................................ 3.4.16-1 3.4.17 Chemical and Volume Control System (CVS) Makeup Isolation Valves ................................................................................................... 3.4.17-1 3.4.18 Steam Generator (SG) Tube Integrity ......................................................... 3.4.18-1

3.5 PASSIVE

CORE COOLING SYSTEM (PXS) 3.5.1 Accumulators ................................................................................................ 3.5.1-1 3.5.2 Core Makeup Tanks (CMTs) - Operating ..................................................... 3.5.2-1 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, RCS Intact .................................. 3.5.3-1

3.5.4 Passive

Residual Heat Removal Heat Exchanger (PRHR HX) -

Operating ................................................................................................ 3.5.4-1 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, RCS Intact ............................................................................ 3.5.5-1 3.5.6 In-containment Refueling Water Storage Tank (IRWST) -

Operating ................................................................................................ 3.5.6-1 3.5.7 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, MODE 5 ................................................................................ 3.5.7-1 3.5.8 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, MODE 6 ................................................................................ 3.5.8-1

3.6 CONTAINMENT

SYSTEMS

3.6.1 Containment

................................................................................................. 3.6.1-1

3.6.2 Containment

Air Locks

.................................................................................. 3.6.2-1 3.6.3 Containment Isolation Valves ....................................................................... 3.6.3-1 3.6.4 Containment Pressure .................................................................................. 3.6.4-1

3.6.5 Containment

Air Temperature ....................................................................... 3.6.5-1

3.6.6 Passive

Containment Cooling System (PCS) - Operating ........................... 3.6.6-1 3.6.7 Passive Containment Cooling System (PCS) - Shutdown ........................... 3.6.7-1 3.6.8 Containment Penetrations ............................................................................ 3.6.8-1 3.6.9 pH Adjustment .............................................................................................. 3.6.9-1 3.6.10 Vacuum Relief Valves ................................................................................ 3.6.10-1

3.7 PLANT

SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs) ............................................................ 3.7.1-1 Technical Specifications Turkey Point Unit 7 iii TABLE OF CONTENTS Page

3.7 PLANT

SYSTEMS (continued) 3.7.2 Main Steam Isolation Valves (MSIVs)

........................................................... 3.7.2-1 3.7.3 Main Feedwater Isolation and Control Valves (MFIVs and MFCVs) ............ 3.7.3-1 3.7.4 Secondary Specific Activity ........................................................................... 3.7.4-1 3.7.5 Spent Fuel Pool Water Level ........................................................................ 3.7.5-1 3.7.6 Main Control Room Habitability System (VES) ............................................ 3.7.6-1

3.7.7 Startup

Feedwater Isolation and Control Valves

........................................... 3.7.7-1 3.7.8 Main Steam Line Leakage ............................................................................ 3.7.8-1 3.7.9 Fuel Storage Pool Makeup Water Sources .................................................. 3.7.9-1 3.7.10 Steam Generator Isolation Valves .............................................................. 3.7.10-1 3.7.11 Fuel Storage Pool Boron Concentration ..................................................... 3.7.11-1 3.7.12 Spent Fuel Pool Storage ............................................................................. 3.7.12-1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 DC Sources - Operating .............................................................................. 3.8.1-1 3.8.2 DC Sources - Shutdown .............................................................................. 3.8.2-1 3.8.3 Inverters - Operating .................................................................................... 3.8.3-1

3.8.4 Inverters

- Shutdown

.................................................................................... 3.8.4-1 3.8.5 Distribution Systems - Operating ................................................................. 3.8.5-1

3.8.6 Distribution

Systems - Shutdown ................................................................. 3.8.6-1 3.8.7 Battery Parameters ...................................................................................... 3.8.7-1

3.9 REFUELING

OPERATIONS

3.9.1 Boron

Concentration .................................................................................... 3.9.1-1

3.9.2 Unborated

Water Source Flow Paths ........................................................... 3.9.2-1

3.9.3 Nuclear

Instrumentation ............................................................................... 3.9.3-1 3.9.4 Refueling Cavity Water Level ....................................................................... 3.9.4-1 3.9.5 Containment Penetrations ............................................................................ 3.9.5-1

3.9.6 Containment

Air Filtration System (VFS) ...................................................... 3.9.6-1

3.9.7 Decay

Time .................................................................................................. 3.9.7-1 4.0 DESIGN FEATURES 4.1 Site ......................................................................................................................

.. 4.0-1 4.1.1 Site and Exclusion Boundaries ........................................................................ 4.0-1 4.1.2 Low Population Zone (LPZ) ............................................................................. 4.0-1

4.2 Reactor

Core ......................................................................................................... 4.0-1 4.2.1 Fuel Assemblies .............................................................................................. 4.0-1

4.2.2 Control

Rod and Gray Rod Assemblies ........................................................... 4.0-1 4.3 Fuel Storage .......................................................................................................... 4.0

-2 4.3.1 Criticality .......................................................................................................... 4.

0-2 4.3.2 Drainage .......................................................................................................... 4.0-3 4.3.3 Capacity........................................................................................................... 4.0-3

5.0 ADMINISTRATIVE

CONTROLS 5.1 Responsibility ........................................................................................................ 5.1

-1 5.2 Organization .......................................................................................................... 5.2

DOSE EQUIVALENT I-131 (continued) Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," EPA-520/

1-88-020, September 1988. DOSE EQUIVALENT XE-133 DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same effective dose equivalent as the quantity and isotopic mixture of noble gases (Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138) actually present. The dose conversion factors used for this calculation shall be those listed in Table III.1 of EPA Federal Guidance Report No. 12, "External Exposure to Radionuclides in Air, Water, and Soil," EPA 402-R-93-081, September 1993. ENGINEERED SAFETY FEATURE (ESF) RESPONSE TIME The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions). The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved

by the NRC. LEAKAGE LEAKAGE shall be: a. Identified LEAKAGE 1. LEAKAGE, such as that from seals or valve packing, that is captured and conducted to collection systems or a sump or collecting tank; 2. LEAKAGE into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; Technical Specifications Definitions

1.1 Turkey

Point Unit 7 1.1 - 4

1.1 Definitions

LEAKAGE (continued) 3. Reactor Coolant System (RCS) LEAKAGE through a steam generator (SG) to the Secondary System (primary to secondary LEAKAGE); or 4. RCS LEAKAGE through the passive residual heat removal heat exchanger (PRHR HX) to the In-containment Refueling Water Storage Tank (IRWST). b. Unidentified LEAKAGE All LEAKAGE that is not identified LEAKAGE. c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE and PRHR HX tube LEAKAGE) through a nonisolatable fault in a RCS component body, pipe wall, or vessel wall. MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel. OPERABLE-OPERABILITY A system, subsyste m, train, 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, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s). PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are: a. Described in Chapter 14, Initial Test Program;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

Technical Specifications Definitions

1.1 Turkey

Point Unit 7 1.1 - 5

1.1 Definitions

PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) The PTLR is the unit specific document that provides the reactor vessel pressure and temperature limits, including heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6. Plant operation within these operating limits is addressed in LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits" and LCO 3.4.14, "Low Temperature Overpressure Protection (LTOP) System." QUADRANT POWER TILT RATIO (QPTR) QPTR shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. RATED THERMAL POWER (RTP) RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3400 MWt. REACTOR TRIP CHANNEL OPERATIONAL TEST (RTCOT) A RTCOT shall be the injection of a simulated or actual signal into the reactor trip channel as close to the sensor as practicable to verify OPERABILITY of the required interlock and/or trip functions. The RTCOT may be performed by means of a series of sequential, overlapping, or total channel steps so that the entire channel is tested from the signal conditioner through the trip logic. REACTOR TRIP SYSTEM (RTS) RESPONSE TIME The RTS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RTS trip setpoint at the channel sensor until loss of stationary gripper coil voltage. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured. In lieu of measurement, response time may be verified for selected components provided that the components and methodology

for verification have been previously reviewed and approved

by the NRC. SHUTDOWN MARGIN (SDM) SDM shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming: a. All rod cluster control assemblies (RCCAs) are fully inserted except for the single assembly of highest reactivity worth, which is assumed to be fully withdrawn.

Technical Specifications Definitions

1.1 Turkey

Point Unit 7 1.1 - 6

1.1 Definitions

SHUTDOWN MARGIN (continued) However, with all RCCAs verified fully inserted by two independent means, it is not necessary to account for a stuck RCCA in the SDM calculation. With any RCCAs not capable of being fully inserted, the reactivity worth of these assemblies must be accounted for in the determination of SDM; and b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal zero power design level. c. In MODE 2 with keff < 1.0, and MODES 3, 4, and 5, the worth of fully inserted Gray Rod Cluster Assemblies (GRCAs) will be included in the SDM calculation. STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total

number of systems, subsystems, channels, or other designated components in the associated function. THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT) A TADOT shall consist of operating the trip actuating device and verifying the OPERABILITY of all devices in the channel required for trip actuating device OPERABILITY. The TADOT shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the required accuracy. The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps.

Technical Specifications Definitions

1.1 Turkey

Point Unit 7 1.1 - 7 Table 1.1-1 (page 1 of 1) MODES MODES TITLE REACTIVITY CONDITION (keff) % RATED THERMAL POWER (a) AVERAGE REACTOR COOLANT TEMPERATURE

(°F) 1 Power Operation 0.99 > 5 NA 2 Startup 0.99 5 NA 3 Hot Standby < 0.99 NA > 420 4 Safe Shutdown (b) < 0.99 NA 420 Tavg > 200 5 Cold Shutdown (b) < 0.99 NA 200 6 Refueling (c) NA NA NA (a) Excluding decay heat. (b) All reactor vessel head closure bolts fully tensioned. (c) One or more reactor vessel head closure bolts less than fully tensioned.

Technical Specifications Logical Connectors

1.2 Turkey

Point Unit 7 1.2 - 1 1.0 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 Specifications to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in Technical Specifications are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meaning.

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 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.

Technical Specifications Logical Connectors

1.2 Turkey

Point Unit 7 1.2 - 2

1.2 Logical

Connectors EXAMPLES (continued) EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify . . .

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.

Technical Specifications Logical Connectors

1.2 Turkey

Point Unit 7 1.2 - 3

1.2 Logical

Connectors EXAMPLES (continued) EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip ... 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.

Technical Specifications Completion Times

1.3 Turkey

Point Unit 7 1.3 - 1 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 Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO 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 time of 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 LCO. 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 LCO Applicability. If situations are discovered that require entry into more than one Condition at a time within a single LCO (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 time of discovery of the situation that required entry into the Condition. Once a Condition has been entered, subsequent trains, 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. However, when a subsequent train, subsystem, component, or variable, expressed in the Condition, is discovered to be inoperable or not within

Technical Specifications Completion Times

1.3 Turkey

Point Unit 7 1.3 - 2

1.3 Completion

Times DESCRIPTION (continued) 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 extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each train, 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 Specifications. 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 ...." Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Conditions A and B in example 1.3-3 may not be extended.

Technical Specifications Completion Times

1.3 Turkey

Point Unit 7 1.3 - 3

1.3 Completion

Times 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 and

associated

Completion Time not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND in MODE 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-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 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months ) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months , the time allowed for reaching MODE 5 is the next 33 hours3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months because the total time allowed for reaching MODE 5 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 5 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Technical Specifications Completion Times

1.3 Turkey

Point Unit 7 1.3 - 4

1.3 Completion

Times EXAMPLES (continued) EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One valve inoperable. A.1 Restore valve to OPERABLE status.

7 days B. Required Action and associated

Completion Time not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a valve is declared inoperable, Condition A is entered. If the valve 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 valve 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 valve is declared inoperable while the first valve is still inoperable, Condition A is not re-entered for the second valve. LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable valve. The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered. While in LCO 3.0.3, if one of the inoperable valves is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition A. While in LCO 3.0.3, if one of the inoperable valves is restored to OPERABLE status and the Completion Time for Condition A has expired, LCO 3.0.3 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.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours 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 (including the extension) expires while one or more valves are still inoperable, Condition B is entered.

Technical Specifications Completion Times

1.3 Turkey

Point Unit 7 1.3 - 8

1.3 Completion

Times EXAMPLES (continued) EXAMPLE 1.3-5 ACTIONS - NOTE - Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more valves inoperable. A.1 Restore valve to OPERABLE status.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and

associated

Completion Time not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours 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 only applicable 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. 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 which 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.

Technical Specifications Completion Times

1.3 Turkey

Point Unit 7 1.3 - 9

1.3 Completion

Times EXAMPLES (continued) EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel inoperable. A.1 Perform SR 3.x.x.x. OR A.2 Reduce THERMAL POWER to 50% RTP.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 hours B. Required Action and

associated

Completion Time not met. B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 SR 3.0.2, to each performance after the initial performance. The initial 8 hours9.259259e-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 complete 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 SR 3.0.2),

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.

Technical Specifications Completion Times

1.3 Turkey

Point Unit 7 1.3 - 10

1.3 Completion

Times EXAMPLES (continued) EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One subsystem inoperable. A.1 Verify affected subsystem isolated.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem to OPERABLE status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and associated

Completion Time not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 SR 3.0.2), 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 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.

Point Unit 7 1.4 - 5

1.4 Frequency

EXAMPLES (continued) 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 performed within the "specified Frequency." Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was < 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 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 SR 3.0.3 would apply.

Technical Specifications Frequency

1.4 Turkey

Point Unit 7 1.4 - 6

1.4 Frequency

EXAMPLES (continued) 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 SR 3.0.2), but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 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), SR 3.0.4 would require satisfying the SR.

Technical Specifications Frequency

1.4 Turkey

Point Unit 7 1.4 - 7

1.4 Frequency

EXAMPLES (continued) EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

- NOTE - Only required to be performed in MODE 1. -----------------------------------------------------------------

Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MODE 1, 2, or 3 (the assumed Applicability of the associated LCO) between

performances. As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance. The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to entering MODE 1. Therefore, if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1. Once the unit reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance were not performed prior to entering MODE 1, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

Technical Specifications Frequency

1.4 Turkey

Point Unit 7 1.4 - 8

1.4 Frequency

EXAMPLES (continued) EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

- NOTE - Not required to be met in MODE 3. -----------------------------------------------------------------

Verify parameter is within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met while the unit is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1, 2, and 3). 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 SR 3.0.2), and the unit was in MODE 3, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, 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 does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were not met), SR 3.0.4

would require satisfying the SR.

Technical Specifications SLs 2.0 Turkey Point Unit 7 2.0 - 1

2.0 SAFETY

LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop cold leg temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following SLs shall not be exceeded: 2.1.1.1 The departure from nucleate boiling ratio (DNBR) shall be maintained 1.14 for the WRB-2M DNB correlation.

2.1.1.2 The peak fuel centerline temperature shall be maintained < 5080°F, decreasing by 58°F per 10,000 MWD/MTU of burnup. 2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5 the RCS pressure shall be maintained 2733.5 psig.

2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . 2.2.2 If SL 2.1.2 is violated: 2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes.

Technical Specifications LCO Applicability

3.0 Turkey

Point Unit 7 3.0 - 1

3.0 LIMITING

CONDITIONS FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, ex cept as provided in LCO 3.0.5 and 3.0.6. If the LCO 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.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in: a. MODE 3 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ; and

b. MODE 4 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and c. MODE 5 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications. Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required. LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall not be made except 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. This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or are part of a shutdown of the unit.

Exceptions to this Specification are stated in the individual Specifications. LCO 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, 3, and 4.

Technical Specifications LCO Applicability

3.0 Turkey

Point Unit 7 3.0 - 2 3.0 LCO Applicability LCO 3.0.5 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 LCO 3.0.2 for

the system returned to service under adm inistrative control to perform the test required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, additional evaluations and limitations may be required in accordance with Specification 5.5.7, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Test Exception LCO 3.1.8 allows specified Technical Specification (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Test Exception LCOs is optional. When a Test Exception LCO is desired to be met but is not met, the ACTIONS of the Test Exception LCO shall be met. When a Test Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.

LCO 3.0.8 When an LCO is not met and the associated ACTIONS are not met or an associated ACTION is not provided, action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to: a. Restore inoperable equipment and b. Monitor Safety System Shutdown Monitoring Trees parameters Exceptions to this Specification are stated in the individual Specifications.

Technical Specifications LCO Applicability

3.0 Turkey

Point Unit 7 3.0 - 3 3.0 LCO Applicability LCO 3.0.8 (continued) Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.8 is not required. LCO 3.0.8 is only applicable in MODES 5 and 6.

Technical Specifications SR Applicability

3.0 Turkey

Point Unit 7 3.0 - 4

3.0 SURVEILLANCE

REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified Conditions in the Applicability of individual LCOs, unless otherwise stated in the SR.

Failure to meet a Surveillance, whether such failure is experienced during the performance of the surveillance or between performances of the Surveillance, shall be a failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance 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 Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO 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, which ever is greater. This delay period is permitted to allow performance of the Surveillance. 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 Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be

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

Technical Specifications SR Applicability

3.0 Turkey

Point Unit 7 3.0 - 5 3.0 SR Applicability SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of a LCO shall not be made unless the LCO's Surveillances have been met within their specified Frequency. 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. SR 3.0.4 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, 3, and 4.

Technical Specifications SDM 3.1.1 Turkey Point Unit 7 3.1.1 - 1

3.1 REACTIVITY

CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM) LCO 3.1.1 The SDM shall be within the limits specified in the COLR. APPLICABILITY: MODE 2 with keff < 1.0. MODES 3, 4, and 5. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits. A.1 Initiate boration to restore SDM to within limits.

15 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Technical Specifications Core Reactivity

3.1.2 Turkey

Point Unit 7 3.1.2 - 1

3.1 REACTIVITY

CONTROL SYSTEMS 3.1.2 Core Reactivity LCO 3.1.2 The measured core reactivity shall be within +/-1% k/k of the normalized predicted values. APPLICABILITY: MODES 1 and 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core reactivity not within limit. A.1 Re-evaluate core design and safety analysis, and determine that the reactor core is acceptable for continued operation.

7 days AND A.2 Establish appropriate operating restrictions and SRs. 7 days B. Required Action and associated Completion Time not met. B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Technical Specifications Core Reactivity

3.1.2 Turkey

Point Unit 7 3.1.2 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 ----------------------------------------------------------------------- - NOTE - The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 effective full power days (EFPD) after each fuel loading. -----------------------------------------------------------------------

Verify measured core reactivity is within +/-1% k/k of predicted values.

Prior to entering MODE 1 after

each refueling AND ------------------------- - NOTE - Only required after

60 EFPD ------------------------- 31 EFPD thereafter

Technical Specifications MTC 3.1.3 Turkey Point Unit 7 3.1.3 - 1

3.1 REACTIVITY

CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC) LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR. APPLICABILITY: MODE 1 for the upper MTC limit. MODE 2 with keff 1.0 for the upper MTC limit. MODES 1, 2, and 3 for the lower MTC limit. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within upper limit. A.1 Establish administrative withdrawal limits for control banks to maintain MTC within limit.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. Required Action and associated Completion Time of Condition A not met. B.1 Be in MODE 2 with keff < 1.0. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months C. MTC not within lower limit. C.1 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC within upper limit. Prior to entering MODE 1 after

each refueling

Technical Specifications MTC 3.1.3 Turkey Point Unit 7 3.1.3 - 2 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.1.3.2 ----------------------------------------------------------------------- - NOTES - 1. Not required to be performed until 7 effective full power days (EFPD) after reaching the equivalent of an equilibrium RTP all rods out (ARO) boron concentration of 300 ppm. 2. If the MTC is more negative than the 300 ppm Surveillance limit (not LCO limit) specified in the COLR, SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle. 3. SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of 60 ppm is less negative than the 60 ppm Surveillance limit specified in the COLR. -----------------------------------------------------------------------

Verify MTC is within lower limit. Once each cycle

Technical Specifications Rod Group Alignment Limits

3.1.4 Turkey

Point Unit 7 3.1.4 - 1

3.1 REACTIVITY

CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 All shutdown and control rods shall be OPERABLE.

AND Individual indicated rod positions shall be within 12 steps of their group step counter demand position.

- NOTE - Not applicable to Gray Rod Cluster Assemblies (GRCAs) during GRCA bank sequence exchange with the On-Line Power Distribution Monitoring System (OPDMS) OPERABLE. --------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 1 and 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rod(s) inoperable. A.1.1 Verify SDM to be within the limits specified in the COLR. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR A.1.2 Initiate boration to restore SDM within limit.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND A.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B. One rod not within alignment limits.

B.1 Restore rod, to within alignment limits. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months with the OPDMS OPERABLE OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with the OPDMS inoperable OR Technical Specifications Rod Group Alignment Limits

3.1.4 Turkey

Point Unit 7 3.1.4 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B.2.1.1 Verify SDM to be within the limits specified in the COLR. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR B.2.1.2 Initiate boration to restore SDM within limit.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND B.2.2 Reduce THERMAL POWER to 75% RTP.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND B.2.3 Verify SDM is within the limits specified in the COLR. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.2.4 ------------------------------------ - NOTE - Only required to be performed when OPDMS is inoperable. ------------------------------------

Perform SR 3.2.1.1 and SR 3.2.1.2.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND

Technical Specifications Rod Group Alignment Limits

3.1.4 Turkey

Point Unit 7 3.1.4 - 3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B.2.5 ------------------------------------ - NOTE - Only required to be performed when OPDMS

is inoperable. ------------------------------------

Perform SR 3.2.2.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND B.2.6 Re-evaluate safety analyses and confirm results remain valid for duration of operation under

these conditions.

5 days C. Required Action and associated Completion Time of Condition B not met. C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. More than one rod not within alignment limit. D.1.1 Verify SDM is within the limits specified in the COLR. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR D.1.2 Initiate boration to restore required SDM to within limit. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND D.2 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Technical Specifications Rod Group Alignment Limits

3.1.4 Turkey

Point Unit 7 3.1.4 - 4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify individual rod positions within alignment limit. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.1.4.2 ----------------------------------------------------------------------- - NOTE - Not applicable to GRCAs. -----------------------------------------------------------------------

Verify rod freedom of movement (trippability) by moving each rod not fully inserted in the core 10 steps in either direction.

92 days SR 3.1.4.3 ----------------------------------------------------------------------- - NOTE - Not applicable to GRCAs. -----------------------------------------------------------------------

Verify rod drop time of each rod, from the fully withdrawn position, is < 2.47 seconds from the beginning of decay of stationary gripper coil voltage to dashpot entry, with: a. Tavg 500°F, and b. All reactor coolant pumps operating.

Prior to reactor criticality after

each removal of the reactor head, and after each earthquake requiring plant shutdown Technical Specifications Shutdown Bank Insertion Limits 3.1.5 Turkey Point Unit 7 3.1.5 - 1

3.1 REACTIVITY

CONTROL SYSTEMS 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 Each Shutdown Bank shall be within insertion limits specified in the COLR. APPLICABILITY: MODES 1 and 2. -------------------------------------------------------------------------------------------------- - NOTE - This LCO is not applicable while performing SR 3.1.4.2. -------------------------------------------------------------------------------------------------- ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more shutdown banks not within limits. A.1.1 Verify SDM is within the limits specified in the COLR. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR A.1.2 Initiate boration to restore SDM to within limit.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND A.2 Restore shutdown banks to within limits.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. Required Action and associated Completion Time not met. B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Technical Specifications Shutdown Bank Insertion Limits 3.1.5 Turkey Point Unit 7 3.1.5 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each shutdown bank is within the insertion limits specified in the COLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Technical Specifications Control Bank Insertion Limits

3.1.6 Turkey

Point Unit 7 3.1.6 - 1

3.1 REACTIVITY

CONTROL SYSTEMS 3.1.6 Control Bank Insertion Limits LCO 3.1.6 Control banks shall be within the insertion, sequence, and overlap limits specified in the COLR. APPLICABILITY: MODE 1. MODE 2 with keff 1.0. -------------------------------------------------------------------------------------------------- - NOTES - 1. This LCO is not applicable while performing SR 3.1.4.2.

2. This LCO is not applicable to Gray Rod Cluster Assembly (GRCA) banks during GRCA bank sequence exchange with OPDMS OPERABLE. -------------------------------------------------------------------------------------------------- ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control Bank insertion limits not met. A.1.1 Verify SDM is within the limits specified in the COLR. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR A.1.2 Initiate boration to restore SDM to within limit.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND A.2 Restore control bank(s) to within limits.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. Control bank sequence or overlap limits not met. B.1.1 Verify SDM is within the limits specified in the COLR. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR

Technical Specifications Control Bank Insertion Limits

3.1.6 Turkey

Point Unit 7 3.1.6 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B.1.2 Initiate boration to restore SDM to within limit.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND B.2 Restore control bank sequence and overlap to within limits.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C. Required Action and associated Completion Time not met. C.1 Be in MODE 2 with keff < 1.0. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify the estimated critical control bank position is within limits specified in the COLR. Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achieving criticality SR 3.1.6.2 Verify each control bank insertion is within the limits specified in the COLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.1.6.3 Verify sequence and overlap limits, specified in the COLR, are met for control banks not fully withdrawn from the core.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Technical Specifications Rod Position Indication

3.1.7 Turkey

Point Unit 7 3.1.7 - 1

3.1 REACTIVITY

CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Digital Rod Position Indication (DRPI) System and the Bank Demand Position Indication System shall be OPERABLE. APPLICABILITY: MODES 1 and 2. ACTIONS - NOTE - Separate Condition entry is allowed for each inoperable rod position indicator and each demand position indicator.

CONDITION REQUIRED ACTION COMPLETION TIME A. One DRPI per group inoperable for one or more groups. A.1 Verify the position of the rods with inoperable position indicators by using

the On-line Power

Distribution Monitoring System (OPDMS).

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR A.2 Reduce THERMAL POWER to 50% RTP.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months B. More than one DRPI per group inoperable. B.1 Place the control rods under manual control.

Immediately AND B.2 Monitor and record Reactor Coolant System (RCS) Tavg. Once per 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Technical Specifications Rod Position Indication

3.1.7 Turkey

Point Unit 7 3.1.7 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B.3 Verify the position of the rods with inoperable position indicators indirectly by using the incore detectors.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND B.4 Restore inoperable position indicators to OPERABLE status such that a maximum of one DRPI per group is

inoperable.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. One or more rods with inoperable position indicators have been moved in excess of 24 steps in one direction since the last

determination of the rod's position. C.1 Verify the position of the rods with inoperable position indicators by using

the OPDMS.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OR C.2 Reduce THERMAL POWER to 50% RTP.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D. One demand position indicator per bank

inoperable for one or

more banks. D.1.1 Verify by administrative means all DRPIs for the affected banks are OPERABLE.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND D.1.2 Verify the most withdrawn rod and the least

withdrawn rod of the affected banks are 12 steps apart.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR D.2 Reduce THERMAL POWER to 50% RTP.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Technical Specifications Rod Position Indication

3.1.7 Turkey

Point Unit 7 3.1.7 - 3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time not met. E.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify each DRPI agrees within 12 steps of the group demand position for the full indicated range of rod

travel. Prior to criticality after each removal of the reactor head

Technical Specifications PHYSICS TESTS Exceptions

- MODE 2 3.1.8 Turkey Point Unit 7 3.1.8 - 1

3.1 REACTIVITY

CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions - MODE 2 LCO 3.1.8 During the performance of PHYSICS TESTS, the requirements of: LCO 3.1.3 "Moderator Temperature Coefficient (MTC)," LCO 3.1.4 "Rod Group Alignment Limits," LCO 3.1.5 "Shutdown Bank Insertion Limits,"

LCO 3.1.6 "Control Bank Insertion Limits," and LCO 3.4.2 "RCS Minimum Temperature for Criticality" may be suspended, and the number of required channels for LCO 3.3.1, "RTS Instrumentation," Functions 2, 3, 6, and 16.b, may be reduced to 3 provided: a. Reactor Coolant System (RCS) lowest loop average temperature is 541°F, b. SDM is within the limits specified in the COLR, and c. THERMAL POWER is 5% RTP.

APPLICABILITY: During PHYSICS TESTS initiated in MODE 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore SDM to within limit.

15 minutes AND A.2 Suspend PHYSICS TESTS exceptions.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. THERMAL POWER not within limit. B.1 Open reactor trip breakers. Immediately C. RCS lowest loop average temperature

not within limit. C.1 Restore RCS lowest loop average temperature to within limit.

15 minutes Technical Specifications PHYSICS TESTS Exceptions

- MODE 2 3.1.8 Turkey Point Unit 7 3.1.8 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and Associated Completion Time of Condition C not met. D.1 Be in MODE 3. 15 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 Perform a REACTOR TRIP CHANNEL OPERATIONAL TEST on power range and intermediate range channels per SR 3.3.1.8 and SR 3.3.1.9. Prior to initiation of PHYSICS TESTS SR 3.1.8.2 Verify the RCS lowest loop average temperature is 541°F. 30 minutes SR 3.1.8.3 Verify THERMAL POWER is 5% RTP. 30 minutes SR 3.1.8.4 Verify SDM is within the limits specified in the COLR. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Technical Specifications CVS Demineralized Water Isolation Valves and Makeup Line Isolation Valves

3.1.9 Turkey

Point Unit 7 3.1.9 - 1

3.1 REACTIVITY

CONTROL SYSTEMS 3.1.9 Chemical and Volume Control System (CVS) Demineralized Water Isolation Valves and Makeup Line Isolation Valves LCO 3.1.9 Two CVS Demineralized Water Isolation Valves and two Makeup Line Isolation Valves shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CVS demineralized water isolation valve

inoperable. OR One makeup line isolation valve inoperable. OR One CVS demineralized water isolation valve

and one makeup line isolation valve inoperable. A.1 Restore two CVS demineralized water

isolation valves and two makeup line isolation

Point Unit 7 3.2.1 - 3 SURVEILLANCE REQUIREMENTS - NOTES - 1. During power escalation at the beginning of each cycle, THERMAL POWER may be increased until a power level for extended operation has been achieved at which a power distribution map is obtained. 2. If the OPDMS becomes inoperable while in MODE 1 these surveillances must be performed within 31 days of the last verification of OPDMS parameters.

SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify )Z (F C Q within limit. Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving equilibrium conditions after

exceeding, by 10% RTP, the THERMAL POWER at which

)Z (F C Q was last verified AND 31 effective full power days (EFPD) thereafter

Technical Specifications F Q (Z) (F Q Methodology)

3.2.1 Turkey

Point Unit 7 3.2.1 - 4 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.2.1.2 ----------------------------------------------------------------------- - NOTE - If )Z (F W Q measurements indicate maximum over z)Z (F C Q has increased since the previous evaluation of )Z (F C Q: a. Increase )

Z (F W Q by the greater of a factor of 1.02 or by an appropriate factor specified in the COLR and reverify )

Z (F W Q is within limits; or

b. Repeat SR 3.2.1.2 once per 7 EFPD until two successive flux maps indicate maximum over z)Z (F C Q has not increased. -----------------------------------------------------------------------

Verify )Z (F W Q within limits. Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after achieving

equilibrium conditions after

exceeding, by 10% RTP, the THERMAL POWER at which

)Z (F W Q was last verified AND 31 EFPD thereafter

Technical Specifications N H F 3.2.2 Turkey Point Unit 7 3.2.2 - 1

3.2 POWER

DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (N H F) LCO 3.2.2 N H F shall be within the limits specified in the COLR. APPLICABILITY: MODE 1 with On-line Power Distribution Monitoring System (OPDMS) inoperable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------------------------- - NOTE - Required Actions A.2 and A.3 must be completed whenever Condition A is entered. --------------------------------

N H Fnot within limits.

A.1.1 Restore N H F to within limit.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OR A.1.2.1 Reduce THERMAL POWER to < 50% RTP.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND A.1.2.2 Reduce Power Range Neutron Flux - High trip setpoints to 55% RTP. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND A.2 Perform SR 3.2.2.1. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND Technical Specifications N H F 3.2.2 Turkey Point Unit 7 3.2.2 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A.3 ------------------------------------ - NOTE - THERMAL POWER does not have to be reduced to comply with this Required Action. -----------------------------------

Perform SR 3.2.2.1. Prior to THERMAL POWER exceeding 50% RTP AND Prior to THERMAL POWER exceeding 75% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER reaching 95% RTP B. Required Action and associated Completion Time not met. B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Technical Specifications N H F 3.2.2 Turkey Point Unit 7 3.2.2 - 3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 ----------------------------------------------------------------------- - NOTE - If the OPDMS becomes inoperable while in MODE 1 these Surveillances must be performed within 31 days of the last verification of OPDMS parameters. -----------------------------------------------------------------------

Verify N H F within limits specified in the COLR. Once after each refueling prior to THERMAL POWER exceeding 75% RTP AND 31 effective full power days (EFPD) thereafter

Technical Specifications AFD (RAOC Methodology)

3.2.3 Turkey

Point Unit 7 3.2.3 - 1

3.2 POWER

DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology) LCO 3.2.3 The AFD in %-flux-difference units shall be maintained within the limits specified in the COLR. -------------------------------------------------------------------------------------------------- - NOTE - The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits. -------------------------------------------------------------------------------------------------- APPLICABILITY: MODE 1 with THERMAL POWER 50% RTP and with the On-Line Power Distribution Monitoring System (OPDMS) inoperable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. AFD not within limits. A.1 Reduce THERMAL POWER to < 50% RTP.

30 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify AFD within limits for each OPERABLE excore channel. 7 days Technical Specifications QPTR 3.2.4 Turkey Point Unit 7 3.2.4 - 1

3.2 POWER

DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR) LCO 3.2.4 The QPTR shall be 1.02. APPLICABILITY: MODE 1 with THERMAL POWER > 50% RTP and with the On-Line Power Distribution Monitoring System (OPDMS) inoperable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPTR not within limit. A.1 Reduce THERMAL POWER 3% from RTP for each 1% of QPTR

> 1.00. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after each QPTR determination AND A.2 Perform SR 3.2.4.1. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND A.3 Perform SR 3.2.1.1 and SR 3.2.2.1. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions from a THERMAL POWER reduction per

Required Action A.1 AND Once per 7 days thereafter AND A.4 Reevaluate safety analyses and confirm results remain valid for duration of operation under this condition. Prior to increasing THERMAL POWER above the limit of

Required Action A.1 AND Technical Specifications QPTR 3.2.4 Turkey Point Unit 7 3.2.4 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A.5 ------------------------------------ - NOTES - 1. Perform Required Action A.5 only after Required Action A.4 is completed. 2. Required Action A.6 shall be completed

whenever Required Action A.5 is

performed. ------------------------------------

Normalize excore detectors to restore QPTR

to within limit. Prior to increasing THERMAL POWER

above the limit of

Required Action A.1 AND A.6 ------------------------------------ - NOTE - Perform Required Action A.6 only after Required Action A.5 is completed. ------------------------------------

Perform SR 3.2.1.1, SR 3.2.1.2, and

SR 3.2.2.1. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after achieving equilibrium conditions at RTP not

to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after increasing THERMAL POWER

above the limit of

Required Action A.1 B. Required Action and associated Completion Time not met. B.1 Reduce THERMAL POWER to 50% RTP.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Technical Specifications QPTR 3.2.4 Turkey Point Unit 7 3.2.4 - 3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 ----------------------------------------------------------------------- - NOTES - 1. With one power range channel inoperable and THERMAL POWER < 75% RTP, the remaining three power range channels can be used for calculating QPTR. 2. SR 3.2.4.2 may be performed in lieu of this Surveillance. -----------------------------------------------------------------------

Verify QPTR within limit by calculation. 7 days SR 3.2.4.2 ----------------------------------------------------------------------- - NOTE - Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER 75% RTP. -----------------------------------------------------------------------

Verify QPTR is within limit using a minimum of 4 symmetric pairs of fixed incore detectors.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Technical Specifications OPDMS-Monitored Parameters

3.2.5 Turkey

Point Unit 7 3.2.5 - 1

3.2 POWER

DISTRIBUTION LIMITS 3.2.5 On-Line Power Distribution Monitori ng System (OPDMS)-Monitored Parameters LCO 3.2.5 The following parameters shall not exceed their operating limits as specified in the COLR: a. Peak kw/ft(Z)

b. N H F c. DNBR d. SDM. APPLICABILITY: MODE 1 with THERMAL POWER > 50% RTP with OPDMS OPERABLE for parameters a, b, and c. MODE 1 with OPDMS OPERABLE for parameter d.

2 with keff 1.0 and OPDMS OPERABLE for parameter d.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the parameters a. through

c. above not within limits. A.1 Restore all parameters to within limits.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. Required Action and associated Completion Time of Condition A not met. B.1 ------------------------------------ - NOTE - If the power distribution parameters are restored to within their limits while power is being reduced, operation may continue at

the power level where this occurs. ------------------------------------

Reduce THERMAL POWER to 50% RTP. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. Parameter d above not within limits.

C.1 Initiate boration to restore SDM to within limits.

15 minutes

Technical Specifications OPDMS-Monitored Parameters

3.2.5 Turkey

Point Unit 7 3.2.5 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.5.1 Verify the parameters a. through d. to be within their limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months with OPDMS alarms OPERABLE OR 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with OPDMS alarms inoperable

Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 1

3.3 INSTRUMENTATION

3.3.1 Reactor

Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE. APPLICABILITY: According to Table 3.3.1-1. ACTIONS - NOTE - Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one or more required channels inoperable. A.1 Enter the Condition referenced in Table 3.3.1-1 for the channel(s).

Immediately B. One manual initiation device inoperable. B.1 Restore manual initiation device to OPERABLE status. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR B.2.1 Be in MODE 3. 54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND B.2.2 Open reactor trip breakers (RTBs). 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months C. One manual initiation device inoperable. C.1 Restore manual initiation device to OPERABLE status. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR C.2 Open RTBs. 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months

Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. One or two Power Range Neutron Flux -

High channels inoperable. D.1.1 Reduce THERMAL POWER to 75% RTP.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.1.2 Place one inoperable channel in bypass or trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND D.1.3 With two inoperable channels, place one channel in bypass and one channel in trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR D.2.1 Place inoperable channel(s) in bypass.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND D.2.2 ------------------------------------ - NOTE - Only required to be performed when OPDMS is inoperable and the Power Range Neutron Flux

input to QPTR is inoperable. ------------------------------------

Perform SR 3.2.4.2. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR D.3 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. One or two channels inoperable. E.1.1 Place one inoperable channel in bypass or trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND E.1.2 With two channels inoperable, place one channel in bypass and one channel in trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR E.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months F. THERMAL POWER between P-6 and P-10, one or two Intermediate

Range Neutron Flux channels inoperable. F.1.1 Place one inoperable channel in bypass or trip.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND F.1.2 With two channels inoperable, place one channel in bypass and one channel in trip.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OR F.2 Reduce THERMAL POWER to < P-6.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OR F.3 Increase THERMAL POWER to > P-10.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months G. THERMAL POWER between P-6 and P-10, three Intermediate

Range Neutron Flux channels inoperable. G.1 Suspend operations involving positive reactivity additions.

Immediately AND G.2 Reduce THERMAL POWER to < P-6.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 4 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME H. THERMAL POWER

< P-6, one or two

Intermediate Range Neutron Flux channels inoperable. H.1 Restore three of four channels to OPERABLE status. Prior to increasing THERMAL POWER to

> P-6 I. One or two Source Range Neutron Flux channels inoperable. I.1 Suspend operations involving positive reactivity additions.

Immediately J. Three Source Range Neutron Flux channels inoperable. J.1 Open RTBs. Immediately K. One or two channels inoperable. K.1.1 Place one inoperable channel in bypass or trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND K.1.2 With two channels inoperable, place one channel in bypass and one channel in trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR K.2 Reduce THERMAL POWER to < P-10.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months L. One or two channels/ divisions inoperable. L.1 Restore three of four channels/divisions to OPERABLE status.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR L.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 5 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME M. One or two interlock channels inoperable. M.1 Verify the interlocks are in required state for existing plant conditions.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR M.2.1 Place the Functions associated with one

inoperable interlock channel in bypass or trip.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND M.2.2 With two interlock channels inoperable, place the Functions associated with one inoperable interlock channel in bypass and with one inoperable interlock channel in trip.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months OR M.3 Be in MODE 3. 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months N. One division inoperable. N.1 Open RTBs in inoperable division.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR N.2.1 Be in MODE 3, 4, or 5. 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months AND N.2.2 Open RTBs. 14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 6 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME O. Two divisions inoperable. O.1 Restore three of four divisions to OPERABLE status. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR O.2.1 Be in MODE 3, 4, or 5. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND O.2.2 Open RTBs. 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months P. One or two channels/ divisions inoperable. P.1 Restore three of four channels/divisions to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR P.2 Open RTBs. 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months Q. One or two Source Range Neutron Flux channel inoperable. Q.1 Restore three of four channels to OPERABLE status. 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months OR Q.2 Open RTBs. 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months R. Required Source Range Neutron Flux channel inoperable. R.1 Suspend operations involving positive reactivity additions.

Immediately AND R.2 Close unborated water source isolation valves.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND R.3 Perform SR 3.1.1.1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter

Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 7 SURVEILLANCE REQUIREMENTS - NOTE - Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2 ----------------------------------------------------------------------- - NOTES - 1. Adjust nuclear instrument channel in the Protection and Safety Monitoring System (PMS) if absolute difference is > 1% RTP. 2. Required to be met within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reaching 15% RTP. 3. If the calorimetric heat balance is < 70% RTP, and if the nuclear instrumentation channel indicated power is: a. lower than the calorimetric measurement by > 1%, then adjust the nuclear instrumentation channel upward to match

the calorimetric measurement. b. higher than the calorimetric measurement, then no adjustment is required. -----------------------------------------------------------------------

Compare results of calorimetric heat balance to nuclear instrument channel output.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 8 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.1.3 ----------------------------------------------------------------------- - NOTES - 1. Adjust the conversion factor, T°, in the T power calculation (qT) if absolute difference between qT and the calorimetric measurement is > 1% RTP. 2. Required to be met within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reaching 50% RTP. 3. If the calorimetric heat balance is < 70% RTP, and if qT is: a. lower than the calorimetric measurement by > 5%, then adjust T° to match the calorimetric measurement.

b. higher than the calorimetric measurement, then no adjustment is required. -----------------------------------------------------------------------

Compare results of calorimetric heat balance to the T power calculation (qT) output.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.4 ----------------------------------------------------------------------- - NOTES - 1. Adjust nuclear instrument channel in PMS if absolute difference is 3% AFD. 2. Required to be met within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after reaching 20% RTP. -----------------------------------------------------------------------

Compare results of the incore detector measurements to nuclear instrument channel AXIAL FLUX DIFFERENCE. 31 effective full power days (EFPD)

Technical Specifications RTS Instrumentation

Point Unit 7 3.3.1 - 12 Table 3.3.1-1 (page 1 of 4) Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 1. Manual Reactor Trip 1,2 2 B SR 3.3.1.12 3(a),4(a),5(a) 2 C SR 3.3.1.12 2. Power Range Neutron Flux a. High Setpoint 1,2 4 D SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.13 b. Low Setpoint 1(b),2 4 E SR 3.3.1.1 SR 3.3.1.9 SR 3.3.1.11 SR 3.3.1.13 3. Power Range Neutron Flux High Positive Rate 1,2 4 E SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.13 4. Intermediate Range Neutron Flux 1(b),2 (c) 4 F,G SR 3.3.1.1 SR 3.3.1.9 SR 3.3.1.11 SR 3.3.1.13 2(d) 4 H SR 3.3.1.1 SR 3.3.1.9 SR 3.3.1.11 SR 3.3.1.13 5. Source Range Neutron Flux High Setpoint 2(d) 4 I,J SR 3.3.1.1 SR 3.3.1.9 SR 3.3.1.11 SR 3.3.1.13 3(a),4(a),5(a) 4 J,Q SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.13 3(e),4(e),5(e) 1 R SR 3.3.1.1 SR 3.3.1.11 (a) With Reactor Trip Breakers (RTBs) closed and Plant Control System capable of rod withdrawal. (b) Below the P-10 (Power Range Neutron Flux) interlocks.

(c) Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(d) Below the P-6 (Intermediate Range Neutron Flux) interlocks. (e) With RTBs open. In this condition, Source Range Function does not provide reactor trip but does provide indication.

Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 13 Table 3.3.1-1 (page 2 of 4) Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 6. Overtemperature T 1,2 4 (2/loop) E SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.4 SR 3.3.1.5 SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.13 7. Overpower T 1,2 4 (2/loop) E SR 3.3.1.1 SR 3.3.1.3 SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.13 8. Pressurizer Pressure a. Low Setpoint 1(f) 4 K SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.13 b. High Setpoint 1,2 4 E SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.13 9. Pressurizer Water Level - High 3 1(f) 4 K SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.13 10. Reactor Coolant Flow - Low 1(f) 4 per hot leg K SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.13 11. Reactor Coolant Pump (RCP) Bearing Water Temperature -

High 1,2 4 per RCP E SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.13 12. RCP Speed - Low 1(f) 4 (1/pump) K SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.13 13. Steam Generator (SG) Narrow Range Water Level - Low 1,2 4 per SG E SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.13 (f) Above the P-10 (Power Range Neutron Flux) interlock.

Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 14 Table 3.3.1-1 (page 3 of 4) Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 14. Steam Generator (SG) Narrow Range Water Level - High 2 1,2(g) 4 per SG E SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.10 SR 3.3.1.13 15. Safeguards Actuation Input from Engineered Safety Feature Actuation System a. Manual 1,2 2 B SR 3.3.1.12 b. Automatic 1,2 4 L SR 3.3.1.7 16. Reactor Trip System Interlocks a. Intermediate Range Neutron Flux, P-6 2 4 M SR 3.3.1.8 SR 3.3.1.11 b. Power Range Neutron Flux, P-10 1,2 4 M SR 3.3.1.8 SR 3.3.1.11 c. Pressurizer Pressure, P-11 1,2 4 M SR 3.3.1.8 SR 3.3.1.11 17. Reactor Trip Breakers 1,2,3(a),4(a),5(a) 4 divisions with 2 RTBs per division N,O SR 3.3.1.6 18. Reactor Trip Breaker (RTB) Undervoltage and Shunt Trip Mechanisms 1,2,3(a),4(a),5(a) 1 each per RTB mechanism N,O SR 3.3.1.6 19. Automatic Trip Logic 1,2 3(a),4(a),5(a) 4 divisions 4 divisions L P SR 3.3.1.7 SR 3.3.1.7 20. ADS Stages 1, 2, and 3 Actuation input from engineered safety feature actuation system a. Manual 1,2,3(a),4(a),5(a) 2 switch sets B SR 3.3.1.12 b. Automatic 1,2 3(a),4(a),5(a) 4 4 L P SR 3.3.1.7 SR 3.3.1.7 (a) With Reactor Trip Breakers closed and Plant Control System capable of rod withdrawal. (g) Above the P-11 (Pressurizer Pressure) interlock.

Technical Specifications RTS Instrumentation

3.3.1 Turkey

Point Unit 7 3.3.1 - 15 Table 3.3.1-1 (page 4 of 4) Reactor Trip System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 21. Core Makeup Tank Actuation input from engineered safety feature actuation system a. Manual 1,2,3(a),4(a),5(a) 2 switch sets B SR 3.3.1.12 b. Automatic 1,2 3(a),4(a),5(a) 4 4 L P SR 3.3.1.7 SR 3.3.1.7 22. Passive Residual Heat Removal Actuation 1,2 4 per valve E SR 3.3.1.11 SR 3.3.1.12 SR 3.3.1.13 (a) With Reactor Trip Breakers (RTBs) closed and Plant Control System capable of rod withdrawal.

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 1

3.3 INSTRUMENTATION

3.3.2 Engineered

Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 The ESFAS instrumentation for each function in Table 3.3.2-1 shall be OPERABLE. APPLICABILITY: According to Table 3.3.2-1. ACTIONS - NOTES - 1. Separate condition entry is allowed for each Function. 2. The Conditions for each Function are given in Table 3.3.2-1. If the Required Actions and associated Completion Times of the first Condition are not met, refer to the second Condition.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with one or more required channels or divisions inoperable. A.1 Enter the Condition referenced in Table 3.3.2-1 for the channel(s) or division(s).

Immediately B. One or two channels or divisions inoperable. B.1 Place one inoperable channel or division in bypass or trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND B.2 With two inoperable channels or divisions, place one inoperable channel or division in bypass and one inoperable channel or division in trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months C. One channel inoperable. C.1 Place inoperable channel in bypass.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. One required division inoperable. D.1 Restore required division to OPERABLE status.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months E. One switch or switch set inoperable. E.1 Restore switch and switch set to OPERABLE status.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months F. One channel inoperable. F.1 Restore channel to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR F.2.1 Verify alternate radiation monitors are OPERABLE.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND F.2.2 Verify main control room isolation, air supply initiation and electrical load de-energization manual controls are OPERABLE.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months G. One switch, switch set, channel, or division inoperable. G.1 Restore switch, switch set, channel, and division to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months H. One channel inoperable. H.1 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months I. One or two channels inoperable. I.1 Place one inoperable channel in bypass or trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND I.2 With two inoperable channels, place one channel in bypass and one channel in trip.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months J. One or two interlock channels inoperable. J.1 Verify the interlocks are in the required state for the existing plant conditions.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME J.2.1 Place the Functions associated with one

inoperable interlock channel in bypass or trip.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months AND J.2.2 With two interlock channels inoperable, place the Functions associated with one inoperable interlock channel in bypass and with one inoperable interlock channel in trip.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months K. Required Action and associated Completion Time

not met. K.1 ------------------------------------ - NOTE - LCO 3.0.8 is not applicable. ------------------------------------

Suspend movement of irradiated fuel assemblies.

Immediately L. Required Action and associated Completion Time

not met. L.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months M. Required Action and associated Completion Time not met. M.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND M.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months N. Required Action and associated Completion Time not met. N.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND N.2 Be in MODE 4 with the Reactor Coolant System (RCS) cooling provided by the Normal Residual Heat Removal System (RNS).

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 4 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME O. Required Action and associated Completion Time not met. O.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND O.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months P. Required Action and associated Completion Time not met. --------------------------------------------- - NOTE - Flow path(s) may be unisolated intermittently under administrative controls. ---------------------------------------------

P.1 Isolate the affected flow path(s). 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND P.2.1 Isolate the affected flow path(s) by use of at least one closed and deactivated automatic valve, closed manual

valve, blind flange, or

check valve with flow through the valve secured.

7 days OR P.2.2 Verify the affected flow path is isolated.

Once per 7 days Q. Required Action and associated Completion Time

not met. Q.1 ------------------------------------ - NOTE - Flow path(s) may be unisolated intermittently under administrative controls. ------------------------------------

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 5 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME Isolate the affected flow path(s) by use of at least one closed manual or closed and de-activated automatic valve.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR Q.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Q.2.2 Be in MODE 4. 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months R. Required Action and associated Completion Time

not met. R.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND --------------------------------------------- - NOTE - Flow path(s) may be unisolated intermittently under administrative controls. ---------------------------------------------

R.2.1.1Isolate the affected flow path(s). 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND R.2.1.2Verify the affected flow path is isolated.

Once per 7 days OR R.2.2 Be in MODE 4 with the RCS cooling provided by the RNS. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 6 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME S. Required Action and associated Completion Time not met. S.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND S.2.1.1 Be in MODE 4 with the RCS cooling provided by the RNS. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND --------------------------------------------- - NOTE - Flow path(s) may be unisolated intermittently under administrative controls. ---------------------------------------------

S.2.1.2 Isolate the affected flow path(s). 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AND S.2.1.3 Verify the affected flow path is isolated.

Once per 7 days OR S.2.2 Be in MODE 5. 42 hours4.861111e-4 days 0.0117 hours 6.944444e-5 weeks 1.5981e-5 months T. Required Action and associated Completion Time not met. --------------------------------------------- - NOTE - Flow path(s) may be unisolated intermittently under administrative controls. ---------------------------------------------

T.1.1 Isolate the affected flow path(s). 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND

Technical Specifications ESFAS Instrumentation

Point Unit 7 3.3.2 - 10 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME Isolate the affected flow path(s) by use of at least one closed manual or closed and deactivated automatic valve.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR Z.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Z.2.2 Be in MODE 4 with the RCS cooling provided by the RNS. 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months AA. Required Action and associated Completion Time

not met. --------------------------------------------- - NOTE - Flow path(s) may be unisolated intermittently under administrative controls. ---------------------------------------------

AA.1.1 Isolate the affected flow path(s). 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND AA.1.2.1 Isolate the affected flow path(s) by use of at least one closed and

deactivated automatic

valve, closed manual

valve, blind flange, or check valve with flow through the valve secured. 7 days OR Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 11 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME AA.1.2.2 Verify the affected flow path is isolated.

Once per 7 days OR AA.2.1 If in MODE 4, be in MODE 5. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND AA.2.2 If in MODE 4 or 5, initiate action to establish a pressurizer level 20%. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND AA.2.3 If in MODE 6, initiate action to be in MODE 6

with the water level 23 feet above the top of the reactor vessel flange.

Immediately BB. One channel inoperable. BB.1 Place channel in bypass. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND BB.2 Continuously monitor hot leg level.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months CC. Required Action and associated Completion Time not met. CC.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND CC.2 Be in MODE 5 or 6. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months AND CC.3 Open a containment air flow path 6 inches in diameter.

44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 12 SURVEILLANCE REQUIREMENTS - NOTE - Refer to Table 3.3.2-1 to determine which SRs apply for each Engineered Safety Features (ESF) Function.

SURVEILLANCE FREQUENCY SR 3.3.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.2.2 Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.2.3 ----------------------------------------------------------------------- - NOTE - Verification of setpoint not required for manual initiation functions. -----------------------------------------------------------------------

Perform TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT).

24 months SR 3.3.2.4 ----------------------------------------------------------------------- - NOTE - This surveillance shall include verification that the time constants are adjusted to the prescribed values. -----------------------------------------------------------------------

Perform CHANNEL CALIBRATION in accordance with Setpoint Program.

24 months SR 3.3.2.5 Perform CHANNEL OPERATIONAL TEST (COT) in accordance with Setpoint Program.

92 days SR 3.3.2.6 Verify ESFAS RESPONSE TIMES are within limit. 24 months on a STAGGERED TEST BASIS SR 3.3.2.7 ----------------------------------------------------------------------- - NOTE - This Surveillance is not required to be performed for actuated equipment which is included in the Inservice Test (IST) Program. -----------------------------------------------------------------------

Perform ACTUATION DEVICE TEST. 24 months

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 13 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.2.8 Perform ACTUATION DEVICE TEST for squib valves. 24 months SR 3.3.2.9 Perform ACTUATION DEVICE TEST for pressurizer heater circuit breakers.

24 months

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 14 Table 3.3.2-1 (page 1 of 13) Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 1. Safeguards Actuation a. Manual Initiation 1,2,3,4 2 switches E,O SR 3.3.2.3 5 2 switches G,Y SR 3.3.2.3 b. Containment Pressure -

High 2 1,2,3,4 4 B,O SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 c. Pressurizer Pressure - Low 1,2,3(a) 4 B,M SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 d. Steam Line Pressure - Low 1,2,3(a) 4 per steam line B,M SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 e. RCS Cold Leg Temperature (Tcold) - Low 1,2,3(a) 4 per loop B,M SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 (a) Above the P-11 (Pressurizer Pressure) interlock, when the RCS boron concentration is below that necessary to meet the SDM requirements at an RCS temperature of 200°F.

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 15 Table 3.3.2-1 (page 2 of 13) Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 2. Core Makeup Tank (CMT)

Actuation a. Manual Initiation 1,2,3,4(b) 2 switches E,N SR 3.3.2.3 4 (c), 5(d) 2 switches E,U SR 3.3.2.3 b. Pressurizer Water Level - Low 2 1,2,3,4(b) 4 B,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 4 (c), 5(d) 4 B,V SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 c. Safeguards Actuation 1,2,3,4,5(d) Refer to Function 1 (Safeguards Ac tuation) for initiating functions and requirements. d. ADS Stages 1, 2, & 3 Actuation 1,2,3,4,5(d) Refer to Function 9 (ADS Stages 1, 2 & 3 Actuation) for all initiating functions and requirements. 3. Containment Isolation

a. Manual Initiation 1,2,3,4 2 switches E,O SR 3.3.2.3 5(e), 6(e) 2 switches G,Y SR 3.3.2.3 b. Manual Initiation of Passive Containment Cooling 1,2,3,4,5(e,f),6(e,f) Refer to Function 12.a (Passive Containment Cooling Actuation) for initiating functions and requirements. c. Safeguards Actuation 1,2,3,4,5(e) Refer to Function 1 (Safeguards Ac tuation) for initiating functions and requirements.

(b) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS). (c) With the RCS being cooled by the RNS. (d) With the RCS pressure boundary intact. (e) Not applicable for valve isolation Functions whose associated flow path is isolated. (f) With decay heat > 6.0 MWt.

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 16 Table 3.3.2-1 (page 3 of 13) Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 4. Steam Line Isolation a. Manual Initiation 1,2(h),3(h),4(h) 2 switches E,S SR 3.3.2.3 b. Containment Pressure -

High 2 1,2(h),3(h),4(h) 4 B,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 c. Steam Line Pressure (1) Steam Line Pressure - Low 1,2(h),3(a,h) 4 per steam line B,M SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 (2) Steam Line Pressure - Negative Rate - High 3(g,h) 4 per steam line B,M SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 d. Tcold - Low 1,2(h),3(a,h) 4 per loop B,M SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 5. Turbine Trip

a. Manual Main Feedwater Isolation 1,2 Refer to Function 6.a (Manual Main Feedwater Control Valve Isolation) for requirements. b. SG Narrow Range Water Level - High 2 1,2 4 per SG B,L SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6

c. Reactor Trip 1,2 Refer to Function 18.b (ESFAS Interlocks, Reactor Trip, P-4) for requirements. (a) Above the P-11 (Pressurizer Pressure) interlock, when the RCS boron concentration is below that necessary to meet the SDM requirements at an RCS temperature of 200°F.

(g) Below the P-11 (Pressurizer Pressure) interlock. (h) Not applicable if all MSIVs are closed.

Technical Specifications ESFAS Instrumentation

Point Unit 7 3.3.2 - 20 Table 3.3.2-1 (page 7 of 13) Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 11. Reactor Coolant Pump Trip a. ADS Stages 1, 2 & 3 Actuation Refer to Function 9 (ADS Stages 1, 2 & 3 Actuation) for initiating functions and requirements. b. Reactor Coolant Pump Bearing Water Temperature - High 1,2 4 per RCP B,L SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 c. Manual CMT Actuation Refer to Function 2.a (Manual CMT Actuation) for requirements. d. Pressurizer Water Level - Low 2 1,2,3,4(b) 4 B,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 4 (c),5(b,l) 4 B,V SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 e. Safeguards Actuation Refer to Function 1 (Safeguards Actuation) for initiating functions and requirements. 12. Passive Containment Cooling Actuation a. Manual Initiation 1,2,3,4 2 switches E,O SR 3.3.2.3 5(f),6(f) 2 switches G,Y SR 3.3.2.3 b. Containment Pressure -

High 2 1,2,3,4 4 B,O SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 (b) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS). (c) With the RCS being cooled by the RNS.

(f) With decay heat > 6.0 MWt.

(l) With pressurizer level 20%.

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 21 Table 3.3.2-1 (page 8 of 13) Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 13. Passive Residual Heat Removal Heat Exchanger Actuation a. Manual Initiation 1,2,3,4 5(d) 2 switches 2 switches E,O E,U SR 3.3.2.3 SR 3.3.2.3 b. SG Narrow Range Water Level - Low 1,2,3,4(b) 4 per SG B,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 Coincident with Startup Feedwater Flow - Low 1,2,3,4(b) 2 per feedwater line H,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 c. SG Wide Range Water Level - Low 1,2,3,4(b) 4 per SG B,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 d. ADS Stages 1, 2 & 3 Actuation 1,2,3,4,5(d) Refer to Function 9 (ADS Stages 1, 2 & 3 Actuation) for initiating functions and requirements. e. CMT Actuation Refer to Function 2 (CMT Actuation) for initiating functions and requirements. f. Pressurizer Water Level, High 3 1,2,3,4(b,m) 4 B,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 14. SG Blowdown Isolation a. Passive Residual Heat Removal Heat Exchanger

Actuation 1,2,3,4(b,e) Refer to Function 13 (Passive Residual Heat Removal Heat Exchanger Actuation) for all initiating functions and requirements. b. SG Narrow Range Water Level - Low 1,2,3,4(b,e) 4 per SG B,R SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 (b) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS). (d) With the RCS pressure boundary intact. (e) Not applicable for valve isolation Functions whose associated flow path is isolated. (m) Above the P-19 (RCS Pressure) interlock.

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 22 Table 3.3.2-1 (page 9 of 13) Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 15. Boron Dilution Block a. Source Range Neutron Flux Doubling 2(n),3(n, e),4(e) 4 B,T SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 5(e) 4 B,P SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 b. Reactor Trip Refer to Function 18.b (ESFAS Interlocks, Reactor Trip, P-4) for all requirements. 16. Chemical Volume and Control System Makeup Isolation a. SG Narrow Range Water Level - High 2 1,2,3(e),4(b,e) 4 per SG B,R SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 b. Pressurizer Water Level -

High 1 1,2,3(e) 4 B,Q SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 Coincident with Safeguards Actuation 1,2,3(e) Refer to Function 1 (Safeguards Actuation) for initiating functions and requirements. c. Pressurizer Water Level -

High 2 1,2,3,4(b,e,m) 4 B,T SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 d. Containment Radioactivity -

High 2 1,2,3(e) 4 B,Q SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 e. Manual Initiation 1,2,3(e),4(b,e) 2 switches E,R SR 3.3.2.3

f. Source Range Neutron Flux Doubling Refer to Function 15.a (Boron Dilution Block, Source Range Neutron Flux Doubling) for all requirements.

g. SG Narrow Range Water Level High 1,2,3(e),4(b,e) 4 per SG B,R SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 Coincident with Reactor Trip (P-4) Refer to Function 18.b (ESFAS Interlocks, Reactor Trip, P-4) for all requirements. (b) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS). (e) Not applicable for valve isolation Functions whose associated flow path is isolated. (m) Above the P-19 (RCS Pressure) interlock. (n) Not applicable when critical or during intentional approach to criticality.

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 23 Table 3.3.2-1 (page 10 of 13) Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 17. Normal Residual Heat Removal System Isolation a. Containment Radioactivity -

High 2 1,2,3(e) 4 B,Q SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 b. Safeguards Actuation 1,2,3(e) Refer to Function 1 (Safeguards Actuation) for all initiating functions and requirements. c. Manual Initiation 1,2,3(e) 2 switch sets E,Q SR 3.3.2.3 18. ESFAS Interlocks a. Reactor Trip Breaker Open, P-3 1,2,3 3 divisions D,M SR 3.3.2.3 b. Reactor Trip, P-4 1,2,3 3 divisions D,M SR 3.3.2.3 c. Intermediate Range Neutron Flux, P-6 2 4 J,L SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 d. Reactor Coolant Average Temperature, P-8 2, 3(e),4(e) 4 J,T SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 5(e) 4 J,P SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 e. Pressurizer Pressure, P-11 1,2,3 4 J,M SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 f. Pressurizer Level, P-12 1,2,3 4 J,M SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 4,5,6 4 BB,Y SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 g. RCS Pressure, P-19 1,2,3,4(b) 4 J,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 19. Containment Air Filtration System Isolation a. Containment Radioactivity -

High 1 1,2,3,4(b) 4 B,Z SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 b. Containment Isolation Refer to Function 3 (Containment Isolation) for initiating functions and requirements. (b) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS). (e) Not applicable for valve isolation Functions whose associated flow path is isolated.

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 24 Table 3.3.2-1 (page 11 of 13) Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 20. Main Control Room Isolation, Air Supply Initiation and Electrical Load De-energization a. Main Control Room Air Supply Radiation - High 2 1,2,3,4 2 F,O SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 Note (o) 2 G,K SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 21. Auxiliary Spray and Purification Line Isolation a. Pressurizer Water Level - Low 1 1,2 4 B,L SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 b. Manual Initiation 1,2 Refer to Function 16.e (Manual Chemical Volume Control System (Makeup Isolation) for requirements. 22. In-Containment Refueling Water Storage Tank (IRWST) Injection

Line Valve Actuation a. Manual Initiation 1,2,3,4(b) 2 switch sets E,N SR 3.3.2.3 4 (c),5,6 2 switch sets G,Y SR 3.3.2.3 b. ADS 4th Stage Actuation Refer to Function 10 (ADS 4th Stage Actuation) for initiating functions and requirements.

23. IRWST Containment Recirculation Valve Actuation a. Manual Initiation 1,2,3,4(b) 2 switch sets E,N SR 3.3.2.3 4 (c),5,6 2 switch sets G,Y SR 3.3.2.3

b. ADS Stage 4 Actuation Refer to Function 10 (ADS Stage 4 Actuation) for all initiating functions and requirements.

Coincident with IRWST Level - Low 3 1,2,3,4(b) 4 B,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 4 (c),5 (j),6 (j) 4 I,Y SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 (b) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS). (c) With the RCS being cooled by the RNS.

(j) Not applicable when the required ADS valves are open. See LCO 3.4.12 and LCO 3.4.13 for ADS valve and equivalent relief area requirements. (o) During movement of irradiated fuel assemblies.

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 25 Table 3.3.2-1 (page 12 of 13) Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 24. Refueling Cavity Isolation a. Spent Fuel Pool Level - Low 6 3 H,P SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 25. ESF Coincidence Logic a. Coincidence Logic 1,2,3,4 4 divisions, 1 battery-backed subsystem per division D,O SR 3.3.2.2 5,6 4 divisions, 1 battery-backed subsystem per division G,W SR 3.3.2.2 26. ESF Actuation a. ESF Actuation Subsystem 1,2,3,4 4 divisions, 1 battery-backed subsystem per division D,O SR 3.3.2.2 SR 3.3.2.7 SR 3.3.2.8 5,6 4 divisions, 1 battery-backed subsystem per division G,W SR 3.3.2.2 SR 3.3.2.7 27. Pressurizer Heater Trip a. Core Makeup Tank Actuation 1,2,3,4(b,m) Refer to Function 2 (Core Makeup Tank Actuation) for all initiating functions and requirements. In addition to the requirements for Function 2, SR 3.3.2.9 also applies.

b. Pressurizer Water Level, High 3 1,2,3,4(b,m) 4 B,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6

28. Chemical and Volume Control System Letdown Isolation a. Hot Leg Level - Low 1 4(c,p),5(p),6(p,q) 1 per loop C,AA SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 (b) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS). (c) With the RCS being cooled by the RNS. (m) Above the P-19 (RCS Pressure) interlock.

(p) Below the P-12 (Pressurizer Level) interlock. (q) With the water level < 23 feet above the top of the reactor vessel flange.

Technical Specifications ESFAS Instrumentation

3.3.2 Turkey

Point Unit 7 3.3.2 - 26 Table 3.3.2-1 (page 13 of 13) Engineered Safeguards Actuation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQUIREMENTS 29. SG Power Operated Relief Valve and Block Valve Isolation a. Manual Initiation 1,2,3,4(b) 2 switches E,N SR 3.3.2.3 b. Steam Line Pressure - Low 1,2,3,4(b) 4 per steam lineB,N SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 30. Component Cooling Water System Containment Isolation Valve Closure a. Reactor Coolant Pump Bearing Water Temperature - High 1,2,3,4 4 per RCP B,T SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 31. Containment Vacuum Relief Valve Actuation a. Containment Pressure -Low 2 1,2,3,4,5 (r),6 (r) 4 B,CC SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2.6 b. Manual Initiation 1,2,3,4,5 (r),6 (r) 2 switches E,CC SR 3.3.2.3 (b) With the RCS not being cooled by the Normal Residual Heat Removal System (RNS). (r) Without an open containment air flow path 6 inches in diameter.

Technical Specifications PAM Instrumentation

3.3.3 Turkey

Point Unit 7 3.3.3 - 1

3.3 INSTRUMENTATION

3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. ACTIONS - NOTES - 1. LCO 3.0.4 not applicable. 2. Separate Condition entry is allowed for each Function.

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

30 days B. Required Action and associated Completion Time of Condition A not met. B.1 Initiate action in accordance with Specification 5.6.7.

Immediately C. One or more Functions with two required channels inoperable. C.1 Restore one channel to OPERABLE status.

7 days D. Required Action and associated Completion Time of Condition C not met. D.1 Enter the Condition referenced in Table 3.3.3-1 for the channel.

Immediately E. As required by Required Action D.1 and

referenced in Table 3.3.3-1.

E.1 AND E.2 Be in MODE 3.

Be in MODE 4.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours Technical Specifications PAM Instrumentation

3.3.3 Turkey

Point Unit 7 3.3.3 - 2 SURVEILLANCE REQUIREMENTS - NOTE - SR 3.3.3.1 and SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1.

SURVEILLANCE FREQUENCY SR 3.3.3.1 Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.

31 days SR 3.3.3.2 ----------------------------------------------------------------------- - NOTE - Neutron detectors are excluded from CHANNEL CALIBRATION. -----------------------------------------------------------------------

Perform CHANNEL CALIBRATION. 24 months

Technical Specifications PAM Instrumentation

3.3.3 Turkey

Point Unit 7 3.3.3 - 3 Table 3.3.3-1 (page 1 of 1) Post-Accident Monitoring Instrumentation FUNCTION REQUIRED CHANNELS/ DIVISIONS CONDITION REFERENCED FROM REQUIRED ACTION D.1 1. Neutron Flux (Intermediate Range) 2 E 2. Reactor Coolant System (RCS) Hot Leg Temperature (Wide Range) 2 E 3. RCS Cold Leg Temperature (Wide Range) 2 E

4. RCS Pressure (Wide Range) 2 E 5. Pressurizer Pressure and RCS Subcooling Monitor(a) 2 E 6. Containment Water Level 2 E

7. Containment Pressure 2 E 8. Containment Pressure (Extended Range) 2 E 9. Containment Area Radiation (High Range) 2 E

10. Pressurizer Level and Associated Reference Leg Temperature 2 E 11. In-Containment Refueling Water Storage Tank (IRWST) Water Level 2 E 12. Passive Residual Heat Removal (PRHR) Flow and PRHR Outlet Temperature 2 flow & 1 temperature E 13. Core Exit Temperature -- Quadrant 1 2(b) E 14. Core Exit Temperature -- Quadrant 2 2(b) E 15. Core Exit Temperature -- Quadrant 3 2(b) E 16. Core Exit Temperature -- Quadrant 4 2(b) E 17. Passive Containment Cooling System (PCS) Storage Tank Level and PCS Flow 2 level & 1 flow E 18. Remotely Operated Containment Isolation Valve Position 1/valve (c) E 19. IRWST to Normal Residual Heat Removal System (RNS) Suction Valve Status 2 E (a) RCS Subcooling calculated from pressurizer pressure and RCS hot leg temperature. (b) A channel consists of two thermocouples within a single division. Each quadrant contains two divi sions. The minimum requirement is two OPERABLE thermocouples in each of the two divisions. (c) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

Technical Specifications RSW 3.3.4 Turkey Point Unit 7 3.3.4 - 1

3.3 INSTRUMENTATION

3.3.4 Remote

Shutdown Workstation (RSW) LCO 3.3.4 The RSW shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. MODE 4 with Reactor Coolant System (RCS) average temperature (Tavg) 350°F.

ACTIONS - NOTE - LCO 3.0.4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. RSW inoperable. A.1 Restore to OPERABLE status. 30 days B. Required Action and associated Completion Time not met. B.1 AND B.2 Be in MODE 3.

Be in MODE 4 with Tavg < 350°F.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Verify each required transfer switch is capable of performing the required function.

24 months SR 3.3.4.2 Verify that the RSW communicates indication and controls with Division A, B, C and D of the Protection and Safety Monitoring System (PMS).

24 months SR 3.3.4.3 Verify the OPERABILITY of the RSW hardware and software.

24 months Technical Specifications RSW 3.3.4 Turkey Point Unit 7 3.3.4 - 2 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.3.4.4 Perform TADOT of the reactor trip breaker open/closed indication.

24 months

Technical Specifications DAS Manual Controls

3.3.5 Turkey

Point Unit 7 3.3.5 - 1

3.3 INSTRUMENTATION

3.3.5 Diverse

Actuation System (DAS) Manual Controls LCO 3.3.5 The DAS manual controls for each function in Table 3.3.5-1 shall be OPERABLE. APPLICABILITY: According to Table 3.3.5-1. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more manual DAS controls inoperable. A.1 Restore DAS manual controls to OPERABLE status. 30 days B. Required Action and associated Completion Time of Condition A not met for inoperable DAS manual reactor trip control. B.1 AND Perform SR 3.3.1.6.

Once per 31 days on a STAGGERED TEST BASIS B.2 Restore all controls to OPERABLE status.

Prior to entering MODE 2 following next MODE 5 entry C. Required Action and associated Completion Time of Condition A not

met for inoperable DAS

manual actuation control other than reactor trip.

C.1 AND Perform SR 3.3.2.2. Once per 31 days on a STAGGERED TEST BASIS C.2 Restore all controls to OPERABLE status.

Prior to entering MODE 2 following next MODE 5 entry D. Required Action and associated Completion Time of Condition B not met. D.1 AND Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Required Action and associated Completion Time of Condition C not

met.

Technical Specifications DAS Manual Controls

3.3.5 Turkey

Point Unit 7 3.3.5 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.5.1 ----------------------------------------------------------------------- - NOTE - Verification of setpoint not required. -----------------------------------------------------------------------

Perform TRIP ACTUATION DEVICE OPERATIONAL TEST (TADOT).

24 months

Technical Specifications DAS Manual Controls

3.3.5 Turkey

Point Unit 7 3.3.5 - 3 Table 3.3.5-1 (page 1 of 1) DAS Manual Controls FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CONTROLS 1. Reactor trip manual controls 1,2 2 switches 2. Passive Residual Heat Removal Heat Exchanger (PRHR HX) control and In-Containment Refueling Water Storage Tank (IRWST) gutter control valves 1,2,3,4,5(a) 2 switches 3. Core Makeup Tank (CMT) isolation valves 1,2,3,4,5(a) 2 switches 4. Automatic Depressurization System (ADS) stage 1 valves 1,2,3,4,5(a) 2 switches 5. ADS stage 2 valves 1,2,3,4,5(a) 2 switches 6. ADS stage 3 valves 1,2,3,4,5(a) 2 switches 7. ADS stage 4 valves 1,2,3,4,5,6(c) 2 switches 8. IRWST injection squib valves 1,2,3,4,5,6 2 switches 9. Containment recirculation valves 1,2,3,4,5,6 2 switches 10. Passive containment cooling drain valves 1,2,3,4,5(b),6(b) 2 switches 11. Selected containment isolation valves 1,2,3,4,5,6 2 switches (a) With Reactor Coolant System (RCS) pressure boundary intact.

(b) With the calculated reactor decay heat > 6.0 MWt. (c) In MODE 6 with reactor internals in place.

Technical Specifications RCS Pressure, Temperature, and Flow DNB Limits

3.4.1 Turkey

Point Unit 7 3.4.1 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature, and RCS total flow rate shall be within the limits specified

below: a. Pressurizer Pressure is greater than or equal to the limit specified in the COLR b. RCS Average Temperature is less than or equal to the limit specified in the COLR, and c. RCS total flow rate 301,670 gpm and greater than or equal to the limit specified in the COLR. APPLICABILITY: MODE 1. -------------------------------------------------------------------------------------------------- - NOTE - Pressurizer pressure limit does not apply during:

a. THERMAL POWER ramp > 5% RTP per minute, or

b. THERMAL POWER step > 10% RTP. -------------------------------------------------------------------------------------------------- ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB parameters not within limits. A.1 Restore RCS DNB parameter(s) to within limit.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months B. Required Action and associated Completion Time

not met. B.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

Technical Specifications RCS Pressure, Temperature, and Flow DNB Limits

3.4.1 Turkey

Point Unit 7 3.4.1 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is greater than or equal to the limit specified in the COLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.2 Verify RCS average temperature is less than or equal to the limit specified in the COLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.3 Verify RCS total flow rate is 301,670 gpm and greater than or equal to the limit specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.1.4 Perform a CHANNEL CALIBRATION of RCS total flow rate indication (differential pressure) channels.

24 months SR 3.4.1.5 ----------------------------------------------------------------------- - NOTE - Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after 90% RTP. -----------------------------------------------------------------------

Verify that RCS total flow rate is 301,670 gpm and greater than or equal to the limit specified in the COLR as determined by precision heat balance or RCS total flow rate indication (differential pressure) measurements.

24 months

Technical Specifications RCS Minimum Temperature for Criticality

3.4.2 Turkey

Point Unit 7 3.4.2 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.2 RCS Minimum Temperature for Criticality LCO 3.4.2 Each RCS loop average temperature (Tavg) shall be 551°F. APPLICABILITY: MODE 1, MODE 2 with keff 1.0. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tavg in one or more RCS loops not within limit. A.1 Be in MODE 2 with keff < 1.0. 30 minutes SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify RCS Tavg in each loop 551°F. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Technical Specifications RCS P/T Limits

3.4.3 Turkey

Point Unit 7 3.4.3 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 RCS pressure, RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR. APPLICABILITY: At all times. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------------------------- - NOTE - Required Action A.2 shall be completed whenever this Condition is entered. -------------------------------- Requirements of LCO not met in MODE 1, 2, 3, or 4. A.1 Restore parameters to within limits.

30 minutes AND A.2 Determine RCS is acceptable for continued operation.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and associated Completion Time of Condition A not met.

B.1 AND B.2 Be in MODE 3.

Be in MODE 4 with RCS pressure < 500 psig.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 24 hours C. -------------------------------- - NOTE - Required Action C.2 shall be completed whenever this Condition is entered. -------------------------------- Requirements of LCO not met any time in other than MODE 1, 2, 3, or 4. C.1 Initiate action to restore parameter(s) to within limits. Immediately AND C.2 Determine RCS is acceptable for continued operation.

Prior to entering MODE 4 Technical Specifications RCS P/T Limits

3.4.3 Turkey

Point Unit 7 3.4.3 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 ----------------------------------------------------------------------- - NOTE - Only required to be performed during RCS heatup and cooldown operations and inservice leak and hydrostatic testing. -----------------------------------------------------------------------

Verify RCS pressure, RCS temperature, and RCS heatup and cooldown rates within limits specified in the PTLR.

30 minutes

Technical Specifications RCS Loops 3.4.4 Turkey Point Unit 7 3.4.4 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.4 RCS Loops LCO 3.4.4 Two RCS loops shall be OPERABLE with four Reactor Coolant Pumps (RCPs) in operation with variable speed control bypassed.

- NOTES - 1. No RCP shall be started when the reactor trip breakers are closed. 2. No RCP shall be started when the RCS temperature is 350°F unless pressurizer level is < 92%. 3. No RCP shall be started with any RCS cold leg temperature 350°F unless the secondary side water temperature of each steam

generator (SG) is 50°F above each of the RCS cold leg temperatures and the RCP is started at 25% of RCP speed.

4. All RCPs may be de-energized in MODE 3, 4, or 5 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided: a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and b. Core outlet temperature is maintained at least 10°F below saturation temperature. --------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 1 and 2, MODES 3, 4, and 5, whenever the reactor trip breakers are closed. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. -------------------------------- - NOTE - Required Action A.1 must be completed whenever Condition A is

entered. -------------------------------- Requirements of LCO not met in MODE 1 or 2. A.1 Be in MODE 3 with the reactor trip breakers open.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Technical Specifications RCS Loops 3.4.4 Turkey Point Unit 7 3.4.4 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. -------------------------------- - NOTE - Required Action B.1 must be completed

whenever Condition B is

entered. -------------------------------- Requirements of LCO not met in MODE 3, 4, or 5. B.1 Open reactor trip breakers. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation with variable speed control bypassed.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Technical Specifications Pressurizer

3.4.5 Turkey

Point Unit 7 3.4.5 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.5 Pressurizer LCO 3.4.5 The pressurizer water level shall be 92% of span. APPLICABILITY: MODES 1, 2, and 3. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water level not within limit. A.1 Restore pressurizer water level within limit.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR A.2.1 Be in MODE 3 with reactor trip breakers open.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.2.2 Be in MODE 4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify pressurizer water level 92% of span. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Technical Specifications Pressurizer Safety Valves

3.4.6 Turkey

Point Unit 7 3.4.6 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.6 Pressurizer Safety Valves LCO 3.4.6 Two pressurizer safety valves shall be OPERABLE with lift settings 2460 psig and 2510 psig. APPLICABILITY: MODES 1, 2, and 3. MODE 4 with Normal Residual Heat Removal System (RNS) isolated or RCS temperature 275°F. -------------------------------------------------------------------------------------------------- - NOTE - The lift settings are not required to be within the LCO limits during MODES 3 and 4 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions. This exception is allowed for 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months following entry into MODE 3, provided a preliminary cold setting was made prior to heatup. -------------------------------------------------------------------------------------------------- ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety valve inoperable. A.1 Restore valve to OPERABLE status.

15 minutes B. Required Action and associated Completion Time

not met. OR Two pressurizer safety valves inoperable.

B.1 AND B.2 Be in MODE 3.

Be in MODE 4 with RNS aligned to the RCS and RCS temperature < 275°F.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 24 hours Technical Specifications Pressurizer Safety Valves

3.4.6 Turkey

Point Unit 7 3.4.6 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify each pressurizer safety valve OPERABLE in accordance with the Inservice Testing Program.

Following testing, lift settings shall be within +/-1%. In accordance with the Inservice Testing Program

Technical Specifications RCS Operational LEAKAGE

3.4.7 Turkey

Point Unit 7 3.4.7 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.7 RCS Operational LEAKAGE LCO 3.4.7 RCS operational LEAKAGE shall be limited to: a. No pressure boundary LEAKAGE,

b. 0.5 gpm unidentified LEAKAGE, c. 10 gpm identified LEAKAGE from the RCS, d. 150 gallons per day primary to secondary LEAKAGE through any one Steam Generator (SG), and e. 500 gallons per day primary to In-Containment Refueling Water Storage Tank (IRWST) LEAKAGE through the passive residual heat removal heat exchanger (PRHR HX). APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational LEAKAGE not within limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE. A.1 Reduce LEAKAGE to within limits.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and associated Completion Time

not met. OR Pressure boundary LEAKAGE exists. OR Primary to secondary LEAKAGE not within limit. B.1 AND B.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours Technical Specifications RCS Operational LEAKAGE

3.4.7 Turkey

Point Unit 7 3.4.7 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 ----------------------------------------------------------------------- - NOTES - 1. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation. 2. Not applicable to primary to secondary LEAKAGE. -----------------------------------------------------------------------

Verify RCS operational LEAKAGE is within limits by performance of RCS water inventory balance.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months SR 3.4.7.2 ----------------------------------------------------------------------- - NOTE - Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation. -----------------------------------------------------------------------

Verify primary to secondary LEAKAGE is 150 gallons per day through any one SG.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Technical Specifications Minimum RCS Flow

3.4.8 Turkey

Point Unit 7 3.4.8 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.8 Minimum RCS Flow LCO 3.4.8 At least one Reactor Coolant Pump (RCP) shall be in operation with a total flow through the core of at least 3,000 gpm.

- NOTES - 1. All RCPs may be de-energized for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided: a. No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and b. Core outlet temperature is maintained at least 10°F below saturation temperature. 2. No RCP shall be started when the RCS temperature is 350°F unless pressurizer level is < 92%. 3. No RCP shall be started with any RCS cold leg temperature 350°F unless the secondary side water temperature of each steam

generator (SG) is 50°F above each of the RCS cold leg temperatures and the RCP is started at 25% of RCP speed. --------------------------------------------------------------------------------------------------

APPLICABILITY: MODES 3, 4, and 5, whenever the reactor trip breakers are open and with unborated water sources not isolated from the RCS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No RCP in operation. A.1 Isolate all sources of unborated water.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND A.2 Perform SR 3.1.1.1. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

Technical Specifications Minimum RCS Flow

3.4.8 Turkey

Point Unit 7 3.4.8 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify that at least one RCP is in operation at 10% rated speed or equivalent.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Technical Specifications RCS Leakage Detection Instrumentation

3.4.9 Turkey

Point Unit 7 3.4.9 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.9 RCS Leakage Detection Instrumentation LCO 3.4.9 The following RCS leakage detection instrumentation shall be OPERABLE: a. Two containment sump level channels;

b. One containment atmosphere radioactivity monitor (F18 particulate).

APPLICABILITY: MODES 1, 2, 3, and 4. -------------------------------------------------------------------------------------------------- - NOTES - 1. The F18 particulate containment atmosphere radioactivity monitor is only required to be OPERABLE in MODE 1 with RTP > 20%. 2. Containment sump level measurements cannot be used for leak detection if leakage is prevented from draining to the sump such as by redirection to the In-Containment Refueling Water Storage Tank (IRWST) by the containment shell gutter drains. -------------------------------------------------------------------------------------------------- ACTIONS - NOTE LCO 3.0.4 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required containment sump channel inoperable. A.1 Verify that the volume input per day to the containment

sump does not change

(+ or -) more than 10 gallons or 33% of the volume input (whichever is greater). The volume used for comparison will be the value taken during the first day following the entrance into this CONDITION.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND Technical Specifications RCS Leakage Detection Instrumentation

3.4.9 Turkey

Point Unit 7 3.4.9 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A.2 Restore two containment sump channels to OPERABLE status.

14 days B. Two required containment sump channels inoperable. B.1 ----------------------------------- - NOTE - Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation. -----------------------------------

Perform SR 3.4.7.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.2 Restore one containment sump channel to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Required containment atmosphere

radioactivity monitor inoperable. C.1.1 Analyze grab samples of containment atmosphere.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OR C.1.2 ----------------------------------- - NOTE - Not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after establishment of steady state operation. -----------------------------------

Perform SR 3.4.7.1. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND C.2 Restore containment atmosphere radioactivity monitor to OPERABLE status. 30 days D. Required Action and associated Completion Time

not met. D.1 AND D.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Technical Specifications RCS Leakage Detection Instrumentation

3.4.9 Turkey

Point Unit 7 3.4.9 - 3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. All required monitors inoperable. E.1 Enter LCO 3.0.3. Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 Perform a CHANNEL CHECK of required containment atmosphere radioactivity monitor.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.9.2 Perform a COT of required containment atmosphere radioactivity monitor.

92 days SR 3.4.9.3 Perform a CHANNEL CALIBRATION of required containment sump monitor.

24 months SR 3.4.9.4 Perform a CHANNEL CALIBRATION of required containment atmosphere radioactivity monitor.

24 months

Technical Specifications RCS Specific Activity 3.4.10 Turkey Point Unit 7 3.4.10 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.10 RCS Specific Activity LCO 3.4.10 The specific activity of the reactor coolant shall be within limits. APPLICABILITY: MODES 1 and 2. MODE 3 with RCS average temperature (Tavg) 500°F. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT I-131 > 1.0 Ci/gm. ------------------------------------ - NOTE - LCO 3.0.4 is not applicable. ------------------------------------

A.1 Verify DOSE EQUIVALENT I-131 to be 60 Ci/gm. Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND A.2 Restore DOSE EQUIVALENT I-131 to within limit.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months B. DOSE EQUIVALENT XE-133 > 280 Ci/gm. B.1 AND B.2 Perform SR 3.4.10.2.

Be in MODE 3 with Tavg < 500°F. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 6 hours C. Required Action and associated Completion Time of Condition A not met. OR DOSE EQUIVALENT I-131 > 60 Ci/gm. C.1 Be in MODE 3 with Tavg < 500°F. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Technical Specifications RCS Specific Activity 3.4.10 Turkey Point Unit 7 3.4.10 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor coolant DOSE EQUIVALENT XE-133 specific activity < 280 Ci/gm. 7 days SR 3.4.10.2 ------------------------------------------------------------------------ NOTE - Only required to be performed in MODE 1. -----------------------------------------------------------------------

Verify reactor coolant DOSE EQUIVALENT I-131 specific activity 1.0 Ci/gm. 14 days AND Between 2 to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of 15% of RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

period

Technical Specifications ADS - Operating 3.4.11 Turkey Point Unit 7 3.4.11 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.11 Automatic Depressurization System (ADS) - Operating LCO 3.4.11 The ADS, including 10 flow paths, shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One stage 1, 2, or 3 ADS flow path inoperable. A.1 Restore flow path to OPERABLE status.

7 days B. One stage 4 ADS flow path inoperable. B.1 Restore flow path to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Two or three ADS flow paths inoperable with a

combined inoperable flow capacity less than or equal to that of a division with the largest ADS flow capacity. C.1 Restore flow paths to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months D. Required Action and associated Completion Time

not met. OR Requirements of LCO not met for reasons other than Condition A, B, or C.

D.1 AND D.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours Technical Specifications ADS - Operating 3.4.11 Turkey Point Unit 7 3.4.11 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1 Verify that the motor operated valve in series with each 4th stage ADS valve is fully open.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.11.2 Verify that each stage 1, 2, and 3 ADS valve is OPERABLE by stroking them open. In accordance with the Inservice Testing Program SR 3.4.11.3 Verify that each stage 4 ADS valve is OPERABLE in accordance with the Inservice Testing Program. In accordance with the Inservice Testing Program

Technical Specifications ADS - Shutdown, RCS Intact 3.4.12 Turkey Point Unit 7 3.4.12 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.12 Automatic Depressurization System (ADS) - Shutdown, RCS Intact LCO 3.4.12 The ADS, including 9 flow paths, shall be OPERABLE.

APPLICABILITY: MODE 5 with RCS pressure boundary intact. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required stage 1, 2, or 3 ADS flow path inoperable. A.1 Restore flow path to OPERABLE status.

7 days B. One required stage 4 ADS flow path inoperable.

B.1 Restore flow path to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Two or three required ADS flow paths inoperable with a

combined inoperable flow capacity less than or equal to that of a division with the largest ADS flow capacity. C.1 Restore flow paths to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months D. Required Action and associated Completion Time not met. D.1 Initiate action to be in MODE 5, with RCS open and 20% pressurizer level. Immediately OR Requirements of LCO not met for reasons other than Condition A, B, or C.

Technical Specifications ADS - Shutdown, RCS Intact 3.4.12 Turkey Point Unit 7 3.4.12 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.12.1 For flow paths required to be OPERABLE, the SRs of LCO 3.4.11, "Automatic Depressurization System (ADS) - Operating" are applicable. In accordance with applicable SRs

Technical Specifications ADS - Shutdown, RCS Open 3.4.13 Turkey Point Unit 7 3.4.13 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.13 Automatic Depressurization System (ADS) - Shutdown, RCS Open LCO 3.4.13 ADS stage 1, 2, and 3, flow paths shall be open. ADS stage 4 with 2 flow paths shall be OPERABLE. -------------------------------------------------------------------------------------------------- - NOTE - In MODE 5, the ADS valves may be closed to facilitate RCS vacuum fill operations to establish a pressurizer level 20%, provided ADS valve OPERABILITY meets LCO 3.4.12, ADS - Shutdown, RCS Intact. --------------------------------------------------------------------------------------------------

APPLICABILITY: MODE 5 with RCS pressure boundary open or pressurizer level < 20%; MODE 6 with upper internals in place. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ADS stage 1, 2, or 3 flow path not open. A.1 Open the affected flow path. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR A.2 Open an alternative flow path with an equivalent

area. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. One required ADS stage 4 flow path closed and inoperable. B.1 Open an alternative flow path with an equivalent

area. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR B.2 Restore two ADS stage 4 flow paths to OPERABLE status. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Technical Specifications ADS - Shutdown, RCS Open 3.4.13 Turkey Point Unit 7 3.4.13 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time not met while in MODE 5. OR Requirements of LCO not met for reasons other than Conditions A or B while in MODE 5. C.1 Initiate action to fill the RCS to establish 20% pressurizer level.

Immediately AND C.2 Suspend positive reactivity additions.

Immediately D. Required Action and associated Completion Time not met while in MODE 6. OR Requirements of LCO not met for reasons other than Conditions A or B while in MODE 6. D.1 Initiate action to remove the upper internals.

Immediately AND D.2 Suspend positive reactivity additions.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 Verify that each ADS stage 1, 2, and 3 valve is in the fully open position.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.13.2 For each ADS stage 4 flow path required to be OPERABLE, the following SRs of LCO 3.4.11, "Automatic Depressurization System (ADS) -

Operating" are applicable: SR 3.4.11.1 SR 3.4.11.3 In accordance with applicable SRs

Technical Specifications LTOP System 3.4.14 Turkey Point Unit 7 3.4.14 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.14 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.14 At least one of the following Overpressure Protection Systems shall be OPERABLE, with the accumulators isolated: a. The Normal Residual Heat Removal System (RNS) suction relief valve with lift setting within the limit specified in the PTLR, or

b. The RCS depressurized and an RCS vent of 4.15 square inches.

- NOTE - 1. No reactor coolant pump (RCP) shall be started when the RCS temperature is 350°F unless pressurizer level is < 92%.

2. No RCP shall be started with any RCS cold leg temperature 350°F unless the secondary side water temperature of each steam

generator (SG) is 50°F above each of the RCS cold leg temperatures and the RCP is started at 25% of RCP speed. -------------------------------------------------------------------------------------------------- APPLICABILITY: MODE 4 when any cold leg temperature is 275°F, MODE 5, MODE 6 when the reactor vessel head is on. -------------------------------------------------------------------------------------------------- - NOTE - Accumulator isolation is only required when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR. --------------------------------------------------------------------------------------------------

Technical Specifications LTOP System 3.4.14 Turkey Point Unit 7 3.4.14 - 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. An accumulator not isolated when the accumulator pressure is > to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR. A.1 Isolate affected accumulator.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. Required Action and associated Completion Time of Condition A not met. B.1 Increase RCS cold leg temperature to a level acceptable for the existing accumulator pressure allowed in the PTLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR B.2 Depressurize affected accumulator to less than the maximum RCS pressure for existing cold

leg temperature allowed in

the PTLR.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. The RNS suction relief valve inoperable. C.1 Restore the RNS suction relief valve to OPERABLE status. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR C.2 Depressurize RCS and establish RCS vent of 4.15 square inches.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Technical Specifications LTOP System 3.4.14 Turkey Point Unit 7 3.4.14 - 3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 Verify each accumulator is isolated. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.14.2 Verify both RNS suction isolation valves in one RNS suction flow path are open.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.14.3 ----------------------------------------------------------------------- - NOTE - Only required to be performed when complying with LCO 3.4.14.b. -----------------------------------------------------------------------

Verify RCS vent 4.15 square inches is open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for unlocked-open vent AND 31 days for locked-open vent SR 3.4.14.4 Verify the lift setting of the RNS suction relief valve. In accordance with the Inservice Testing Program

Technical Specifications RCS PIV Integrity 3.4.15 Turkey Point Unit 7 3.4.15 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.15 RCS Pressure Isolation Valve (PIV) Integrity LCO 3.4.15 Leakage from each RCS PIV shall be within limit. APPLICABILITY: MODES 1, 2, and 3. MODE 4, with the RCS not being cooled by the Normal Residual Heat Removal System (RNS).

ACTIONS - NOTES - 1. Separate Condition entry is allowed for each flow path. 2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.

CONDITION REQUIRED ACTION COMPLETION TIME A. Leakage from one or more RCS PIVs not within limit.

NOTE - Each valve used to satisfy Required Action A.1 and Required Action A.2 must have been

verified to meet SR 3.4.15.1 and be in the reactor coolant pressure boundary or the high pressure portion of the system. ---------------------------------------------

A.1 Isolate the high pressure portion of the affected

system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND Technical Specifications RCS PIV Integrity 3.4.15 Turkey Point Unit 7 3.4.15 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A.2 Verify a second OPERABLE PIV can meet the leakage limits. This valve is required to be a check valve, or a closed valve, if it isolates a line that penetrates containment.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and associated Completion Time not met. B.1 AND B.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Verify leakage of each RCS PIV is equivalent to 0.5 gpm per nominal inch valve size up to a maximum of 5 gpm at an RCS pressure 2215 and 2255 psig.

24 months

Technical Specifications RVHV 3.4.16 Turkey Point Unit 7 3.4.16 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.16 Reactor Vessel Head Vent (RVHV) LCO 3.4.16 The Reactor Vessel Head Vent shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. MODE 4 with the RCS not being cooled by the Normal Residual Heat Removal System (RNS).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One flow path inoperable. A.1 Restore flow path to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Two flow paths inoperable. B.1 Restore at least one flow path to OPERABLE status.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months C. Required Action and associated Completion Time not met. OR Requirements of LCO not met for reasons other than Conditions A or B. C.1 AND C.2 Be in MODE 3.

Be in MODE 4, with the RCS cooling provided by the RNS. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify that each RVHV valve is OPERABLE by stroking it open. In accordance with the Inservice Testing Program

Technical Specifications CVS Makeup Isolation Valves 3.4.17 Turkey Point Unit 7 3.4.17 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.17 Chemical and Volume Control System (CVS) Makeup Isolation Valves LCO 3.4.17 Two CVS Makeup Isolation Valves shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CVS makeup isolation valve inoperable. A.1 Restore two CVS makeup isolation valves to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and associated Completion Time not met. OR Two CVS makeup isolation valves inoperable. B.1 ------------------------------------ - NOTE - Flow path(s) may be unisolated intermittently

under administrative controls. ------------------------------------

Isolate the flow path from the CVS makeup pumps to the Reactor Coolant System by use of at least one closed manual or one closed and de-activated

automatic valve.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Technical Specifications CVS Makeup Isolation Valves 3.4.17 Turkey Point Unit 7 3.4.17 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.17.1 Verify two CVS makeup isolation valves are OPERABLE by stroking the valves closed. In accordance with the Inservice Testing Program SR 3.4.17.2 Verify closure time of each CVS makeup isolation valve is 30 seconds on an actual or simulated actuation signal. In accordance with the Inservice Testing Program

Technical Specifications SG Tube Integrity 3.4.18 Turkey Point Unit 7 3.4.18 - 1

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.18 Steam Generator (SG) Tube Integrity LCO 3.4.18 SG tube integrity shall be maintained. AND All SG tubes satisfying the tube repair criteria shall be plugged in accordance with the Steam Generator Program.

APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS - NOTE - Separate Condition entry is allowed for each SG tube.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes satisfying the tube repair criteria and not plugged in accordance with the Steam Generator Program. A.1 Verify tube integrity of the affected tube(s) is maintained until the next refueling outage or SG tube inspection.

7 days AND A.2 Plug the affected tube(s) in accordance with the Steam Generator Program.

Prior to entering MODE 4 following the next refueling outage or SG tube inspection B. Required Action and associated Completion Time of Condition A not met. OR SG tube integrity not maintained. B.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND B.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

Technical Specifications SG Tube Integrity 3.4.18 Turkey Point Unit 7 3.4.18 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.18.1 Verify SG tube integrity in accordance with the Steam Generator Program. In accordance with the Steam

Generator Program SR 3.4.18.2 Verify that each inspected SG tube that satisfies the tube repair criteria is plugged in accordance with the Steam Generator Program.

Prior to entering MODE 4 following a SG tube inspection

Technical Specifications Accumulators

3.5.1 Turkey

Point Unit 7 3.5.1 - 1

3.5 PASSIVE

CORE COOLING SYSTEM (PXS)

3.5.1 Accumulators

LCO 3.5.1 Both accumulators shall be OPERABLE. APPLICABILITY: MODES 1 and 2. MODES 3 and 4 with Reactor Coolant System (RCS) pressure > 1000 psig.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator inoperable due to boron concentration outside limits. A.1 Restore boron concentration to within limits. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. One accumulator inoperable for reasons other than Condition A. B.1 Restore accumulator to OPERABLE status. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months if Condition C or E of LCO 3.5.2 has not been entered OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if Condition C or E of LCO 3.5.2 has

been entered C. Required Action and associated Completion Time of Condition A or B not met. C.1 AND C.2 Be in MODE 3.

Reduce RCS pressure to 1000 psig.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 12 hours D. Two accumulators inoperable. D.1 Enter LCO 3.0.3. Immediately

Technical Specifications Accumulators

3.5.1 Turkey

Point Unit 7 3.5.1 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.5.1.2 Verify the borated water volume in each accumulator is 1667 cu. ft., and 1732 cu. ft.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.5.1.3 Verify the nitrogen cover gas pressure in each accumulator is 637 psig and 769 psig.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.5.1.4 Verify the boron concentration in each accumulator is 2600 ppm and 2900 ppm.

31 days AND ------------------------- - NOTE - Only required for affected accumulators. -------------------------

Once within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of 51 cu. ft., 3.0% that is not the result of addition

from the in-containment refueling water storage tank SR 3.5.1.5 Verify power is removed from each accumulator isolation valve operator when pressurizer pressure is 2000 psig.

31 days SR 3.5.1.6 Verify system flow performance of each accumulator in accordance with the System Level OPERABILITY Testing Program.

10 years Technical Specifications CMTs - Operating

3.5.2 Turkey

Point Unit 7 3.5.2 - 1

3.5 PASSIVE

CORE COOLING SYSTEM (PXS) 3.5.2 Core Makeup Tanks (CMTs) - Operating LCO 3.5.2 Both CMTs shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. MODE 4 with the Reactor Coolant Sy stem (RCS) not being cooled by the Normal Residual Heat Removal System (RNS).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CMT inoperable due to one CMT outlet

isolation valve inoperable. A.1 Restore outlet isolation valve to OPERABLE status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. One CMT inoperable due to one or more parameters (water

temperature, boron concentration) not within limits. B.1 Restore water temperature or boron concentration to within limits.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Two CMTs inoperable due to water

temperature or boron concentration not within limits. C.1 Restore water temperature or boron concentration to within limits for one CMT. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months if Condition B of LCO 3.5.1 has not

been entered OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if Condition B of LCO 3.5.1 has been entered D. One CMT inoperable due to presence of non-condensible gases in

one high point vent. D.1 Vent noncondensible gases. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months E. One CMT inoperable for reasons other than Condition A, B, C, or D.

E.1 Restore CMT to OPERABLE status. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months if Condition B of LCO 3.5.1 has not

been entered OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if Condition B of LCO 3.5.1 has been

entered Technical Specifications CMTs - Operating

3.5.2 Turkey

Point Unit 7 3.5.2 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and associated Completion Time not met. OR LCO not met for reasons other than A, B, C, D, or E. F.1 AND F.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the temperature of the borated water in each CMT is < 120°F.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.5.2.2 Verify the borated water volume in each CMT is 2500 cu. ft.

7 days SR 3.5.2.3 Verify each CMT inlet isolation valve is fully open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.5.2.4 Verify the volume of noncondensible gases in each CMT inlet line has not caused the high-point water level to drop below the sensor.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.5.2.5 Verify the boron concentration in each CMT is 3400 ppm, and 3700 ppm.

7 days SR 3.5.2.6 Verify each CMT outle t isolation valve is OPERABLE by stroking it open. In accordance with the Inservice Testing Program SR 3.5.2.7 Verify system flow performance of each CMT in accordance with the System Level OPERABILITY Testing Program.

10 years Technical Specifications CMTs - Shutdown, RCS Intact

3.5.3 Turkey

Point Unit 7 3.5.3 - 1

3.5 PASSIVE

CORE COOLING SYSTEM (PXS) 3.5.3 Core Makeup Tanks (CMTs) - Shutdown, Reactor Coolant System (RCS) Intact LCO 3.5.3 One CMT shall be OPERABLE. APPLICABILITY: MODE 4 with the RCS cooling provided by the Normal Residual Heat Removal System (RNS). MODE 5 with the RCS pressure boundary intact. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required CMT inoperable due to one outlet isolation valve inoperable. A.1 Restore required isolation valve to OPERABLE status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required CMT inoperable due to one or more parameters (water temperature, boron concentration) not within limits. B.1 Restore water temperature or boron concentration to within limits.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Required CMT inoperable for reasons other than A or B. C.1 Restore required CMT to OPERABLE status.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D. Required Action and associated Completion Time not met. OR LCO not met for reasons other than A, B, or C. D.1 Initiate action to be in MODE 5 with RCS pressure boundary open and 20% pressurizer level. Immediately

Technical Specifications CMTs - Shutdown, RCS Intact

3.5.3 Turkey

Point Unit 7 3.5.3 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 For the CMT required to be OPERABLE, the SRs of Specification 3.5.2, "Core Makeup Tanks (CMTs) -

Operating" are applicable. In accordance with applicable SRs

Technical Specifications PRHR HX - Operating

3.5.4 Turkey

Point Unit 7 3.5.4 - 1

3.5 PASSIVE

CORE COOLING SYSTEM (PXS) 3.5.4 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Operating LCO 3.5.4 The PRHR HX shall be OPERABLE. -------------------------------------------------------------------------------------------------- - NOTE - When any reactor coolant pumps (RCPs) are operating, at least one RCP must be operating in the loop with the PRHR HX, Loop 1. -------------------------------------------------------------------------------------------------- APPLICABILITY: MODES 1, 2, and 3. MODE 4 with the Reactor Coolant Sy stem (RCS) not being cooled by the Normal Residual Heat Removal System (RNS). ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One air operated outlet isolation valve inoperable. A.1 Restore air operated outlet isolation valve to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. One air operated In-Containment Refueling Water Storage Tank (IRWST) gutter isolation

valve inoperable. B.1 Restore air operated IRWST gutter isolation valve to OPERABLE status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Presence of non-condensible gases in

the high point vent. C.1 Vent noncondensible gases. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D. Required Action and associated Completion Time of Condition A, B, or C not met. D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND D.2 Be in MODE 4 with the RCS cooling provided by the RNS. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months E. LCO not met for reasons other than Condition A, B, or C. E.1 Restore PRHR HX to OPERABLE status.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Technical Specifications PRHR HX - Operating

3.5.4 Turkey

Point Unit 7 3.5.4 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and associated F.1 ------------------------------------ - NOTE - Prior to initiating actions to change to a lower MODE, verify that redundant means of providing Steam Generator (SG) feedwater are OPERABLE. If

redundant means are not

OPERABLE, suspend LCO 3.0.3 and all other LCO Required Actions requiring MODE changes until redundant means are restored to OPERABLE status. ------------------------------------

Completion Time of Condition E not met. Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND F.2 ------------------------------------ - NOTE - Prior to stopping the SG feedwater, verify that redundant means of cooling the RCS to cold shutdown conditions are OPERABLE. If redundant means are not OPERABLE, suspend LCO 3.0.3 and all other LCO Required Actions requiring MODE changes until redundant means are restored to OPERABLE status. ------------------------------------

Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

Technical Specifications PRHR HX - Operating

3.5.4 Turkey

Point Unit 7 3.5.4 - 3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 Verify the outlet manual isolation valve is fully open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.5.4.2 Verify the inlet motor operated isolation valve is open. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.5.4.3 Verify the volume of noncondensible gases in the PRHR HX inlet line has not caused the high-point water level to drop below the sensor.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.5.4.4 Verify that power is removed from the inlet motor operated isolation valve.

31 days SR 3.5.4.5 Verify both PRHR air operated outlet isolation valves and both IRWST gutter isolation valves are OPERABLE by stroking open the valves. In accordance with the Inservice Testing Program SR 3.5.4.6 Verify PRHR HX heat transfer performance in accordance with the System Level OPERABILITY Testing Program.

10 years SR 3.5.4.7 Verify by visual inspection that the IRWST gutter and downspout screens are not restricted by debris.

24 months

Technical Specifications PRHR HX - Shutdown, RCS Intact

3.5.5 Turkey

Point Unit 7 3.5.5 - 1

3.5 PASSIVE

CORE COOLING SYSTEM (PXS) 3.5.5 Passive Residual Heat Removal Heat Exchanger (PRHR HX) - Shutdown, Reactor Coolant System (RCS) Intact LCO 3.5.5 The PRHR HX shall be OPERABLE.

- NOTE - When any reactor coolant pumps (RCPs) are operating, at least one RCP must be operating in the loop with the PRHR HX, Loop 1. -------------------------------------------------------------------------------------------------- APPLICABILITY: MODE 4 with the RCS cooling provided by the Normal Residual Heat Removal System (RNS).

MODE 5 with the RCS pressure boundary intact and pressurizer level 20%. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One air operated outlet isolation valve inoperable. A.1 Restore air operated outlet valve to OPERABLE status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. One air operated In-Containment Refueling Water Storage Tank (IRWST) gutter isolation

valve inoperable. B.1 Restore air operated IRWST gutter isolation valve to OPERABLE status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Presence of non-condensible gases in

the high point vent. C.1 Vent noncondensible gases. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D. PRHR HX inoperable for reasons other than Condition A, B, or C. D.1 Restore PRHR HX to OPERABLE status.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Technical Specifications PRHR HX - Shutdown, RCS Intact

3.5.5 Turkey

31 days SR 3.5.6.8 Verify each IRWST injection and containment recirculation squib valve is OPERABLE in accordance with the Inservice Testing Program. In accordance with the Inservice Testing Program SR 3.5.6.9 Verify by visual inspection that the IRWST screens and the containment recirculation screens are not restricted by debris.

24 months SR 3.5.6.10 Verify IRWST injection and recirculation system flow performance in accordance with the System Level OPERABILITY Testing Program.

10 years Technical Specifications IRWST - Shutdown, MODE 5 3.5.7 Turkey Point Unit 7 3.5.7 - 1

3.5 PASSIVE

CORE COOLING SYSTEM (PXS) 3.5.7 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, MODE 5 LCO 3.5.7 The IRWST, with one injection flow path and one containment recirculation flow path, shall be OPERABLE. APPLICABILITY: MODE 5. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required motor operated containment recirculation isolation valve not fully open. A.1 Open required motor operated containment recirculation isolation valve. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required IRWST injection line inoperable due to presence of noncondensible gases in one high point vent. B.1 Vent noncondensible gases. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Required IRWST injection line inoperable due to presence of

noncondensible gases in both high point vents. C.1 Vent noncondensible gases from one high point

vent. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D. IRWST boron concentration not within limits. OR IRWST borated water temperature not within limits. OR IRWST borated water volume < 100% and

> 97% of limit. D.1 Restore IRWST to OPERABLE status.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Technical Specifications IRWST - Shutdown, MODE 5 3.5.7 Turkey Point Unit 7 3.5.7 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. Required motor operated IRWST

isolation valve not fully open. OR Power is not removed from required motor operated IRWST isolation valve. E.1 Restore required motor operated IRWST isolation

valve to fully open condition with power removed. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months F. Required Action and associated Completion Time not met. OR F.1 Initiate action to be in MODE 5 with the Reactor Coolant System (RCS) pressure boundary intact

and 20% pressurizer level. Immediately LCO not met for reasons other than AND F.2 Suspend positive reactivity additions.

Immediately Condition A, B, C, D, or E. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.7.1 For the IRWST and flow paths required to be OPERABLE, the SRs of Specification 3.5.6, "In-containment Refueling Water Storage Tank (IRWST) - Operating," are applicable. In accordance with applicable SRs

Technical Specifications IRWST - Shutdown, MODE 6 3.5.8 Turkey Point Unit 7 3.5.8 - 1

3.5 PASSIVE

CORE COOLING SYSTEM (PXS) 3.5.8 In-containment Refueling Water Storage Tank (IRWST) - Shutdown, MODE 6 LCO 3.5.8 The IRWST, with one injection flow path and one containment recirculation flow path, shall be OPERABLE. APPLICABILITY: MODE 6. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required motor operated containment recirculation isolation valve not fully open. A.1 Open required motor operated containment recirculation isolation valve. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required IRWST injection line inoperable due to presence of noncondensible gases in one high point vent. B.1 Vent noncondensible gases. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. Required IRWST injection line inoperable due to presence of noncondensible gases in both high point vents. C.1 Vent noncondensible gases from one high point vent. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D. IRWST and refueling cavity boron concentra-tion not within limits. OR IRWST and refueling cavity borated water temperature not within limits. OR IRWST and refueling cavity borated water volume < 100% and

> 97% of limit. D.1 Restore IRWST to OPERABLE status.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Technical Specifications IRWST - Shutdown, MODE 6 3.5.8 Turkey Point Unit 7 3.5.8 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. Required motor operated IRWST isolation valve not fully open. OR Power is not removed from required motor operated IRWST isolation valve. E.1 Restore required motor operated IRWST isolation valve to fully open condition with power removed. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months F. Required Action and associated Completion Time not met. OR F.1 Initiate action to be in MODE 6 with the water level 23 feet above the top of the reactor vessel flange. Immediately LCO not met for reasons other than Condition A, B, C, D, or

E. AND F.2 Suspend positive reactivity additions.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.8.1 Verify the IRWST and refueling cavity water temperature is < 120°F.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.5.8.2 Verify the IRWST and refueling cavity water total borated water volume is > 73,100 cu. ft.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.5.8.3 Verify the IRWST and refueling cavity boron concentration is 2600 ppm and 2900 ppm.

31 days AND Once within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume

increase of

15,000 gal Technical Specifications IRWST - Shutdown, MODE 6 3.5.8 Turkey Point Unit 7 3.5.8 - 3 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.5.8.4 For the IRWST and flow paths required to be OPERABLE, the following SRs of Specification 3.5.6, "In-containment Refueling Water Storage Tank (IRWST) - Operating" are applicable:

SR 3.5.6.3 SR 3.5.6.6 SR 3.5.6.8 SR 3.5.6.10 SR 3.5.6.5 SR 3.5.6.7 SR 3.5.6.9 In accordance with applicable SRs

Technical Specifications Containment

3.6.1 Turkey

Point Unit 7 3.6.1 - 1

3.6 CONTAINMENT

SYSTEMS 3.6.1 Containment LCO 3.6.1 Containment shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment inoperable. A.1 Restore containment to OPERABLE status.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. Required Action and associated Completion Time not met. B.1 AND B.2 Be in MODE 3.

Point Unit 7 3.6.2 - 3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B.2 Lock an OPERABLE door closed in the affected air lock. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND B.3 ------------------------------------ - NOTE - Air lock doors in high radiation areas may be verified locked closed by administrative means. ------------------------------------

Verify an OPERABLE door is locked closed in the affected air lock.

Once per 31 days C. One or more containment air locks inoperable for reasons other than Condition A

or B. C.1 Initiate action to evaluate overall containment leakage rate per LCO 3.6.1.

Immediately AND C.2 Verify a door is closed in the affected air lock.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND C.3 Restore air lock to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D. Required Action and associated Completion Time not met.

D.1 AND D.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours Technical Specifications Containment Air Locks

3.6.2 Turkey

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours Technical Specifications Containment Isolation Valves

3.6.3 Turkey

Point Unit 7 3.6.3 - 4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1 Verify each 16 inch containment purge valve is closed, except when the 16 inch containment purge valves are open for pressure control, ALARA or air quality considerations for personnel containment entry, or for Surveillances which require the valves to

be open. 31 days SR 3.6.3.2 ----------------------------------------------------------------------- - NOTE - Valves and blind flanges in high radiation areas may be verified by use of administrative controls. -----------------------------------------------------------------------

Verify each containment isolation manual valve and blind flange that is located outside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

31 days SR 3.6.3.3 ----------------------------------------------------------------------- - NOTE - Valves and blind flanges in high radiation areas may be verified by use of administrative controls. -----------------------------------------------------------------------

Verify each containment isolation manual valve and blind flange that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.

Prior to entering MODE 4 from MODE 5 if not

performed within

the previous

92 days SR 3.6.3.4 Verify the isolation time of each automatic power operated containment isolation valve is within limits. In accordance with the Inservice Testing Program SR 3.6.3.5 Verify each automatic containment isolation valve that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal.

24 months

Technical Specifications Containment Pressure

3.6.4 Turkey

Point Unit 7 3.6.4 - 1

3.6 CONTAINMENT

SYSTEMS 3.6.4 Containment Pressure LCO 3.6.4 Containment pressure shall be -0.2 psig and +1.0 psig.

APPLICABILITY: MODES 1, 2, 3, and 4. MODES 5 and 6 without an open containment air flow path 6 inches in diameter.

- NOTE - The high pressure LCO limit is not applicable in MODES 5 or 6. --------------------------------------------------------------------------------------------------

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment pressure not within limits. A.1 Restore containment pressure to within limits.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. Required Action and associated Completion Time not met. B.1 AND B.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months AND B.3 Open a containment air flow path 6 inches in diameter.

44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within limits. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Technical Specifications Containment Air Temperature

3.6.5 Turkey

Point Unit 7 3.6.5 - 1

3.6 CONTAINMENT

SYSTEMS 3.6.5 Containment Air Temperature LCO 3.6.5 Containment average air temperature shall be 120°F. APPLICABILITY: MODES 1, 2, 3, and 4, MODES 5 and 6 with both containment equipment hatches and both containment airlocks closed.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average air temperature not within limit. A.1 Restore containment average air temperature to within limit.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months B. Required Action and associated Completion Time not met. B.1 AND B.2 AND B.3 Be in MODE 3.

Be in MODE 5 or 6.

Open containment equipment hatch or containment airlock.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours 44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify containment average air temperature is within limit. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Technical Specifications PCS - Operating

3.6.6 Turkey

Point Unit 7 3.6.6 - 1

3.6 CONTAINMENT

SYSTEMS 3.6.6 Passive Containment Cooling System (PCS) - Operating LCO 3.6.6 The passive containment cooling system shall be OPERABLE, with all three water flow paths OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One passive containment cooling water flow path inoperable. A.1 Restore flow path to OPERABLE status.

7 days B. Two passive containment cooling water flow paths inoperable. B.1 Restore flow paths to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. One or more water storage tank parameters (temperature and volume) not within limits. C.1 Restore water storage tank to OPERABLE status.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D. Required Action and associated Completion Time not met. OR LCO not met for reasons other than A, B, or C. D.1 AND D.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 84 hours Technical Specifications PCS - Operating

3.6.6 Turkey

Point Unit 7 3.6.6 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.6.1 Verify the water storage tank temperature 40°F and 120°F. 7 days AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when water storage tank temperature is

verified 50°F or 100°F SR 3.6.6.2 Verify the water storage tank volume 756,700 gallons. 7 days SR 3.6.6.3 Verify each passive containment cooling system, power operated, and automatic valve in each flow path that is not locked, sealed, or otherwise secured in position, is in the correct position.

31 days SR 3.6.6.4 Verify each passive containment cooling system automatic valve in each flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

24 months SR 3.6.6.5 Verify the air flow path from the shield building annulus inlet to the exit is unobstructed and, that all air baffle sections are in place.

24 months SR 3.6.6.6 Verify passive containment cooling system flow and water coverage performance in accordance with the System Level OPERABILITY Testing Program. At first refueling AND 10 years Technical Specifications PCS - Shutdown 3.6.7 Turkey Point Unit 7 3.6.7 - 1

3.6 CONTAINMENT

SYSTEMS 3.6.7 Passive Containment Cooling System (PCS) - Shutdown LCO 3.6.7 The passive containment cooling system shall be OPERABLE with all three water flow paths OPERABLE. APPLICABILITY: MODE 5 with the calculated reactor decay heat > 6.0 MWt, MODE 6 with the calculated reactor decay heat > 6.0 MWt.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One passive containment cooling water flow path inoperable. A.1 Restore flow path to OPERABLE status.

7 days B. Two passive containment cooling water flow paths inoperable. B.1 Restore flow paths to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C. One or more water storage tank parameters (temperature and volume) not within limits. C.1 Restore water storage tank to OPERABLE status.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Technical Specifications PCS - Shutdown 3.6.7 Turkey Point Unit 7 3.6.7 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time not met. OR LCO not met for reasons other than Condition A, B, or C. D.1.1 If in MODE 5, initiate action to be in MODE 5 with the Reactor Coolant System (RCS) pressure boundary intact and 20% pressurizer level.

Immediately OR D.1.2 If in MODE 6, initiate action to be in MODE 6 with the water level 23 feet above the top of the reactor vessel flange.

Immediately AND D.2 Suspend positive reactivity additions.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 The SRs of Specification 3.6.6, "Passive Containment Cooling System - Operating," are applicable. In accordance with applicable SRs

Technical Specifications Containment Penetrations

3.6.8 Turkey

Point Unit 7 3.6.8 - 1

3.6 CONTAINMENT

SYSTEMS 3.6.8 Containment Penetrations LCO 3.6.8 The containment penetrations shall be in the following status: a. The equipment hatches closed and held in place by four bolts or, if open, clear of obstructions such that the hatches can be closed prior to steaming into the containment. b. One door in each air lock closed or, if open, the containment air locks shall be clear of obstructions such that they can be closed prior to steaming into the containment. c. The containment spare penetrations, if open, shall be clear of obstructions such that the penetrations can be closed prior to steaming into the containment. d. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either: 1. closed by a manual or automatic isolation valve, blind flange, or equivalent, or 2. capable of being closed by an OPERABLE Containment Isolation signal. APPLICABILITY: MODES 5 and 6. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more containment

penetrations not in required status. A.1 Restore containment penetrations to required status. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Technical Specifications Containment Penetrations

3.6.8 Turkey

Point Unit 7 3.6.8 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time not met. OR LCO not met for reasons other than

Condition A. B.1.1 If in MODE 5, initiate action to be in MODE 5 with the Reactor Coolant System (RCS) pressure boundary intact and 20% pressurizer level.

Immediately OR B.1.2 If in MODE 6, initiate action to be in MODE 6 with the water level 23 feet above the top of the reactor vessel flange.

Immediately AND B.2 Suspend positive reactivity additions.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.8.1 Verify each required containment penetration is in the required status.

7 days SR 3.6.8.2 ----------------------------------------------------------------------- - NOTE - Only required to be met for an open equipment hatch. -----------------------------------------------------------------------

Verify that the hardware, tools, equipment and power source necessary to install the equipment hatch are

available.

Prior to hatch removal AND 7 days Technical Specifications Containment Penetrations

3.6.8 Turkey

Point Unit 7 3.6.8 - 3 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.6.8.3 ----------------------------------------------------------------------- - NOTE - Not required to be met for automatic isolation valve(s) in penetrations closed to comply with LCO 3.6.8.d.1. -----------------------------------------------------------------------

Verify one automatic isolation valve in each open penetration providing direct access from the containment atmosphere to the outside atmosphere actuates to the isolation position on an actual or simulated actuation signal.

24 months

Technical Specifications pH Adjustment

3.6.9 Turkey

Point Unit 7 3.6.9 - 1

3.6 CONTAINMENT

SYSTEMS 3.6.9 pH Adjustment LCO 3.6.9 The pH adjustment baskets shall contain 560 ft 3 of trisodium phosphate (TSP). APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The volume of trisodium phosphate not within limit. A.1 Restore volume of trisodium phosphate to within limit.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Action and associated Completion Time not met. B.1 AND B.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 84 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.9.1 Verify that the pH adjustment baskets contain at least 560 ft 3 of TSP (Na 3 PO 4-12 H 2O). 24 months SR 3.6.9.2 Verify that a sample from the pH adjustment baskets provides adequate pH adjustment of the post-accident water.

24 months

Technical Specifications Vacuum Relief Valves 3.6.10 Turkey Point Unit 7 3.6.10 - 1

3.6 CONTAINMENT

SYSTEMS 3.6.10 Vacuum Relief Valves LCO 3.6.10 Two vacuum relief flow paths shall be OPERABLE.

AND Containment inside to outside differential air temperature shall be 90°F.

APPLICABILITY: MODES 1, 2, 3, and 4. MODES 5 and 6 without an open containment air flow path 6 inches in diameter. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One vacuum relief flow path inoperable. A.1 Restore vacuum relief flow path to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Containment inside to outside differential air temperature > 90°F. B.1 Restore containment inside to outside differential air

temperature to within limit.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR B.2 Reduce containment average temperature 80°F. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months C. Required Action and associated Completion Time of Conditions A or B not

met. C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND C.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR AND Both vacuum relief flow paths inoperable. C.3 Open a containment air flow path 6 inches in diameter.

44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months Technical Specifications Vacuum Relief Valves 3.6.10 Turkey Point Unit 7 3.6.10 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.10.1 Verify containment inside to outside differential air temperature is 90°F. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.6.10.2 Verify each vacuum relief flow path is OPERABLE in accordance with the Inservice Testing Program. In accordance with the Inservice Testing Program

Technical Specifications MSSVs 3.7.1 Turkey Point Unit 7 3.7.1 - 1

3.7 PLANT

SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs) LCO 3.7.1 The MSSVs shall be OPERABLE as specified in Table 3.7.1-1 and Table 3.7.1-2. APPLICABILITY: MODES 1, 2, and 3. MODE 4 with the Reactor Coolant Sy stem (RCS) not being cooled by the Normal Residual Heat Removal System (RNS).

ACTIONS - NOTE - Separate Condition entry is allowed for each MSSV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required MSSVs inoperable. A.1 Reduce THERMAL POWER to less than or equal to the Maximum Allowable % RTP specified in Table 3.7.1-1 for the

number of OPERABLE MSSVs. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND A.2 ------------------------------------ - NOTE - Only required in MODE 1. ------------------------------------

Reduce the Power Range Neutron Flux - High reactor trip setpoint to less

than or equal to the Maximum Allowable %

RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Technical Specifications MSSVs 3.7.1 Turkey Point Unit 7 3.7.1 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time not met. OR One or more steam generators with

> 5 MSSVs inoperable.

B.1 AND B.2 Be in MODE 3.

Be in MODE 4 with the RCS cooling provided by the RNS. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 24 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 ----------------------------------------------------------------------- - NOTE - Only required to be performed in MODES 1 and 2. -----------------------------------------------------------------------

Verify each required MSSV lift setpoint per Table 3.7.1-2 in accordance with the Inservice Testing Program. Following testing, lift settings shall be

within +/-1%. In accordance with the Inservice Testing Program

Technical Specifications MSSVs 3.7.1 Turkey Point Unit 7 3.7.1 - 3 Table 3.7.1-1 (page 1 of 1) OPERABLE MSSVs versus Maximum Allowable Power NUMBER OF OPERABLE MSSVs PER STEAM GENERATOR MAXIMUM ALLOWABLE POWER (% RTP) 5 4 3 2 60 46 32 18 Technical Specifications MSSVs 3.7.1 Turkey Point Unit 7 3.7.1 - 4 Table 3.7.1-2 (page 1 of 1) Main Steam Safety Valve Lift Settings VALVE NUMBER STEAM GENERATOR LIFT SETTING (psig + 1%) #1 #2 V030A V031A V032A V033A V034A V035A V030B V031B V032B V033B V034B V035B 1185 1197 1209 1221 1232 1232

Technical Specifications MSIVs 3.7.2 Turkey Point Unit 7 3.7.2 - 1

3.7 PLANT

SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs) LCO 3.7.2 The minimum combination of valves required for steam flow isolation shall be OPERABLE. APPLICABILITY: MODE 1, MODES 2, 3, and 4 except when steam flow is isolated. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV inoperable in MODE 1. A. Restore valve to OPERABLE status.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months B. One or more of the turbine stop valves and its associated turbine control valve, turbine bypass valves, or moisture separator reheater 2nd stage

steam isolation valves inoperable in MODE 1. B. Restore valve to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Technical Specifications MSIVs 3.7.2 Turkey Point Unit 7 3.7.2 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. Two MSIVs inoperable in MODE 1. C.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR One MSIV inoperable and one or more of the turbine stop valves and its associated turbine control valve, all turbine bypass valves, or moisture separator reheater 2nd stage

steam isolation valves inoperable in MODE 1. OR Required Action and associated Completion Time of Condition A or B not met.

Technical Specifications MSIVs 3.7.2 Turkey Point Unit 7 3.7.2 - 3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. -------------------------------- - NOTE - Separate Condition entry is allowed for each MSIV. -------------------------------- One or two MSIVs inoperable in MODE 2, 3, or 4.

D.1 AND D.2 Isolate associated steam flow path.

Verify flow path remains closed. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Once per 7 days OR One or more of the turbine stop valves and its associated turbine control valve, all turbine bypass valves, or moisture separator reheater 2nd stage steam isolation valves inoperable in MODE 2, 3, or 4. E. Required Action and associated Completion Time of

Condition D not met.

E.1 AND E.2 Be in MODE 3.

Be in MODE 4 with the Reactor Coolant System (RCS) cooling provided by the Normal Residual Heat Removal System (RNS).

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 24 hours Technical Specifications MSIVs 3.7.2 Turkey Point Unit 7 3.7.2 - 4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 ----------------------------------------------------------------------- - NOTE - Only required to be performed prior to entry into MODE 2. -----------------------------------------------------------------------

Verify MSIV closure time 5 seconds on an actual or simulated actuation signal. In accordance with the Inservice Testing Program SR 3.7.2.2 ----------------------------------------------------------------------- - NOTE - Only required to be performed prior to entry into MODE 2. -----------------------------------------------------------------------

Verify turbine stop, turbine control, turbine bypass, and moisture separator reheater 2nd stage steam isolation valves' closure time 5 seconds on an actual or simulated actuation signal. In accordance with the Inservice Testing Program

Technical Specifications MFIVs and MFCVs

3.7.3 Turkey

Point Unit 7 3.7.3 - 1

3.7 PLANT

SYSTEMS 3.7.3 Main Feedwater Isolation and Control Valves (MFIVs and MFCVs) LCO 3.7.3 The MFIV and the MFCV for each Steam Generator shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4 except when the MFIVs or associated MFCV are closed and deactivated. ACTIONS - NOTE - Separate Condition entry is allowed for each valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two MFIVs inoperable. A.1 Close or isolate the MFIV flow path.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND A.2 Verify MFIV is closed or isolated.

Once per 7 days B. One or two MFCVs inoperable. B.1 Close or isolate the MFCV the flow path.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND B.2 Verify MFCV is closed or isolated.

Once per 7 days C. Two valves in the same flow path inoperable. C.1 Isolate affected flow path. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

Technical Specifications MFIVs and MFCVs

3.7.3 Turkey

Point Unit 7 3.7.3 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time not met. D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND D.2 Be in MODE 4 with the Reactor Coolant System (RCS) cooling provided by the Normal Residual Heat Removal System (RNS).

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND D.3.1 Isolate the affected flow path(s). 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR D.3.2 Be in MODE 5. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 ----------------------------------------------------------------------- - NOTE - Only required to be performed prior to entry into MODE 2. -----------------------------------------------------------------------

Verify the closure time of each MFIV and MFCV is 5 seconds on an actual or simulated actuation signal. In accordance with the Inservice Testing Program

Technical Specifications Secondary Specific Activity

3.7.4 Turkey

Point Unit 7 3.7.4 - 1

3.7 PLANT

SYSTEMS 3.7.4 Secondary Specific Activity LCO 3.7.4 The specific activity of the secondary coolant shall be < 0.01 Ci/gm DOSE EQUIVALENT I-131. APPLICABILITY: MODES 1, 2, 3 and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not within limit.

A.1 AND A.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify the specific activity of the secondary coolant 0.01 Ci/gm DOSE EQUIVALENT I-131.

31 days Technical Specifications Spent Fuel Pool Water Level

3.7.5 Turkey

Point Unit 7 3.7.5 - 1

3.7 PLANT

SYSTEMS 3.7.5 Spent Fuel Pool Water Level LCO 3.7.5 The spent fuel pool water level shall be 23 ft above the top of irradiated fuel assemblies seated in the storage racks. APPLICABILITY: At all times. ACTIONS - NOTE - LCOs 3.0.3 and 3.0.8 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel pool water level < 23 ft. A.1 Suspend movement of irradiated fuel assemblies in the spent fuel pool.

Immediately AND A.2 Initiate action to restore water level to 23 ft. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify the spent fuel pool water level is 23 ft above the top of the irradiated fuel assemblies seated in the storage racks.

7 days Technical Specifications VES 3.7.6 Turkey Point Unit 7 3.7.6 - 1

3.7 PLANT

SYSTEMS 3.7.6 Main Control Room Emergency Habitability System (VES) LCO 3.7.6 The VES shall be OPERABLE. -------------------------------------------------------------------------------------------------- - NOTE - The main control room envelope (MCRE) boundary may be opened intermittently under administrative control. -------------------------------------------------------------------------------------------------- APPLICABILITY: MODES 1, 2, 3, and 4, During movement of irradiated fuel assemblies. ACTIONS - NOTE - LCO 3.0.8 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One valve or damper inoperable. A.1 Restore valve or damper to OPERABLE status.

7 days B. One PMS division inoperable in MCR Load-Shed Panel(s). B.1 Restore MCR Load-shed panel(s) to OPERABLE status. 7 days C. MCRE air temperature not within limit.

C.1 Restore MCRE air temperature to within limit.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D. Air temperature in one or more required rooms not within limit. D.1 Restore air temperature of required room(s) to within limit. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months E. VES inoperable due to inoperable MCRE boundary in MODE 1, 2, 3, or 4. E.1 Initiate action to implement mitigating actions.

Immediately

Technical Specifications VES 3.7.6 Turkey Point Unit 7 3.7.6 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME AND E.2 Verify mitigating actions ensure MCRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND E.3 Restore MCRE boundary to OPERABLE status.

90 days F. One bank of VES air tanks (8 tanks) inoperable. F.1 Verify that the OPERABLE tanks contain greater than 245,680 scf of compressed air. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND F.2 Verify VBS MCRE ancillary fans and supporting equipment are available.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AND F.3 Restore VES to OPERABLE status.

7 days G. Required Action and associated Completion Time of Conditions A, B, C, D, E or F not met in MODE 1, 2, 3, or 4. G.1 AND G.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours OR VES inoperable for reasons other than Conditions A, B, C, or D, E or F in MODE 1, 2, 3, or 4.

Technical Specifications VES 3.7.6 Turkey Point Unit 7 3.7.6 - 3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and associated Completion Time of Conditions A, B, C, D, E or F not met during movement of irradiated

fuel. H.1 Suspend movement of irradiated fuel assemblies.

Immediately OR VES inoperable for reasons other than Conditions A, B, C, D, E or F during movement of irradiated fuel. OR VES inoperable due to inoperable MCRE

boundary during movement of irradiated

fuel. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify MCRE air temperature is 75°F. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.7.6.2 Verify that the compressed air storage tanks contain greater than 327,574 scf of compressed air.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.7.6.3 Verify the air temperatures of required rooms are 85°F. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.7.6.4 Operate VES for 15 minutes. 31 days SR 3.7.6.5 Verify that each VES air header manual isolation valve is in an open position.

31 days Technical Specifications VES 3.7.6 Turkey Point Unit 7 3.7.6 - 4 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.7.6.6 Verify that the air quality of the air storage tanks meets the requirements of Appendix C, Table C-1 of ASHRAE Standard 62 with a pressure dew point of 40°F or lower at 3400 psig or greater.

92 days SR 3.7.6.7 Verify that each VES air delivery isolation valve is OPERABLE. In accordance with the Inservice Testing Program SR 3.7.6.8 Verify that each VES pressure relief isolation valve within the MCRE pressure boundary is OPERABLE. In accordance with the Inservice Testing Program SR 3.7.6.9 Verify that the self-contained pressure regulating valve in each VES air delivery flow path is OPERABLE. In accordance with the Inservice Testing Program SR 3.7.6.10 Perform required MCRE unfiltered air inleakage testing in accordance with the Main Control Room Envelope Habitability Program. In accordance with the Main Control Room Envelope Habitability Program SR 3.7.6.11 Perform required VES Passive Filtration system filter testing in accordance with the Ventilation Filter Testing Program (VFTP). In accordance with the VFTP SR 3.7.6.12 Verify the MCR load-shed function actuates upon receipt of an actual or simulated actuation signal.

24 months SR 3.7.6.13 Verify that all MCRE isolation valves are OPERABLE and will close upon receipt of an actual or simulated actuation signal.

24 months SR 3.7.6.14 Verify that each VES pressure relief damper is OPERABLE.

24 months

Technical Specifications Startup Feedwater Isolation and Control Valves

3.7.7 Turkey

Point Unit 7 3.7.7 - 1

3.7 PLANT

SYSTEMS 3.7.7 Startup Feedwater Isolation and Control Valves LCO 3.7.7 Both Startup Feedwater Isolation Valves and Control Valves shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4 except when the startup feedwater flow paths are isolated. ACTIONS - NOTES - 1. Flow paths may be unisolated intermittently under administrative controls. 2. Separate Condition entry is allowed for each flow path.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths with one inoperable valve. A.1 Isolate the affected flow path(s). 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND A.2 Verify affected flow path(s) is isolated.

Once per 7 days B. One flow path with two inoperable valves. B.1 Isolate the affected flow path. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months C. Required Action and associated Completion Time not met. C.1 AND C.2 Be in MODE 3.

Be in MODE 4 with the Reactor Coolant System (RCS) cooling provided by the Normal Residual Heat Removal System (RNS).

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 24 hours AND C.3 Isolate the affected flow path(s). 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Technical Specifications Startup Feedwater Isolation and Control Valves

3.7.7 Turkey

Point Unit 7 3.7.7 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify both startup feedwater isolation and control valves are OPERABLE. In accordance with the Inservice Testing Program

Technical Specifications Main Steam Line Leakage

3.7.8 Turkey

Point Unit 7 3.7.8 - 1

3.7 PLANT

SYSTEMS 3.7.8 Main Steam Line Leakage LCO 3.7.8 Main Steam Line leakage through the pipe walls inside containment shall be limited to 0.5 gpm. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Main Steam Line leakage exceeds

operational limit.

A.1 AND A.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify main steam line leakage into the containment sump 0.5 gpm. Per SR 3.4.7.1

Technical Specifications Fuel Storage Pool Makeup Water Sources

3.7.9 Turkey

Point Unit 7 3.7.9 - 1

3.7 PLANT

SYSTEMS 3.7.9 Fuel Storage Pool Makeup Water Sources LCO 3.7.9 Fuel storage pool makeup water sources shall be OPERABLE. -------------------------------------------------------------------------------------------------- - NOTES - 1. OPERABILITY of the cask washdown pit is required when the calculated spent fuel storage pool decay heat > 4.7 MWt and 7.2 MWt.

2. OPERABILITY of the cask loading pit is required when the calculated spent fuel storage pool decay heat > 5.6 MWt and 7.2 MWt. 3. OPERABILITY of the Passive Containment Cooling Water Storage Tank (PCCWST) is required as a spent fuel storage pool makeup water source when the calculated spent fuel storage pool decay heat > 7.2 MWt. If the reactor decay heat is > 6.0 MWt, the PCCWST must be exclusively available for containment cooling in accordance with LCO 3.6.7. -------------------------------------------------------------------------------------------------- APPLICABILITY: During storage of fuel in the spent fuel storage pool with a calculated decay heat > 4.7 MWt.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required spent fuel storage pool makeup water sources inoperable. A.1 ------------------------------------ - NOTE - LCOs 3.0.3 and 3.0.8 are not applicable. ------------------------------------

Initiate action to restore the required makeup water source(s) to OPERABLE status. Immediately

Technical Specifications Fuel Storage Pool Makeup Water Sources

3.7.9 Turkey

Point Unit 7 3.7.9 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.1 ----------------------------------------------------------------------- - NOTE - Only required to be performed when spent fuel storage pool calculated decay heat is > 7.2 MWt. -----------------------------------------------------------------------

Verify one passive containment cooling system, motor-operated valve in each flow path is closed and locked, sealed, or otherwise secured in position.

7 days SR 3.7.9.2 ----------------------------------------------------------------------- - NOTE - Only required to be performed when spent fuel storage pool calculated decay heat is > 7.2 MWt. -----------------------------------------------------------------------

Verify the PCCWST volume is 756,700 gallons. 7 days SR 3.7.9.3 ----------------------------------------------------------------------- - NOTE - Only required to be performed when spent fuel storage pool calculated decay heat is 7.2 MWt. -----------------------------------------------------------------------

Verify the water level in the cask washdown pit is 13.75 ft.

31 days SR 3.7.9.4 ----------------------------------------------------------------------- - NOTE - Only required to be performed when spent fuel storage pool calculated decay heat is > 5.6 MWt and 7.2 MWt. -----------------------------------------------------------------------

Verify the water level in the cask loading pit is 43.9 ft. and in communication with the spent fuel storage pool.

31 days Technical Specifications Fuel Storage Pool Makeup Water Sources

3.7.9 Turkey

Point Unit 7 3.7.9 - 3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.9.5 Verify the spent fuel storage pool makeup isolation valves PCS-PL-V009, PCS-PL-V045, PCS-PL-V051, SFS-PL-V042, SFS-PL-V045, SFS-PL-V049, SFS- PL-V066, and SFS-PL-V068 are OPERABLE in accordance with the Inservice Testing Program. In accordance with the Inservice Testing Program

Technical Specifications Steam Generator Isolation Valves 3.7.10 Turkey Point Unit 7 3.7.10 - 1

3.7 PLANT

SYSTEMS 3.7.10 Steam Generator (SG) Isolation Valves LCO 3.7.10 The steam generator isolation valves shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3. MODE 4 with the Reactor Coolant Sy stem (RCS) not being cooled by the Normal Residual Heat Removal System (RNS).

ACTIONS - NOTES - 1. Steam generator blowdown flow path(s) may be unisolated intermittently under administrative controls. 2. Separate Condition entry is allowed for each flow path.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORV flow paths with one SG isolation valve inoperable. A.1 Isolate the flow path by use of at least one closed and deactivated automatic valve. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. One or more blowdown flow paths with one SG isolation valve inoperable. B.1 Isolate the flow path by one closed valve.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND B.2 Verify that the affected SG blowdown flow path is isolated.

Once per 7 days C. One or more PORV flow paths with two SG isolation valves inoperable. C.1 Isolate the affected flow path by use of at least one closed and deactivated automatic valve.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Technical Specifications Steam Generator Isolation Valves 3.7.10 Turkey Point Unit 7 3.7.10 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. One or more blowdown flow paths with two SG

isolation valves inoperable. D.1 Isolate the flow path by one closed valve.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND D.2 Verify that the affected SG blowdown flow path is isolated.

Once per 7 days E. Required Action and associated Completion Time not met. E.1 AND E.2 Be in MODE 3.

Be in MODE 4 with the RCS cooling provided by the RNS. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 24 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.10.1 Verify each steam generator isolation valve (PORV block valves (SGS-PL-V027A & B), PORVs (SGS-PL-V233A & B), and blowdown isolation valves (SGS-PL-V074A & B and SGS-PL-V075A & B)) is OPERABLE by stroking the valve closed. In accordance with the Inservice Testing Program

Technical Specifications Fuel Storage Pool Boron Concentration 3.7.11 Turkey Point Unit 7 3.7.11 - 1

3.7 PLANT

SYSTEMS 3.7.11 Fuel Storage Pool Boron Concentration LCO 3.7.11 The fuel storage pool boron concentration shall be 2300 ppm. APPLICABILITY: When fuel assemblies are stored in the fuel storage pool and a fuel storage pool verification has not been performed since the last movement of fuel assemblies in the fuel storage pool. ACTIONS - NOTE - LCOs 3.0.3 and 3.0.8 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool boron concentration not within limit. A.1 Suspend movement of fuel assemblies in the fuel storage pool.

Immediately AND A.2.1 Initiate action to restore fuel storage pool boron concentration to within limit. Immediately OR A.2.2 Initiate action to perform a fuel storage pool verification.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify the fuel storage pool boron concentration is within limit.

7 days Technical Specifications Spent Fuel Pool Storage 3.7.12 Turkey Point Unit 7 3.7.12 - 1

3.7 PLANT

24 months

Technical Specifications DC Sources -

Shutdown 3.8.2 Turkey Point Unit 7 3.8.2 - 1

3.8 ELECTRICAL

POWER SYSTEMS 3.8.2 DC Sources - Shutdown LCO 3.8.2 DC electrical power subsystems shall be OPERABLE to support the DC electrical power distribution subsystem(s) required by LCO 3.8.6, "Distribution Systems - Shutdown." APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies. ACTIONS - NOTE - LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required DC electrical power subsystems inoperable. A.1 Declare affected required features inoperable.

Immediately OR A.2.1 Suspend CORE ALTERATIONS.

Immediately AND A.2.2 Suspend movement of irradiated fuel assemblies.

Immediately AND A.2.3 Suspend operations with a potential for draining the reactor vessel.

Immediately AND

Technical Specifications DC Sources -

Shutdown 3.8.2 Turkey Point Unit 7 3.8.2 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A.2.4 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

Immediately AND A.2.5 Initiate action to restore required DC electrical power subsystems to OPERABLE status.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 ----------------------------------------------------------------------- - NOTE - The following SRs are not required to be performed:

SR 3.8.1.2 and SR 3.8.1.3. -----------------------------------------------------------------------

For DC sources required to be OPERABLE, the following SRs are applicable:

SR 3.8.1.1 SR 3.8.1.2 SR 3.8.1.3 In accordance with applicable SRs

Technical Specifications Inverters -

Operating

3.8.3 Turkey

Point Unit 7 3.8.3 - 1

3.8 ELECTRICAL

POWER SYSTEMS 3.8.3 Inverters - Operating LCO 3.8.3 The Division A, B, C, and D inverters (Divisions A and D, one each and Divisions B and C two each; six total) shall be OPERABLE. -------------------------------------------------------------------------------------------------- - NOTES - One inverter may be disconnected from its associated DC bus for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to perform an equalizing charge on its associated battery, providing: 1. The associated instrument and control bus is energized from its Class 1E constant voltage source transformer; and 2. All other AC instrument and control buses are energized from their associated OPERABLE inverters. -------------------------------------------------------------------------------------------------- APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One inverter inoperable. A.1 ------------------------------------ - NOTE - Enter applicable Conditions and Required Actions of LCO 3.8.5 "Distribution Systems -

Operating" with any instrument and control bus de-energized. ------------------------------------

Restore inverter to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. Required Action and associated Completion Time

not met. B.1 AND B.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours Technical Specifications Inverters -

Operating

3.8.3 Turkey

Point Unit 7 3.8.3 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify correct inverter voltage, frequency, and alignment to required AC instrument and control buses. 7 days Technical Specifications Inverters -

Shutdown 3.8.4 Turkey Point Unit 7 3.8.4 - 1

3.8 ELECTRICAL

POWER SYSTEMS 3.8.4 Inverters - Shutdown LCO 3.8.4 Inverters shall be OPERABLE to support the onsite Class 1E power distribution subsystems required by LCO 3.8.6, "Distribution Systems -

Shutdown." APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies. ACTIONS - NOTE - LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required inverters inoperable. A.1 Declare affected required features inoperable.

Immediately OR A.2.1 Suspend CORE ALTERATIONS.

Immediately AND A.2.2 Suspend movement of irradiated fuel assemblies.

Immediately AND A.2.3 Suspend operations with a potential for draining the reactor vessel.

Immediately AND

Technical Specifications Inverters -

Shutdown 3.8.4 Turkey Point Unit 7 3.8.4 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A.2.4 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

Immediately AND A.2.5 Initiate action to restore required inverters to OPERABLE status.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify correct inverter voltage, frequency, and alignments to required AC instrument and control buses. 7 days Technical Specifications Distribution Systems

- Operating

3.8.5 Turkey

Point Unit 7 3.8.5 - 1

3.8 ELECTRICAL

POWER SYSTEMS 3.8.5 Distribution Systems - Operating LCO 3.8.5 The Division A, B, C, and D AC instrument and control bus and DC electrical power distribution subsystems shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Division AC instrument and control bus inoperable. A.1 Restore AC instrument and control bus to OPERABLE status. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from discovery of failure to meet the LCO B. One Division DC electrical power distribution subsystem inoperable. B.1 Restore DC electrical power distribution subsystem to OPERABLE status. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from discovery of failure to

meet the LCO C. Two Divisions AC instrument and control bus inoperable. C.1 Restore AC instrument and control bus to OPERABLE status. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet the LCO. D. Two Divisions DC electrical power distribution subsystem inoperable. D.1 Restore DC electrical power distribution subsystem to OPERABLE status. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months from discovery of failure to meet the LCO.

Technical Specifications Distribution Systems

- Operating

3.8.5 Turkey

Point Unit 7 3.8.5 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time not met. E.1 AND E.2 Be in MODE 3.

Be in MODE 5.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 36 hours F. Two Divisions with inoperable distribution subsystems that result in a loss of safety function. F.1 Enter LCO 3.0.3. Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 Verify correct breaker and switch alignments and voltage to required DC and AC instrument and control bus electrical power distribution subsystems.

7 days Technical Specifications Distribution Systems

- Shutdown 3.8.6 Turkey Point Unit 7 3.8.6 - 1

3.8 ELECTRICAL

POWER SYSTEMS 3.8.6 Distribution Systems - Shutdown LCO 3.8.6 The necessary portions of DC and AC instrument and control bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE. APPLICABILITY: MODES 5 and 6, During movement of irradiated fuel assemblies. ACTIONS - NOTE - LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required DC or AC instrument and control bus electrical power distribution subsystems inoperable. A.1 Declare associated supported required features inoperable.

Immediately OR A.2.1 Suspend CORE ALTERATIONS.

Immediately AND A.2.2 Suspend movement of irradiated fuel assemblies.

Immediately AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel. Immediately AND

Technical Specifications Distribution Systems

- Shutdown 3.8.6 Turkey Point Unit 7 3.8.6 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME A.2.4 Suspend operations involving positive reactivity additions that could result in loss of required SDM or boron concentration.

Immediately AND A.2.5 Initiate actions to restore required DC and AC instrument and control bus electrical power distribution

subsystems to OPERABLE status. Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify correct breaker and switch alignments and voltage to required DC and AC instrument and control bus electrical power distribution subsystems.

7 days Technical Specifications Battery Parameters

3.8.7 Turkey

Point Unit 7 3.8.7 - 1

3.8 ELECTRICAL

POWER SYSTEMS 3.8.7 Battery Parameters LCO 3.8.7 Battery Parameters for Division A, B, C, and D batteries shall be within limits. APPLICABILITY: When associated DC electrical power sources are required to be OPERABLE. ACTIONS - NOTE - Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries in one division with one or more battery cells float voltage < 2.07 V.

A.1 AND A.2 Perform SR 3.8.1.1.

Perform SR 3.8.7.1.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND A.3 Restore affected cell voltage 2.07 V. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. One or more batteries in one division with float current > 2 amps.

B.1 AND B.2 Perform SR 3.8.1.1.

Restore battery float current to 2 amps.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 24 hours Technical Specifications Battery Parameters

3.8.7 Turkey

Point Unit 7 3.8.7 - 2 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME -------------------------------- - NOTE - Required Action C.2 shall be completed if electrolyte

level was below the top of plates. -------------------------------- -------------------------------------------------- NOTE - Required Actions C.1 and C.2 are only applicable if electrolyte level was below the top of plates. ------------------------------------------------

C. One or more batteries in one division with one or more cells electrolyte level less than minimum established design limits. C.1 Restore electrolyte level to above top of plates.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months AND C.2 Verify no evidence of leakage. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND C.3 Restore electrolyte level to greater than or equal to minimum established design limits.

31 days D. One or more batteries in one division with pilot cell electrolyte temperature less than minimum established design limits. D.1 Restore battery pilot cell temperature to greater

than or equal to minimum established design limits.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. One or more batteries in two or more divisions with battery parameters not within limits. E.1 Restore battery parameters for batteries in three divisions to within limits. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Technical Specifications Battery Parameters

3.8.7 Turkey

Point Unit 7 3.8.7 - 3 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and associated Completion Time not met. OR One or more batteries in one division with one or

more battery cells float voltage < 2.07 V and float current > 2 amps. F.1 Declare associated battery inoperable.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 ----------------------------------------------------------------------- - NOTE - Not required to be met when battery terminal voltage is less than the minimum established float voltage of

SR 3.8.1.1. -----------------------------------------------------------------------

Verify each battery float current is 2 amps. 7 days SR 3.8.7.2 Verify each battery pilot cell voltage is 2.07 V. 31 days SR 3.8.7.3 Verify each battery connected cell electrolyte level is greater than or equal to minimum established design limits. 31 days SR 3.8.7.4 Verify each battery pilot cell temperature is greater than or equal to minimum established design limits.

31 days SR 3.8.7.5 Verify each battery connected cell voltage is 2.07 V. 92 days

Technical Specifications Battery Parameters

3.8.7 Turkey

Point Unit 7 3.8.7 - 4 SURVEILLANCE REQUIREMENTS (continued) SURVEILLANCE FREQUENCY SR 3.8.7.6 ----------------------------------------------------------------------- - NOTE- This Surveillance shall not be performed in MODE 1, 2, 3, or 4. However, credit may be taken for unplanned events that satisfy this SR. -----------------------------------------------------------------------

Verify battery capacity is 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.

60 months AND 12 months when battery shows degradation, or has reached 85%

of the expected life with capacity

< 100% of manufacturer's

rating AND 24 months when battery has reached 85% of

the expected life with capacity 100% of manufacturer's

rating Technical Specifications Boron Concentration

3.9.1 Turkey

Point Unit 7 3.9.1 - 1

3.9 REFUELING

OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentration of the R eactor Coolant System (RCS), the fuel transfer canal, and the refueling cavity shall be maintained within the limit specified in COLR. APPLICABILITY: MODE 6. -------------------------------------------------------------------------------------------------- - NOTE - Only applicable to the fuel transfer canal and the refueling cavity when connected to the RCS. -------------------------------------------------------------------------------------------------- ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not within limit. A.1 Suspend CORE ALTERATIONS.

Immediately AND A.2 Suspend positive reactivity additions.

Immediately AND A.3 Initiate actions to restore boron concentration to within limits.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit specified in the COLR.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Technical Specifications Unborated Water Source Flow Paths

3.9.2 Turkey

Point Unit 7 3.9.2 - 1

3.9 REFUELING

OPERATIONS 3.9.2 Unborated Water Source Flow Paths LCO 3.9.2 Each unborated water source flow path shall be isolated. APPLICABILITY: MODE 6. ACTIONS - NOTE - Separate condition entry is allowed for each unborated water source flow path.

CONDITION REQUIRED ACTION COMPLETION TIME A. -------------------------------- - NOTE - Required Action A.3 must be completed whenever Condition A is

entered. -------------------------------- One or more flow paths not isolated. A.1 Suspend CORE ALTERATIONS.

Immediately AND A.2 Initiate actions to isolate flow paths.

Immediately AND A.3 Perform SR 3.9.1.1. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify each unborated water source flow path is isolated by at least one valve secured in the closed position.

31 days Technical Specifications Nuclear Instrumentation

3.9.3 Turkey

Point Unit 7 3.9.3 - 1

3.9 REFUELING

OPERATIONS 3.9.3 Nuclear Instrumentation LCO 3.9.3 Two source range neutron flux monitors shall be OPERABLE. APPLICABILITY: MODE 6. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required source range neutron flux

monitor inoperable. A.1 Suspend CORE ALTERATIONS.

Immediately AND A.2 Suspend operations that would cause introduction into the Reactor Coolant

System (RCS), coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

Immediately B. Two required source range neutron flux monitors inoperable. B.1 Initiate action to restore one source range neutron flux monitor to OPERABLE status. Immediately AND B.2 Perform SR 3.9.1.1. Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Technical Specifications Nuclear Instrumentation

3.9.3 Turkey

Point Unit 7 3.9.3 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform a CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.3.2 ----------------------------------------------------------------------- - NOTE- Neutron detectors are excluded from CHANNEL CALIBRATION. -----------------------------------------------------------------------

Perform CHANNEL CALIBRATION. 24 months

Technical Specifications Refueling Cavity Water Level

3.9.4 Turkey

Point Unit 7 3.9.4 - 1

3.9 REFUELING

OPERATIONS 3.9.4 Refueling Cavity Water Level LCO 3.9.4 Refueling Cavity Water Level shall be maintained 23 ft above the top of the reactor vessel flange. APPLICABILITY: During movement of irradiated fuel assemblies within containment. ACTIONS - NOTE - LCO 3.0.8 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Refueling cavity water level not within limit. A.1 Suspend movement of irradiated fuel assemblies within containment.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify that refueling cavity water level is 23 ft above the top of reactor vessel flange.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Technical Specifications Containment Penetrations

3.9.5 Turkey

Point Unit 7 3.9.5 - 1

3.9 REFUELING

OPERATIONS 3.9.5 Containment Penetrations LCO 3.9.5 The containment penetrations shall be in the following status: a. The equipment hatches closed and held in place by four bolts or, if open, the containment air filtration system (VFS) shall be OPERABLE and operating; b. One door in each air lock closed or, if open, the VFS shall be OPERABLE and operating; c. The containment spare penetrations closed or, if open, the VFS shall be OPERABLE and operating; d. Each penetration providing direct access from the containment atmosphere to the outside atmosphere either: 1. Closed by a manual or automatic isolation valve, blind flange, or equivalent, or 2. Capable of being closed by an OPERABLE Containment Isolation signal. -------------------------------------------------------------------------------------------------- - NOTE - Penetration flow path(s) providing direct access from the containment atmosphere to the outside atmosphere may be unisolated under administrative controls. -------------------------------------------------------------------------------------------------- APPLICABILITY: During movement of irradiated fuel assemblies within containment. ACTIONS - NOTE - LCO 3.0.8 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Suspend movement of irradiated fuel assemblies within containment.

Immediately

Technical Specifications Containment Penetrations

3.9.5 Turkey

Point Unit 7 3.9.5 - 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify each required containment penetration is in the required status.

7 days SR 3.9.5.2 ----------------------------------------------------------------------- - NOTE- Not required to be met for containment purge and exhaust valve(s) in penetrations closed to comply with LCO 3.9.5.d.1. -----------------------------------------------------------------------

Verify each required containment purge and exhaust valve actuates to the isolation position on a manual actuation signal. In accordance with the Inservice Test Program SR 3.9.5.3 Verify the VFS can maintain a negative pressure

( -0.125 inches water gauge relative to outside atmospheric pressure) in the area enclosed by the containment and alternate barrier.

24 months SR 3.9.5.4 Operate each VFS train for 10 continuous hours with the heaters operating. Within 31 days prior to fuel movement or CORE ALTERATIONS

Technical Specifications VFS 3.9.6 Turkey Point Unit 7 3.9.6 - 1

3.9 REFUELING

OPERATIONS 3.9.6 Containment Air Filtration System (VFS) LCO 3.9.6 One VFS exhaust subsystem shall be OPERABLE. APPLICABILITY: During movement of irradiated fuel assemblies in the fuel building. ACTIONS - NOTE - LCOs 3.0.3 and 3.0.8 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required VFS exhaust subsystem inoperable. A.1 Suspend movement of irradiated fuel assemblies in the fuel building.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Operate each VFS exhaust subsystem for > 10 continuous hours with the heaters operating. Within 31 days

prior to fuel movement SR 3.9.6.2 Verify the VAS fuel handling area subsystem aligns to the VFS exhaust subsystem on an actual or simulated actuation signal.

24 months SR 3.9.6.3 Verify one VFS exhaust subsystem can maintain a negative pressure (< -0.125 inches water gauge relative to outside atmospheric pressure) in the fuel handling area.

24 months

Technical Specifications Decay Time

3.9.7 Turkey

Point Unit 7 3.9.7 - 1

3.9 REFUELING

OPERATIONS 3.9.7 Decay Time LCO 3.9.7 The reactor shall be subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel. ACTIONS - NOTE - LCO 3.0.8 is not applicable.

Point Unit 7 4.0 - 3

4.0 DESIGN

FEATURES

4.3.2 Drainage

The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below a minimum water depth of 23 ft above the surface of the fuel storage racks. 4.3.3 Capacity The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 889 fuel assemblies.

Technical Specifications Design Features

4.0 Turkey

Point Unit 7 4.0 - 4 FIGURE 4.1-1 Low Population Zone and Site Boundary Map Technical Specifications Design Features

4.0 Turkey

Point Unit 7 4.0 - 5 FIGURE 4.1-2 Exclusion Area Boundary Technical Specifications Design Features

4.0 Turkey

Point Unit 7 4.0 - 6 Region 1 (A1, A2, A3) - 243 locations Region 2 (B1, B2, B3, B4, C1) - 641 locations Defective Fuel Cells (DFCs) - 5 locations Total Storage Locations - 889 Figure 4.3-1 Discrete Two Region Spent Fuel Pool Rack Layout

Technical Specifications Responsibility

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Point Unit 7 5.1 - 1

5.0 ADMINISTRATIVE

CONTROLS

5.1 Responsibility

5.1.1 The plant manager shall be responsible for overall unit operations and shall delegate in writing the succession to this responsibility during his absence. The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment or modification to systems or equipment that affect nuclear safety. 5.1.2 The shift manager (SM) shall be responsible for the control room command function. During any absence of the SM from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the SM from the control room while the unit is in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

Technical Specifications Organization

5.2 Turkey

Point Unit 7 5.2 - 1

5.0 ADMINISTRATIVE

CONTROLS 5.2 Organization

5.2.1 Onsite

and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant. a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the FSAR; b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant; c. A specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and d. The individuals who train the operating staff, carry out radiation protection, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operation pressures. 5.2.2 Unit Staff The unit staff organization shall include the following: a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODE 1, 2, 3, or 4. b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.e for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

Technical Specifications Organization

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Point Unit 7 5.2 - 2

5.2 Organization

5.2.2 Unit Staff (continued)

c. A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position. d. The operations manager or assistant operations manager shall hold an SRO license. e. An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

Technical Specifications Unit Staff Qualifications

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Point Unit 7 5.3 - 1

5.0 ADMINISTRATIVE

CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 3, 2000, with the following exception: a. During cold license operator training through the first refueling outage, the Regulatory Position C.1.b of Regulatory Guide 1.8, Revision 2, 1987, applies: cold license operator candidates meet the training elements defined in ANSI/ANS 3.1-1993 but are exempt from the experience requirements defined in ANSI/ANS 3.1-1993. 5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed reactor operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

Technical Specifications Procedures

5.4 Turkey

Point Unit 7 5.4 - 1

5.0 ADMINISTRATIVE

CONTROLS

5.4 Procedures

5.4.1 Written

procedures shall be established, implemented, and maintained covering the following activities: a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978; b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33;

c. Quality assurance for effluent and environmental monitoring; d. Fire Protection Program implementation; and

e. All programs specified in Specification 5.5.

Technical Specifications Programs and Manuals

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Point Unit 7 5.5 - 1

5.0 ADMINISTRATIVE

CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained. 5.5.1 Offsite Dose Calculation Manual (ODCM) a. The ODCM shall contain the methodology and 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 and trip setpoints, and in the conduct of the radiological environmental

monitoring program; and b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification 5.6.2 and Specification 5.6.3. Licensee initiated changes to the ODCM: a. Shall be documented and records of reviews performed shall be retained. This documentation shall contain: 1. Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and 2. A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; b. Shall become effective after the approval of the plant manager; and

c. Shall be submitted to the NRC in the form of a complete, legible copy of the changed portion of the ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

a. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are 0.60 L a for the Type B and Type C tests and 0.75 L a for Type A tests; 2. Air lock testing acceptance criteria are: a) Overall air lock leakage rate is 0.05 L a when tested at P a , b) For each door, leakage rate is 0.01 L a when pressurized to 10 psig. e. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program. f. Nothing in these Technical Specifications shall be construed to modify the testing Frequencies required by 10 CFR 50, Appendix J. 5.5.9 System Level OPERABILITY Testing Program The System Level OPERABILITY Testing Program provides requirements for performance tests of passive systems. The System Level Inservice Tests specified in Section 3.9.6 and Table 3.9-17 apply when specified by individual Surveillance Requirements. a. The provisions of SR 3.0.2 are applicable to the test frequencies specified in Table 3.9-17 for performing system level OPERABILITY testing activities;

and b. The provisions of SR 3.0.3 are applicable to system level OPERABILITY testing activities. 5.5.10 Component Cyclic or Transient Limit This program provides controls to track the Table 3.9-1A cyclic and transient occurrences to ensure that components are maintained within the design limits.

2. The instrument channel trip setting shall be set to a value within the specified ALT around the specified NTS at the completion of the surveillance; otherwise, the surveillance requirement is not met and the instrument channel shall be immediately declared inoperable.

Technical Specifications Programs and Manuals

5.5 Turkey

Point Unit 7 5.5 - 14

5.5 Programs

and Manuals 5.5.14 Setpoint Program (SP) (continued) d. The difference between the instrument channel trip setting as-found value and the previously recorded as-left value for each Technical Specification required automatic protection instrumentation function shall be trended and evaluated to verify that the instrument channel is functioning in accordance with its design basis. e. The SP shall establish a document containing the current value of the specified NTS, AFT, and ALT for each Technical Specification required automatic protection instrumentation function and references to the calculation documentation. Changes to this document shall be governed by the regulatory requirement of 10 CFR 50.59. In addition, changes to the specified NTS, AFT, and ALT values shall be governed by the approved setpoint methodology. This document, including any revisions or supplements, shall be provided upon issuance to the NRC.

Technical Specifications Reporting Requirements

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Point Unit 7 5.6 - 1

5.0 ADMINISTRATIVE

CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4. 5.6.1 Occupational Radiation Exposure Report

- NOTE - A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem/yr and their associated collective deep dose equivalent (reported in person-rem) according to work and job functions (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance, waste processing, and refueling). This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), electronic dosimeter or film badge measurements. Small exposures totaling < 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total deep dose equivalent received from external sources should be assigned to specific major work functions. The report shall be submitted by April 30 of each year. The initial report shall be submitted by April 30 of the year following the initial criticality. 5.6.2 Annual Radiological Environmental Operating Report

- NOTE - A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the radiological environmental monitoring program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

Technical Specifications Reporting Requirements

5.6 Turkey

Point Unit 7 5.6 - 2

5.6 Reporting

Requirements

5.6.2 Annual

Radiological Environmental Operating Report (continued) The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible. 5.6.3 Radioactive Effluent Release Report

- NOTE - A single submittal may be made for a multiple unit station.

The Radioactive Effluent Release Report covering the operation of the unit in the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1. 5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis no later than the 15th of each month following the

calendar month covered by the report. 5.6.5 CORE OPERATING LIMITS REPORT (COLR) a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

2.1.1, "Reactor Core SLs" 3.1.1, "SHUTDOWN MARGIN (SDM)" 3.1.3, "Moderator Temperature Coefficient" 3.1.5, "Shutdown Bank Insertion Limits" 3.1.6, "Control Bank Insertion Limits" 3.2.1, "Heat Flux Hot Channel Factor"

Technical Specifications Reporting Requirements

5.6 Turkey

Point Unit 7 5.6 - 3

5.6 Reporting

Requirements 5.6.5 CORE OPERATING LIMITS REPORT (continued) 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor" 3.2.3, "AXIAL FLUX DIFFERENCE" 3.2.5, "OPDMS-monitored Power Distribution Parameters" 3.3.1, "Reactor Trip System (RTS) Instrumentation" 3.4.1, "RCS Pressure, Temperature, and DNB Limits" 3.9.1, "Boron Concentration" b. 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. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary) and WCAP-9273-NP-A (Non-Proprietary). (Methodology for Specifications 3.1.4 - Moderator Temperature Coefficient, 3.1.6 - Shutdown Bank Insertion Limits, 3.1.7 - Control Bank Insertion Limits, 3.2.1 - Heat Flux Hot Channel Factor, 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor, 3.2.3 - AXIAL FLUX DIFFERENCE, and 3.9.1 - Boron Concentration.) 2a. WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report," September 1974 (Westinghouse Proprietary) and WCAP-8403 (Non-Proprietary). (Methodology for Specification 3.2.3 - AXIAL FLUX DIFFERENCE (Constant Axial Offset Control).) 2b. T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC)

January 31, 1980 -

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Follow Package. (Methodology for Specification 3.2.3 - AXIAL FLUX DIFFERENCE (Constant Axial Offset Control).) 2c. NUREG-0800, Standard Review Plan, U.S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981. Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981. (Methodology for Specification 3.2.3 - AXIAL FLUX DIFFERENCE (Constant Axial Offset Control).)

Technical Specifications Reporting Requirements

5.6 Turkey

Point Unit 7 5.6 - 4

5.6 Reporting

Requirements 5.6.5 CORE OPERATING LIMITS REPORT (continued) 3. WCAP-10216-P-A, Revision 1A, "Relaxation of Constant Axial Offset Control FQ Surveillance Technical Specification," February 1994 (Westinghouse Proprietary) and WCAP-10217-A (Non-Proprietary). (Methodology for Specifications 3.2.3 - AXIAL FLUX DIFFERENCE (Relaxed Axial Offset Control) and 3.2.1 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements for FQ Methodology).) 4. WCAP-12945-P-A, Volumes 1-5, "Westinghouse Code Qualification Document for Best Estimate Loss of Coolant Accident Analysis,"

Revision 2, March 1998 (Westinghouse Proprietary) and WCAP-14747 (Non-Proprietary). (Methodology for Specification 3.2.1 - Heat Flux Hot Channel Factor.) 5. WCAP-12472-P-A, "BEACON Core Monitoring and Operations Support System," August 1994, Addendum 1, May 1996 (Westinghouse Proprietary), and Addendum 2, March 2001 (Westinghouse Proprietary) and WCAP-12473-A (Non-Proprietary). (Methodology for Specification 3.2.5 - OPDMS - Monitored Power Distribution Parameters.) 6. APP-GW-GLR-137, Revision 1, "Bases of Digital Overpower and Overtemperature Delta-T (OPT/OTT) Reactor Trips," Westinghouse Electric Company LLC. (Methodology for Specification 2.1.1 - Reactor Core Safety Limits, and 3.3.1 - Reactor Trip System (RTD) Instrumentation.)

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Passive Core Cooling Systems limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met. d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

Technical Specifications Reporting Requirements

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Point Unit 7 5.6 - 5

5.6 Reporting

Requirements

5.6.6 Reactor

Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following: 3.4.3, "RCS Pressure and Temperature (P/T) Limits" 3.4.14, "Low Temperature Overpressure Protection (LTOP) System" b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following document: WCAP-14040-A, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves."

(Limits for LCO 3.4.3 and LCO 3.4.14).

c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluency period and for any revision or supplement thereto. 5.6.7 Post Accident Monitoring Report When a report is required by Condition B of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status. 5.6.8 Steam Generator Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE 4 following completion of an inspection performed in accordance with the Specification 5.5.4, "Steam Generator (SG) Program." The report shall include: a. The scope of inspections performed on each SG,

b. Active degradation mechanisms found,

c. Nondestructive examination techniques utilized for each degradation mechanism, d. Location, orientation (if linear), and measured sizes (if available) of service induced indications, Technical Specifications Reporting Requirements

5.6 Turkey

Point Unit 7 5.6 - 6

5.6 Reporting

Requirements

5.6.8 Steam

Generator Tube Inspection Report (continued)

e. Number of tubes plugged during the inspection outage for each active degradation mechanism, f. Total number and percentage of tubes plugged to date,

g. The results of condition monitoring, including the results of tube pulls and in-situ testing, and h. The effective plugging percentage for all plugging in each SG.

Technical Specifications High Radiation Area

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Point Unit 7 5.7 - 1

5.0 ADMINISTRATIVE

CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20: 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment. b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures. c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas. d. Each individual or group entering such an area shall possess: 1. A radiation monitoring device that continuously displays radiation dose rates in the area, or 2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or 3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or

Technical Specifications High Radiation Area

5.7 Turkey

Point Unit 7 5.7 - 2 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Su rface Penetrated by the Radiation (continued) 4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance. e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry. 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition: 1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designees, and 2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

Technical Specifications High Radiation Area

5.7 Turkey

Point Unit 7 5.7 - 3 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued) b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection

equipment and measures. c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such

areas. d. Each individual group entering such an area shall possess: 1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or 2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or 3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, or personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the

area.

Technical Specifications High Radiation Area

5.7 Turkey

Point Unit 7 5.7 - 4 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued) 4. In those cases where options (2) and (3), above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displaces radiation dose rates in the area. e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry. f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

@@ Line 2: / Line 2: @@
 | number = ML17088A314
 | issue date = 04/12/2018
-| title = Turkey Point, Unit 7 COL Appendix a, Tech Specs
+| title = COL Appendix a, Tech Specs
 | author name =
 | author affiliation = NRC/NRO

ML17088A314: Difference between revisions

Revision as of 17:07, 2 April 2019

Text

1.1 Definitions

3.0 LIMITING

3.1 REACTIVITY

3.1.1 SHUTDOWN

3.1.5 Shutdown

3.1.6 Control

3.1.9 Chemical

3.2 POWER

3.3 INSTRUMENTATION

3.3.1 Reactor

3.3.2 Engineered

3.3.4 Remote

3.3.5 Diverse

3.4 REACTOR

3.4 REACTOR

3.5 PASSIVE

3.5.4 Passive

3.6 CONTAINMENT

3.6.1 Containment

3.6.2 Containment

3.6.5 Containment

3.6.6 Passive

3.7 PLANT

3.7 PLANT

3.7.7 Startup

3.8.4 Inverters

3.8.6 Distribution

3.9 REFUELING

3.9.1 Boron

3.9.2 Unborated

3.9.3 Nuclear

3.9.6 Containment

3.9.7 Decay

4.2 Reactor

4.2.2 Control

5.0 ADMINISTRATIVE

5.0 ADMINISTRATIVE

1.1 Turkey

1.1 Definitions

1.1 Turkey

1.1 Definitions

1.1 Turkey

1.1 Definitions

1.1 Turkey

1.1 Definitions

1.1 Turkey

1.1 Definitions

1.1 Turkey

1.1 Definitions

1.1 Turkey

1.2 Turkey

1.2 Turkey

1.2 Logical

1.2 Turkey

1.2 Logical

1.3 Turkey

1.3 Turkey

1.3 Completion

1.3 Turkey

1.3 Completion

1.3 Turkey

1.3 Completion

1.3 Turkey

1.3 Completion

1.3 Turkey

1.3 Completion

1.3 Turkey

1.3 Completion

1.3 Turkey

1.3 Completion

1.3 Turkey

1.3 Completion

1.3 Turkey

1.3 Completion

1.3 Turkey

1.3 Completion

1.4 Turkey