Text

Periodic Update to the Updated Final Safety Analysis Report, Technical Requirements Manual (Trm), Revision 0
	ML24135A083
Person / Time
Site:	Turkey Point
Issue date:	05/09/2024
From:	; Florida Power & Light Co
To:	; Office of Nuclear Reactor Regulation
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ML24135A107	List: L-2024-080, Periodic Update to the Updated Final Safety Analysis Report, Technical Specifications Bases, Revision 0; ML24135A082; ML24135A083; ML24135A084; ML24135A085; ML24135A086; ML24135A087; ML24135A089; ML24135A090; ML24135A091; ML24135A092; ML24135A093; ML24135A094; ML24135A095; ML24135A096; ML24135A097; ML24135A098; ML24135A099; ML24135A100; ML24135A101; ML24135A102; ML24135A103; ML24135A104; ML24135A105; ML24135A106;
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FLORIDA POWER & LIGHT

TURKEY POINT - UNIT 3 and UNIT 4

Technical Requirements Manual (TRM)

Revision 0 PURPOSE

The Technical Requirements Manual (TRM) contains design and licensing basis technical requirements that do not appear in the Technical Specifications (TS).

Chapter 13 of this document includes TE CHNICAL REQUIREMENTS (TRs), TECHNICAL REQUIREMENT SURVEILLANCES (TRSs), and ACTIONS. Instructions for the use and application of the TRs, TRSs, and ACTIONS are included in Section 11.0.

The TRM is a licensee document controlled under 10 CFR 50.59.

The TRM may reference the plant TS. However, the TRM cannot change TS requirements.

Turkey Point Unit 3 and Unit 4 i Revision 0 TABLE OF CONTENTS - TECHNICAL REQUIREMENTS Page

11.0 USE AND APPLICATION 11.1 Definitions ............................................................................................................ 11.1-1 11.2 Logical Connectors .............................................................................................. 11.2-1 11.3 Completion Times ............................................................................................... 11.3-1 11.4 Frequency ........................................................................................................... 11.4 -1

12.0 Not Used

13.0 TECHNICAL REQUIREMENT (TR) APPLICABILITY ............................................... 13.0-1 13.0 TECHNICAL REQUIREMENT SURVEILLANCE (TRS) APPLICABILITY ................ 13.0-2

13.1 REACTIVITY CONTROL SYSTEMS 13.1.1 Boration System - Operating ........................................................................... 13.1.1-1 13.1.2 Boration System - Shutdown ........................................................................... 13.1.2-1 13.1.3 Position Indicator System - Shutdown ............................................................. 13.1.3-1

13.2 POWER DISTRIBUTION LIMITS 13.2.1 Axial Flux Difference (AFD) .............................................................................. 13.2.1-1

13.3 INSTRUMENTATION 13.3.1 Movable Incore Detection System (MIDS) ....................................................... 13.3.1-1 13.3.2 Leading Edge Flow Meter (LEFM) ................................................................... 13.3.2-1 13.3.3 Post Accident Monitoring (PAM) Instrumentation ............................................. 13.3.3-1

13.4 REACTOR COOLANT SYSTEM (RCS) 13.4.1 Reactor Vessel Specimens .............................................................................. 13.4.1-1 13.4.2 Power Operated Relief Valve (PORV) Backup Nitrogen Supply ...................... 13.4.2-1 13.4.3 RCS Pressure Isolation Valve (PIV) Leakage .................................................. 13.4.3-1 13.4.4 RCS Tritium Activity ......................................................................................... 13.4.4-1 13.4.5 Pressurizer ....................................................................................................... 13.4 .5-1 13.4.6 RCS Vents ........................................................................................................ 13.4.6-1

13.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 13.5.1 Containment Debris .......................................................................................... 13.5.1-1

13.6 Not Used

13.7 PLANT SYSTEMS 13.7.1 Standby Feedwater System ............................................................................. 13.7.1-1 13.7.2 Control Room Emergency Ventilation System (CREVS) Filters and Compensatory Filtration System .................................................................. 13.7.2-1 13.7.3 Snubbers .......................................................................................................... 13.7 .3-1 13.7.4 Sealed Source Contamination .......................................................................... 13.7.4-1

Turkey Point Unit 3 and Unit 4 ii Revision 0 TABLE OF CONTENTS - TECHNICAL REQUIREMENTS Page

13.8 ELECTRICAL POWER SYSTEMS 13.8.1 Emergency Diesel Generator (EDG) Fuel Oil .................................................. 13.8.1-1 13.8.2 480 V Load Centers (LCs) and Motor Control Centers (MCCs) - Operating ... 13.8.2-1 13.8.3 Battery Chargers - Parallel Operation ............................................................. 13.8.3-1

13.9 REFUELING OPERATIONS 13.9.1 Communications ............................................................................................... 13.9.1-1 13.9.2 Manipulator Cranes .......................................................................................... 13.9.2-1 13.9.3 Decay Time ...................................................................................................... 13.9.3 -1 13.9.4 Residual Heat Removal (RHR) Flow Indicator ................................................. 13.9.4-1 13.9.5 Spent Fuel Pit Metamic Inserts ........................................................................ 13.9.5-1

13.10 Not Used

13.11 RADIOLOGICAL EFFLUENTS 13.11.1 Explosive Gas ................................................................................................ 13.11.1- 1 13.11.2 Gas Decay Tanks ........................................................................................... 13.11.2-1

14.0 Not Used

15.0 ADMINISTRATIVE CONTROLS 15.1.1 Organization ........................................................................................................ 15 .1-1 15.1.2 Snubber Testing Program ................................................................................... 15.1-2

Turkey Point Unit 3 and Unit 4 iii Revision 0 Definitions 11.1

11.0 USE AND APPLICATION

11.1 Definitions

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

1. Definitions are defined in Section 1.1 of the Technical Specifications (TSs) and are applicable throughout the Technical Requirements Manual (TRM) and Bases. Only definitions specific to the TRM will be defined in this section.

2. The defined terms of this section appear in capitalized type and are applicable throughout the TRM.

3. When a term is defined in both the TS and the TRM, TRM definition takes precedence within the TRM and the TRM Bases.

Term Definition

ACTION / ACTIONS ACTION or ACTIONS shall be that part of a Technical Requirement (TR) that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

FUNCTIONAL/ A system, structure, or component (SSC) is FUNCTIONAL FUNCTIONALITY or has FUNCTIONALITY when it is capable of performing its function(s) as described in the design and licensing basis.

FUNCTIONALITY includes the ability of required support systems to perform their related support function(s) for equipment required to be OPERABLE by the TS.

IMMEDIATELY When IMMEDIATELY is used as a Completion Time, the Required Actions should be pursued without delay and in a controlled manner.

STAGGERED TEST BASIS STAGGERED TEST BASIS shall consist of:

a. A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, and

b. The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.

TECHNICAL REQUIREMENT A TR is a requirement specified or assumed in the design (TR) or licensing basis.

TECHNICAL REQUIREMENT A TRS is a test or verification required by the design SURVEILLANCE (TRS) or licensing basis.

Turkey Point Unit 3 and Unit 4 11.1-1 Revision 0 Logical Connectors 11.2

11.0 USE AND APPLICATION

11.2 Logical Connectors

The guidance provided for the use and application of logical connectors in Section 1.2, "Logical Connectors" of the TSs is also applicable to the logical connectors in TRs, ACTIONS, and TRSs contained in this manual.

Turkey Point Unit 3 and Unit 4 11.2-1 Revision 0 Completion Times 11.3

11.0 USE AND APPLICATION

11.3 Completion Times

The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the discovery of a situation (e.g., TR not met) unless otherwise specified.

Once an ACTION has been entered, subsequent trains, subsystems, components, or variables expressed in the TR, discovered to not be FUNCTIONAL or not within limits, will not result in separate entry into the ACTION, unless specifically stated. The Completion Times are based on initial entry into the ACTION, unless otherwise specified.

Completion Times for Required Actions that state that a structure, system, or component (SSC) must be restored to FUNCTIONAL status have a fixed Completion Time (referred to as the "front stop") and the option to determine a Completion Time based on the licensee-established performance goals required by 10 CFR 50.65(a)(4) (referred to as the "Maintenance Rule backstop"). The front stop Completion Time may always be used. Use of the Maintenance Rule backstop is elective and may be used after the front stop Completion Time is in use or has been exceeded.

Turkey Point Unit 3 and Unit 4 11.3-1 Revision 0 Frequency 11.4

11.0 USE AND APPLICATION

11.4 Frequency

Each TRS has a specified Frequency that must be met while in the MODE or other specified conditions of the Applicability or the corresponding TR is not met. The "specified Frequency" consists of the requirements of the Frequency column of each TRS as modified by TRS 13.0.2, as well as certain Notes in the test column that modify performance requirements.

The use of "met" or "performed" conveys specific meanings. A TRS is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a TRS, even without a TRS specifically being "performed," constitutes a TRS not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.

If the specified Frequency for a TRS is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the associated TRS, it must be performed prior to entry into the MODE or other specified condition or the TRS is considered not met, unless otherwise stated.

Turkey Point Unit 3 and Unit 4 11.4-1 Revision 0 TR Applicability 13.0

13.0 TECHNICAL REQUIREMENT (TR) APPLICABILITY

TR 13.0.1 TRs shall be met during the MODES or other specified conditions in the Applicability, except as provided in TR 13.0.2.

TR 13.0.2 Upon discovery of a failure to meet a TR, the ACTIONS shall be met within the Completion Times, with the exceptions specified below.

a. If the TR is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the ACTION(S) is not required unless otherwise stated.

b. Administrative controls may be employed in lieu of the specified ACTIONS if necessary to perform testing to verify the FUNCTIONALITY of equipment.

TR 13.0.3 When a TR is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTION, initiate a Condition Report in accordance with the Corrective Action Program.

TR 13.0.4 TR Conditions and the associated Required Actions shall apply to each unit individually unless otherwise indicated as follows:

a. Whenever the TR refers to systems or components which are shared by both units, the Conditions and Required Actions will apply to both units simultaneously;

b. Whenever the TR applies to only one unit, this will be identified in the Applicability section of the TR; and

c. Whenever certain portions of a TR contain operating parameters, setpoints, etc., which are different for each unit, this will be identified in parentheses, Notes, or body of the requirement.

Turkey Point Unit 3 and Unit 4 13.0-1 Revision 0 TRS Applicability 13.0

13.0 TECHNICAL REQUIREMENT SURVEILLANCE (TRS) APPLICABILITY

TRS 13.0.1 TRSs shall be met during the MODES or other specified conditions in the Applicability of the associated TR, unless otherwise stated. Failure to meet a TRS, whether such failure is experienced during the performance of the TRS or between performances of the TRS, shall be failure to meet the TR. TRSs do not have to be performed on nonfunctional equipment or variables outside specified limits.

TRS 13.0.2 The specified Frequency for each TRS is met if the TRS 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.

Should a TRS not be performed within the specified Frequency a Condition Report shall be initiated to determine if the associated TR is met. The TRS shall be performed at the next reasonable opportunity.

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.

Turkey Point Unit 3 and Unit 4 13.0-2 Revision 0 TR Applicability 13.0

BASES

TR 13.0.1 TR 13.0.1 establishes the Applicability statement within each individual requirement for when the TR is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of the requirement).

TR 13.0.2 TR 13.0.2 establishes that upon discovery of a failure to meet a TR, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered, unless otherwise specified. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of a TR are not met. Completing the Required Actions is not required when a TR is met or is no longer applicable, unless otherwise stated in the individual requirement.

TR 13.0.2 provides an allowance for following administrative controls instead of the ACTIONS when necessary to allow the performance of required testing to demonstrate either the FUNCTIONALITY of the equipment that is nonfunctional in accordance with the a ssociated TR or the FUNCTIONALITY of other equipment.

TR 13.0.3 TR 13.0.3 establishes the actions that must be implemented when a TR is not met and either:

a. An associated Required Action and Completion Time is not met and no other Condition applies;

b. The condition of the unit is not specifically addressed by the associated ACTIONS; or

A TR may also direct entry into TR 13.0.3.

Under these conditions, as a minimum, a Condition Report must be initiated in accordance with the Corrective Action Program. Initiation of a Condition Report assures that the plant condition will be corrected as required by 10 CFR 50, Appendix B, Criterion XVI, "Corrective Action."

Turkey Point Unit 3 and Unit 4 13.0-3 Revision 0 TR Applicability 13.0

BASES

TR 13.0.4 TR 13.0.4 delineates the applicability of each TR to Unit 3 and Unit 4 operation. TR 13.0.4 states that TRs, including the associated Required Actions, shall apply to each unit individually unless otherwise indicated as follows:

a. Whenever the TR refers to systems or components which are shared by both units, the Required Actions will apply to both units simultaneously;

b. Whenever the TR applies to only one unit, this will be identified in the APPLICABILITY section of the TR; and

c. Whenever certain portions of a TR contain operating parameters, Setpoints, etc., which are different for each unit, this will be identified in parentheses, footnotes or body of the requirement.

Examples of Required Actions applicable to both units simultaneously are found in Section 3.1. There are no examples of a TR applying to only one unit. An example of when certain portions of a TR have operating parameters, etc., which are different for each unit is found in TRM Table 13.8.2-1 and TRM Table 13.8.2-2.

Turkey Point Unit 3 and Unit 4 13.0-4 Revision 0 TRS Applicability 13.0

BASES

TRS 13.0.1 TRS 13.0.1 establishes the requirement that TRSs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the TR apply, unless otherwise specified in the individual TRS. This TRS is to ensure that tests are performed to verify the FUNCTIONALITY of systems and components, and that variables are within specified limits. TRSs may be performed by means of any series of sequential, overlapping, or total steps provided the entire TRS is performed within the specified Frequency.

TRSs do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated TR are not applicable, unless otherwise specified.

TRSs, including TRSs invoked by Required Actions, do not have to be performed on nonfunctional equipment or variable outside their limits because the ACTIONS define the remedial measures that apply. TRSs have to be met and performed in accordance with TRS 13.0.2 prior to returning equipment to FUNCTIONAL status.

TRS 13.0.2 TRS 13.0.2 establishes the requirements for meeting the specified Frequency for TRSs and for any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per ..." interval.

TRS 13.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates scheduling and considers plant operating conditions that may not be suitable for conducting the TRS (e.g.,

transient conditions or other ongoing testing or maintenance activities).

If a TRS is not performed within the specified Frequency, or it is determined that a TRS was not performed within the specified Frequency, a Condition Report shall be initiated to determine if the associated TR is met. The TRS shall be performed at the next reasonable opportunity.

Turkey Point Unit 3 and Unit 4 13.0-5 Revision 0 Boration System - Operating 13.1.1

13.1 REACTIVITY CONTROL SYSTEMS

13.1.1 Boration System - Operating

TR 13.1.1 The following boron injection subsystems capable of injecting into the RCS through the charging pump discharge via the regenerative heat exchanger shall be FUNCTIONAL:

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

Each subsystem shall include a separate FUNCTIONAL charging pump.

a. The source path from a boric acid storage tank (BAST) via a boric acid transfer pump to the charging pump suction, isolated from the other unit from the boric acid transfer pump discharge to the charging pump suction; and

b. At least one of the two source paths from the refueling water storage tank (RWST) to the charging pump suction.

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

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One required boron A.1 Restore required boron 70 hours8.101852e-4 days 0.0194 hours 1.157407e-4 weeks 2.6635e-5 months injection subsystem injection subsystem to nonfunctional. FUNCTIONAL status.

B. Both required boron B.1 Enter TR 13.0.3. IMMEDIATELY injection subsystems nonfunctional.

OR

Required Action and associated Completion Time not met.

Turkey Point Unit 3 and Unit 4 13.1.1-1 Revision 0 Boration System - Operating 13.1.1

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.1.1.1 -----------------------------NOTE-----------------------------

Only applicable when outside air temperature is

< 39 °F or > 100 °F.

Verify RWST solution temperature 39 °F and Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of 100 °F. exceeding outside air temperature limits for 23 consecutive hours

AND

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter

TRS 13.1.1.2 Verify the temperature of the rooms containing 7 days Boration System components is 62 °F.

TRS 13.1.1.3 Verify boron concentration of borated water source 7 days within limit:

a) RWST > 2400 and < 2600 ppm

b) BAST in accordance with TRM Figure 13.1.1-1.

TRS 13.1.1.4 Verify indicated borated water source volume within 7 days limit:

a) RWST 320,000 gallons

b) BAST in accordance with TRM Figure 13.1.1-1.

TRS 13.1.1.5 Verify that each valve (manual, power-operated, or 92 days automatic) in the required flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

Turkey Point Unit 3 and Unit 4 13.1.1-2 Revision 0 Boration System - Operating 13.1.1

TECHNICAL REQUIREMENT SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY

TRS 13.1.1.6 Verify the source path from a BAST via a boric 18 months acid transfer pump to the charging pump suction delivers 16 gpm to the RCS.

TRS 13.1.1.7 Verify the flow path from the charging pump 18 months discharge to the RCS via the regenerative heat exchanger delivers 16 gpm to the RCS.

TRS 13.1.1.8 Perform testing of required charging pumps in In accordance with accordance with the INSERVICE TESTING the INSERVICE PROGRAM. TESTING PROGRAM

Turkey Point Unit 3 and Unit 4 13.1.1-3 Revision 0 Boration System - Operating 13.1.1

TRM FIGURE 13.1.1-1 (page 1 of 1)

Boric Acid Storage Tank Minimum Volume (1)

22000 21450

20000

18500

18000

16400

16000

14800 14075 13450 14000

12600

12000 11550

10750 10075 10000

8000 3.00 3.25 3.50 3.75 4.00 (5245 ppm) (5682 ppm) (6119 ppm) (6556 ppm) (6993 ppm)

BAST INVENTORY CONCENTRATION (WEIGHT %)

Minimum Acceptable One Unit Operation (2)

Minimum Acceptable Two Unit Operation

NOTES:

(1) Combined volume of all available BASTs assuming RWST boron concentration between 2400 ppm and 2600 ppm.

(2) Includes 2900 gallons for the shutdown unit.

Turkey Point Unit 3 and Unit 4 13.1.1-4 Revision 0 Boration System - Operating 13.1.1

SUPPORT FUNCTION

The Boration System is not a required support function for any TS system.

BASES

The Boration System ensures that negative reactivi ty control is available during each MODE of facility operation. The components required to perform this function include: (1) borated water sources, (2) charging pumps, (3) separate flow paths, and (4) boric acid transfer pumps.

With the Reactor Coolant System (RCS) average temperature above 200 °F, a minimum of two boron injection subsystems are required to ensure single functional capability in the event an assumed failure renders one of the flow paths nonfunctional. One flow path from the charging pump discharge is acceptable since the flow path components subject to an active failure are upstream of the charging pumps.

The boration flow path specification allows the refueling water storage tank (RWST) and the Boric Acid Storage Tank (BAST) to be the boron sources. Due to the lower boron concentration in the RWST, borating the RCS from this source is less effective than borating from the BAST.

ACTION B requires TR 13.0.3 entry when both required boration subsystems are nonfunctional.

Entry into TR 13.0.3 will evaluate whether continued operation in MODE 1 with either boration source flow path or the normal flow path to the RCS (via the regenerative heat exchanger) nonfunctional is acceptable. In this case, the plant capability to borate and charge into the RCS is limited and the potential operational impact of this limitation on MODE 1 operation must be addressed.

The boration capability of either flow path is sufficient to provide the required shutdown margin in accordance with the Core Operating Limits Report (COLR) from expected operating conditions after xenon decay and cooldown to 200 °F. The maximum expected boration capability requirement occurs at end of life (EOL) peak xenon conditions without letdown such that boration occurs only during the makeup provided for coolant contraction. This requirement can be met for a range of boric acid concentrations in the BAST and the RWST.

The FUNCTIONALITY requirement of 62 °F and corre sponding surveillance intervals associated with the Boration System ensures that the solubility of the boron solution will be maintained.

The temperature limit of 62 °F includes a 5 °F margin over the 57 °F solubility limit of 4.0 wt.%

boric acid. Portable instrumentation may be used to measure the temperature of the rooms containing boric acid sources and flow paths.

Turkey Point Unit 3 and Unit 4 13.1.1-5 Revision 0 Boration System - Operating 13.1.1

BASES (continued)

The required fluid volume in the BAST is specified as a function of boric acid concentration in weight % as shown in TRM Figure 13.1.1-1. The minimum volumes listed for one unit operation include uncertainty, 2,900 gallons for shutdow n and combined volume of all available BASTs assuming a RWST concentration of 2400 ppm or greater. The minimum volumes listed for two-unit operation include uncertainty, and combined volume of all available BASTs assuming an RWST concentration of 2400 ppm or greater. Any configuration in the acceptable unit(s) operation region from TRM Figure 13.1.1-1 will provide sufficient boric acid delivery to maintain required shutdown margin. The indicated borated water volume can be determined using any one of the FUNCTIONAL BAST level indicators (LI-102, LI-106, or LI-108) provided the BASTs are cross-tied (i.e., 327, 331, 335, 345, 373, 390, and 391 all open).

The RWST boron concentration (2400-2600 ppm) in conjunction with the Recirculation pH Control System (TS 3.6.7) ensures that the Containment Sump pH will be greater than 7.0 following a loss of coolant accident (LOCA). The basic solution minimizes the evolution of iodine and the effect of chloride and caustic stress corrosion on mechanical systems and components. The temperature requirements for the RWST are based on the containment integrity and large break LOCA analysis assumptions.

Two charging pumps are required to be FUNCTIONAL to ensure single functional capability in the event an assumed failure renders one of the pumps or power supplies nonfunctional. Each bus supplying the pumps can be fed from either the Emergency Diesel Generator (EDG) or the offsite grid through a Startup Transformer.

The charging pumps are demonstrated to be FUNCTIONAL by testing as required by the ASME OM code or by specific surveillances in the TRM. These requirements are adequate to determine FUNCTIONALITY because no safety analysis assumption relating to the charging pump performance is more restrictive than these acceptance criteria for the pumps.

Turkey Point Unit 3 and Unit 4 13.1.1-6 Revision 0 Boration System - Shutdown 13.1.2

13.1 REACTIVITY CONTROL SYSTEMS

13.1.2 Boration System - Shutdown

TR 13.1.2 One of the following boron injection subsystems shall be FUNCTIONAL:

a. A flow path from a boric acid storage tank (BAST) via a boric acid transfer pump and a charging pump to the Reactor Coolant System (RCS); or

b. A flow path from a refueling water storage tank (RWST) via a charging pump to the RCS.

APPLICABILITY: MODES 5 and 6.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Required boron A.1 Suspend all operations IMMEDIATELY injection flow path involving positive reactivity nonfunctional. changes.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.1.2.1 -----------------------------NOTE-----------------------------

Only required to be performed when outside air temperature is < 39 °F.

Verify RWST solution temperature 39 °F. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of exceeding outside air temperature is

< 39 °F for 23 consecutive hours

AND

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter

Turkey Point Unit 3 and Unit 4 13.1.2-1 Revision 0 Boration System - Shutdown 13.1.2

TECHNICAL REQUIREMENT SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY

TRS 13.1.2.2 Verify the temperature of the rooms containing 7 days boron injection flow path components is 62 °F.

TRS 13.1.2.3 Verify boron concentration of required borated 7 days water source within limit:

a) RWST > 2400 and < 2600 ppm

b) BAST > 3.0 wt% (5245 ppm) and < 4.0 wt%

(6993 ppm).

TRS 13.1.2.4 Verify indicated volume of required borated water 7 days source within limit:

a) RWST 20,000 gallons

b) BAST 2,900 gallons per unit.

TRS 13.1.2.5 Verify that each valve (manual, power-operated, or 92 days automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

Turkey Point Unit 3 and Unit 4 13.1.2-2 Revision 0 Boration System - Shutdown 13.1.2

SUPPORT FUNCTION

The Boration System is not a required support function for any TS system.

BASES

The boron capability required below 200 °F is sufficient to provide a shutdown margin of 1.77% k/k after xenon decay and cooldown from 200 °F to 140 °F. This condition requires either 2,900 gallons of at least 3.0 wt% (5245 ppm) borated water per unit from the boric acid storage tanks (BASTs) or 20,000 gallons of between 2400 and 2600 ppm borated water from the refueling water storage tank (RWST).

With the Reactor Coolant System (RCS) temperature below 200 °F, one boron injection flow path is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restriction prohibiting positive reactivity changes in the event the single boron injection system source flow path becomes nonfunctional.

During MODES 5 and 6, charging pump TRSs specified for the boration flow paths in TRM 13.1.1 are not required to be met (reference AR 1755509 Condition Evaluation). The TRSs for charging pumps are contained in TRM 13.1.1, which applies in MODES 1, 2, 3, and 4 only.

The FUNCTIONALITY of one boron injection flow path during refueling ensures that this system is available for reactivity control while in MODE 6.

Turkey Point Unit 3 and Unit 4 13.1.2-3 Revision 0 Position Indicator System - Shutdown 13.1.3

13.1 REACTIVITY CONTROL SYSTEMS

13.1.3 Position Indicator System - Shutdown

TR 13.1.3 The group step counter demand pos ition indicator shall be FUNCTIONAL and capable of determining within +/- 2 steps the demand position for each shutdown and control rod not fully inserted.

APPLICABILITY: MODES 3, 4, and 5, with the Reactor Trip System (RTS) breakers in the closed position.

ACTION

CONDITION REQUIRED ACTION COMPLETION TIME

A. Group step counter A.1 Enter TR 13.0.3. IMMEDIATELY demand position indicator nonfunctional.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.1.3.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

TRS 13.1.3.2 Verify movement of associated control rods at least 31 days 10 steps in any one direction.

TRS 13.1.3.3 Perform COT. 18 months

Turkey Point Unit 3 and Unit 4 13.1.3-1 Revision 0 Position Indicator System - Shutdown 13.1.3

SUPPORT FUNCTION

The group step counter demand position indicator is not a required support function for any TS system in MODE 3, 4, or 5.

BASES

None.

Turkey Point Unit 3 and Unit 4 13.1.3-2 Revision 0 Target Flux Difference 13.2.1

13.2 POWER DISTRIBUTION LIMITS

13.2.1 Target Flux Difference

TR 13.2.1 The target flux difference shall be monitored.

APPLICABILITY: MODE 1, 50% of RATED THERMAL POWER.

ACTION

CONDITION REQUIRED ACTION COMPLETION TIME

A. TRS 13.2.1.1 or A.1 Enter TR 13.0.3. IMMEDIATELY TRS 13.2.1.2 not performed within required Frequency.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.2.1.1 Update the target flux difference: 31 EFPD

a. By performance of TRS 13.2.1.2

OR

b. By linear interpolation between the most recently measured value and the predicted value at the end of the cycle life.

TRS 13.2.1.2 Determine the target flux difference for each 92 EFPD OPERABLE excore channel.

Turkey Point Unit 3 and Unit 4 13.2.1-1 Revision 0 Target Flux Difference 13.2.1

SUPPORT FUNCTION

Monitoring of the target flux difference supports TS 3.2.3.

BASES

Target flux difference is determined at equilibrium xenon conditions. The full-length rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady-state operation at high power levels. The value of the target flux difference obtained under these conditions divided by the fraction of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup conditions. Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER value by the appropriate fractional THERMAL POWER level. The periodic updating of the target flux difference value is necessary to reflect core burnup considerations.

Turkey Point Unit 3 and Unit 4 13.2.1-2 Revision 0 MIDS 13.3.1

13.3 INSTRUMENTATION

13.3.1 Movable Incore Detection System (MIDS)

TR 13.3.1 The MIDS shall be FUNCTIONAL with:

a. A minimum of two detector thimbles per quadrant, and

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

1. Applicable when MIDS used for recalibration and check of the Excore Neutron Flux Detection System.

2. Applicable when MIDS used for monitoring QUADRANT POWER TILT RATIO.

3. The 16-detector thimble requirement may be excepted for monitoring QUADRANT POWER TILT RATIO during performance of Technical Specification Surveillance Requirement 3.2.4.2 using two sets of four symmetric thimbles.

b. At least 16 detector thimbles, and

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

Applicable when MIDS used to monitor F N , FQ(Z), and Fxy(Z).

c. At least 38 de

APPLICABILITY: for:

a. n

b. Monitoring QUADRANT POWER TIor

c. Measurement of F , F H Q (Z), and F (Z).

ACTION

CONDITION REQUIRED ACTION COMPLETION TIME

A. MIDS nonfunctional. A.1 Suspend use of MIDS for IMMEDIATELY applicable monitoring or calibration functions.

Turkey Point Unit 3 and Unit 4 13.3.1-1 Revision 0 MIDS 13.3.1

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.3.1.1 Normalize each detector output. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Turkey Point Unit 3 and Unit 4 13.3.1-2 Revision 0 MIDS 13.3.1

SUPPORT FUNCTION

The MIDS is used to measure core power distribution in accordance with the Technical Specification (TS) Section 3.2. The MIDS is also used to calibrate the Excore Neutron Flux Detection System in accordance with TS 3.3.1.

BASES

The FUNCTIONALITY of the movable incore detecto rs with the specified minimum complement of equipment ensures that the measurements obt ained from use of this system accurately represent the spatial neutron flux distribution of the core. The FUNCTIONALITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve. Sufficient movable detectors, drive, and readout equipment must be FUNCTIONAL to map required thimbles.

For the purpose of measuring F Q(Z) or F N a full incore flux map is used. Quarter-core flux H maps, as defined in WCAP-8648, June 1976 or in the Westinghouse Single Point Calibration Technique, may be used in recalibration of the Excore Neutron Flux Detection System, and full incore flux maps or symmetric incore thim bles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.

Turkey Point Unit 3 and Unit 4 13.3.1-3 Revision 0 LEFM 13.3.2

13.3 INSTRUMENTATION

13.3.2 Leading Edge Flow Meter (LEFM)

TR 13.3.2 The minimum number of LEFM channels shown in TRM Table 13.3.2-1 shall be FUNCTIONAL.

APPLICABILITY: MODE 1.

ACTIONS

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

Separate Condition entry is allowed for each LEFM channel.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more required A.1.1 Verify venturi corrected IMMEDIATELY channels nonfunctional. value is selected.

AND

A.1.2 Restore required 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months channel(s) to FUNCTIONAL status.

OR

A.2 Reduce power in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months accordance with TRM Table 13.3.2-2.

B. One or more required B.1 Initiate action to limit IMMEDIATELY channels nonfunctional. RATED THERMAL POWER to 2599 MWt.

AND

Power change > 2%.

TECHNICAL REQUIREMENT SURVEILLANCES

None

Turkey Point Unit 3 and Unit 4 13.3.2-1 Revision 0 LEFM 13.3.2

TABLE 13.3.2-1 (Page 1 of 1)

LEFM Calorimetric Instrumentation

Minimum Channels Function Total No. of Channels FUNCTIONAL

LEFM CPU 2 1 LEFM Meter Section (Path 1-4, 5-8) 6 6

Calorimetric portion of DCS 1 1

Turkey Point Unit 3 and Unit 4 13.3.2-2 Revision 0 LEFM 13.3.2

TABLE 13.3.2-2 (Page 1 of 1)

Reduced Power Limits Applicable to Nonfunctional LEFM Calorimetric Instrumentation

Selected Maximum Maximum Total Power Calorimetric RTP Power Uncertainty Mode of Description of Nonfunctional LEFM (MWt) (%) (%) Operation Calorimetric Instrument

One meter section (plane) in any 2638.7 99.8 0.50 LEFM LEFM in "Check Mode" (Level 2 LEFM System Status)

Any LEFM meter in "Fail Mode" (Level 3 LEFM System Status) or 2599.0 98.3 2.0 Venturi loss of communication with both LEFM central processing units (CPUs).

2599.0 98.3 2.0 ------ Calorimetric portion of distributed control system (DCS) nonfunctional.

Turkey Point Unit 3 and Unit 4 13.3.2-3 Revision 0 LEFM 13.3.2

SUPPORT FUNCTION

The LEFM calorimetric instrumentation supports the calorimetric heat balance calculation of TS SR 3.3.1.2.

BASES

See UFSAR Section 7.9.1.

Turkey Point Unit 3 and Unit 4 13.3.2-4 Revision 0 PAM Instrumentation 13.3.3

13.3 INSTRUMENTATION

13.3.3 Post Accident Monitoring (PAM) Instrumentation

TR 13.3.3 The PAM instrumentation shown in TRM Table 13.3.3-1 shall be FUNCTIONAL.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME

A. ------------NOTE----------- A.1 Restore at least one 30 days Only applicable to channel to FUNCTIONAL Function 6. status.

One or more channels nonfunctional.

B. ------------NOTE----------- B.1 Restore channel to 30 days Only applicable to FUNCTIONAL status.

Functions 1 and 2.

One or more Functions with one channel nonfunctional.

Turkey Point Unit 3 and Unit 4 13.3.3-1 Revision 0 PAM Instrumentation 13.3.3

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

C. ------------NOTE----------- C.1 Restore at least one 7 days Only applicable to channel of associated Functions 1 and 2. Function to FUNCTIONAL

status.

One or more Functions with two channels nonfunctional.

OR

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

Only applicable to Function 5.

Required channel nonfunctional.

D. ------------NOTE----------- D.1 Close and de-energize IMMEDIATELY Only applicable to associated power operated Functions 3 and 4. relief valve (PORV) block

valve.

One or more Functions with required channel nonfunctional.

E. Required Action and E.1 Enter TR 13.0.3. IMMEDIATELY associated Completion Time not met.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.3.3.1 Perform CHANNEL CHECK. 31 days

TRS 13.3.3.2 Perform CHANNEL CALIBRATION. 18 months

Turkey Point Unit 3 and Unit 4 13.3.3-2 Revision 0 PAM Instrumentation 13.3.3

TRM TABLE 13.3.3-1 (page 1 of 1)

PAM Instrumentation

FUNCTION REQUIRED CHANNELS

1. Auxiliary Feedwater Flow Rate 2/steam generator

2. Reactor Coolant System Subcooling Margin Monitor 2

3. PORV Position Indicator (Primary Detector) 1/valve

4. PORV Block Valve Position Indicator 1/valve

5. Safety Valve Position Indicator (Primary Detector) 1/valve

6. Containment Water Level (Narrow Range) 2

Turkey Point Unit 3 and Unit 4 13.3.3-3 Revision 0 PAM Instrumentation 13.3.3

SUPPORT FUNCTION

The PAM instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident.

BASES

The FUNCTIONALITY of the PAM instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide (RG) 1.97, Revision 3, "Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," May 1983 and NUREG-0737, "Clarification of TMI Action Plan Requirements," November 1980. Note that RG 1.97 Category 1 and Type A instruments are required to be included in the Technical Specifications. This TR contains other RG 1.97 instruments.

An ACTIONS Note states that separate Condition entry is allowed for each instrument. This Note has been added for clarification. The ACTIONS may be entered independently for each instrument listed on TRM Table 13.3.3-1. Completion Times of the nonfunctional channels will be tracked separately for each instrument starting from the time the ACTION was entered for that instrument. When the Required Channels in TRM Table 13.3.3-1 are specified on a per Steam Generator (SG) basis, then the Condition may be entered separately for each SG, as appropriate.

Function 2, "Reactor Coolant System Subcooling Margin Monitor," receives inputs from the following Technical Specification PAM instruments: 1) wide range reactor coolant outlet temperature THOT, 2) wide range reactor coolant inlet temperature T COLD, 3) wide range reactor coolant pressure, and 4) the core exit thermocouples.

Turkey Point Unit 3 and Unit 4 13.3.3-4 Revision 0 Reactor Vessel Specimens 13.4.1

13.4 REACTOR COOLANT SYSTEM (RCS)

13.4.1 Reactor Vessel Specimens

TR 13.4.1 The reactor vessel material irradiation surveillance specimens shall be used to determine changes in reactor vessel material properties.

APPLICABILITY: At all times.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Reactor vessel A.1 Enter TR 13.0.3. IMMEDIATELY specimen not available when required to assess vessel material properties.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.4.1.1 Remove and examine required reactor vessel In accordance with specimens and determine changes in reactor vessel the 10 CFR 50, materials properties. Appendix H

Turkey Point Unit 3 and Unit 4 13.4.1-1 Revision 0 Reactor Vessel Specimens 13.4.1

SUPPORT FUNCTION

The reactor vessel specimens are not required support functions for any TS system.

BASES

The actual shifts in the reference temperature for nil ductility transition (RT NDT) of the vessel materials will be established periodically during operation by removing and evaluating, in accordance with the version of the ASTM E185 standard required by 10 CFR 50, Appendix H, reactor vessel material irradiation surveillance specimens installed near the inside wall of the reactor vessel in the core area. Since the neutron spectra at the irradiation samples and vessel inside radius are essentially identical, the measured transition shift for a sample can be applied with confidence to the adjacent section of the reactor vessel. The results of the examinations shall be used to update Technical Specification Figures 3.4-2 and 3.4-3.

Turkey Point Unit 3 and Unit 4 13.4.1-2 Revision 0 PORV Backup Nitrogen Supply 13.4.2

13.4 REACTOR COOLANT SYSTEM (RCS)

13.4.2 Power Operated Relief Valve (PORV) Backup Nitrogen Supply

TR 13.4.2 The PORV backup nitrogen supply shall be FUNCTIONAL.

APPLICABILITY: MODES 4, 5 and 6 when PORV is relied upon in accordance with LCO 3.4.12.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more required A.1 Enter TR 13.0.3. IMMEDIATELY PORV backup nitrogen supply nonfunctional.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.4.2.1 Verify PORV backup nitrogen supply. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

Turkey Point Unit 3 and Unit 4 13.4.2-1 Revision 0 PORV Backup Nitrogen Supply 13.4.2

SUPPORT FUNCTION

The PORV backup nitrogen supply can be used to support the Overpressure Mitigating Systems (OMS) of TS 3.4.12.

BASES

Verifying the FUNCTIONALITY of the backup nitr ogen supply is provided in the proposed license amendment correspondence L-2000-146 and in the NRC Safety Evaluation Report provided in the associated Technical Specification Amendments 208/202 effective October 30, 2000.

Turkey Point Unit 3 and Unit 4 13.4.2-2 Revision 0 RCS Leakage Monitoring 13.4.3

13.4 REACTOR COOLANT SYSTEM (RCS)

13.4.3 RCS Pressure Isolation Valve (PIV) Leakage

TR 13.4.3 RCS PIV leakage shall be monitor ed when leakage limit of TS SR 3.4.14.1 is exceeded.

APPLICABILITY: MODES 1, 2, 3, MODE 4, except valves in the residual heat removal (RHR) flow path when in, or during the transition to or from, the RHR mode of operation.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. RCS PIV leakage not A.1 Enter TR 13.0.3. IMMEDIATELY monitored.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.4.3.1 -----------------------------NOTE-----------------------------

Not required to be performed to manual valves located inside containment.

Verify the position of valves located in high 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months pressure lines having an RCS PIV exceeding the limits of LCO 3.4.14.

TRS 13.4.3.2 Determine and record PIV leakage of RCS PIVs 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that exceed the leakage limits of LCO 3.4.14.

Turkey Point Unit 3 and Unit 4 13.4.3-1 Revision 0 RCS Leakage Monitoring 13.4.3

SUPPORT FUNCTION

Monitoring PIV leakage supports TS 3.4.14.

BASES

The RCS leakage detection instrumentation is provided to monitor and detect leakage from the reactor coolant pressure boundary to the containment. In addition, gross leakage will be detected by changes in makeup water requirements, visual inspection, and audible detection.

Leakage to other systems will be detected by activity changes (e.g., within the component cooling system) or water inventory changes (e.g., tank levels).

The inability to verify valve positions in high pressure lines having an RCS pressure isolation valve (PIV) which exceeds the leakage limits of LCO 3.4.14 or the inability to determine and record leakage in high pressure lines having an RCS pressure isolation valve which exceeds the leakage limits of LCO 3.4.14 may impact compliance with LCO 3.4.14.

Turkey Point Unit 3 and Unit 4 13.4.3-2 Revision 0 RCS Activity 13.4.4

13.4 REACTOR COOLANT SYSTEM (RCS)

13.4.4 RCS Activity

TR 13.4.4 RCS tritium activity shall be determined.

AND

RCS radiochemical isotopic analysis shall be performed.

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

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. RCS tritium activity not A.1 Enter TR 13.0.3. IMMEDIATELY determined.

OR

RCS radiochemical isotopic analysis including gaseous activity not performed.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.4.4.1 Determine the tritium activity of the RCS. 7 days

TRS 13.4.4.2 Perform a radiochemical isotopic determination 31 days including gaseous activity.

Turkey Point Unit 3 and Unit 4 13.4.4-1 Revision 0 RCS Activity 13.4.4

SUPPORT FUNCTION

The RCS radiochemical isotopic determination including gaseous activity and RCS tritium activity are not a required support function for any TS system.

BASES

A gamma isotopic analysis as a measure of noble gas specific activity of the reactor coolant is performed every 31 days. This measurement is the sum of the degassed gamma activities and the gaseous gamma activities in the sample taken. This surveillance provides an indication of any increase in the noble gas specific activity.

Turkey Point Unit 3 and Unit 4 13.4.4-2 Revision 0 Pressurizer 13.4.5

13.4 REACTOR COOLANT SYSTEM (RCS)

13.4.5 Pressurizer

TR 13.4.5 The pressurizer temperature shall be limited to:

a. A maximum heatup of 100 °F in any 1-hour period,

b. A maximum cooldown of 200 °F in any 1-hour period, and

c. A maximum spray water temperature differential of 320 °F.

APPLICABILITY: At all times.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Pressurizer A.1 Initiate action to perform an IMMEDIATELY temperature not within engineering evaluation to limits. determine effects of the out-of-limit condition on the structural integrity of the pressurizer to verify the pressurizer remains acceptable for continued operation.

AND

A.2 Restore pressurizer 30 minutes temperature to within limits.

B. Required Action and B.1 Enter TR 13.0.3. IMMEDIATELY associated Completion Time not met.

Turkey Point Unit 3 and Unit 4 13.4.5-1 Revision 0 Pressurizer 13.4.5

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.4.5.1 -------------------------------NOTE------------------------------

Only required to be performed during RCS heatup and cooldown.

Verify pressurizer temperature within limits. 30 minutes

TRS 13.4.5.2 -------------------------------NOTE------------------------------

Only required to be performed during pressurizer auxiliary spray operation.

Verify pressurizer auxiliary spray water temperature 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months differential within limit.

Turkey Point Unit 3 and Unit 4 13.4.5-2 Revision 0 Pressurizer 13.4.5

SUPPORT FUNCTION

The pressurizer supports RCS TS requirements.

BASES

The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pressurizer is operated within the design criteria assumed for the fatigue analysis performed in accordance with the ASME Code requirements.

The Pressurizer heatup and cooldown rates shall not exceed 100 °F/h and 200 °F/h, respectively. The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 320 °F.

Turkey Point Unit 3 and Unit 4 13.4.5-3 Revision 0 RCS Vents 13.4.6

13.4 REACTOR COOLANT SYSTEM (RCS)

13.4.6 RCS Vents

TR 13.4.6 Two RCS vent valves in series in each of the following flow paths shall be FUNCTIONAL:

a. Reactor vessel head, and

b. Pressurizer steam space.

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

ACTIONS

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

Separate Condition entry is allowed for each required RCS vent valve.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One RCS vent path A.1 Initiate action to IMMEDIATELY nonfunctional. de-energize RCS vent valves in the nonfunctional flow path in closed position.

AND

A.2 Restore nonfunctional RCS 30 days flow path to FUNCTIONAL status.

B. Both RCS vent paths B.1 Initiate action to IMMEDIATELY nonfunctional. de-energize RCS vent valves in the nonfunctional flow path in closed position.

AND

B.2 Restore at least one 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months nonfunctional vent path to FUNCTIONAL status.

Turkey Point Unit 3 and Unit 4 13.4.6-1 Revision 0 RCS Vents 13.4.6

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

C. Required Action and C.1 Enter TR 13.0.3. IMMEDIATELY associated Completion Time of Condition A or B not met.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.4.6.1 Cycle each required RCS vent valve through one In accordance with complete cycle of full travel. the INSERVICE TESTING PROGRAM

TRS 13.4.6.2 Verify flow through the required RCS vent paths. 18 months

TRS 13.4.6.3 Verify manual valves in each RCS vent path are 18 months locked in the open position.

Turkey Point Unit 3 and Unit 4 13.4.6-2 Revision 0 RCS Vents 13.4.6

SUPPORT FUNCTION

The RCS vents support RCS TS requirements.

BASES

RCS vents are provided to exhaust non-condensable gases and/or steam from the RCS that could inhibit natural circulation core cooling. The FUNCTIONALITY of at least one RCS vent path from the reactor vessel head and the pressurizer steam space ensures that the capability exists to perform this function. The valve redundancy of the RCS vent paths serves to minimize the probability of inadvertent or irreversible actuation while ensuring that a single failure of a vent valve, power supply, or control system does not prevent isolation of the vent path.

Due to Appendix R considerations, the fuses for the Reactor Vessel Head Vent System solenoid valves are removed to prevent inadvertent openi ng of a leak path from the primary system during a fire (Reference JPN-PTN-SEEJ-89-0076, Revision 1). The Reactor Vessel Head Vent System solenoid valves are considered FUNCTIO NAL with the fuses pulled since the removal and the administrative control of these fuses is controlled by plant procedures. The performances of the specified surveillances will verify the FUNCTIONALITY of the system.

The function, capabilities, and testing requirements of the RCS vents are consistent with the requirements of Item II.B.1 of NUREG-0737, "Clarification of TMI Action Plan."

Turkey Point Unit 3 and Unit 4 13.4.6-3 Revision 0 Containment Debris 13.5.1

13.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

13.5.1 Containment Debris

TR 13.5.1 Containment debris shall be controlled.

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

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Containment debris A.1 Remove identified debris. IMMEDIATELY identified that could cause restriction to pump suctions during loss of coolant accident (LOCA) conditions.

B. Required Action and B.1 Initiate action to verify IMMEDIATELY associated Completion identified debris is within Time not met. analyzed limits by performance of an engineering evaluation.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.5.1.1 -------------------------------NOTE------------------------------

Only required for areas accessed during containment entries.

Perform a visual inspection of the containment for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months loose debris that could be transported to the containment sump and cause restriction to pump AND suctions during LOCA conditions.

During final containment entry

Turkey Point Unit 3 and Unit 4 13.5.1-1 Revision 0 Containment Debris 13.5.1

TECHNICAL REQUIREMENT SURVEILLANCES (continued)

SURVEILLANCE FREQUENCY

TRS 13.5.1.2 Perform a visual inspection of the containment for 18 months loose debris that could be transported to the containment sump and cause restriction to pump suctions during LOCA conditions.

Turkey Point Unit 3 and Unit 4 13.5.1-2 Revision 0 Containment Debris 13.5.1

SUPPORT FUNCTION

The control of containment debris supports Em ergency Core Cooling System and Containment Spray System TS requirements.

BASES

None.

Turkey Point Unit 3 and Unit 4 13.5.1-3 Revision 0 Standby Feedwater System 13.7.1

13.7 PLANT SYSTEMS

13.7.1 Standby Feedwater System

TR 13.7.1 The Standby Feedwater System shall be FUNCTIONAL with:

a. Two Standby Feedwater System pumps, and

b. A Demineralized Water Storage Tank containing 145,000 gallons of water.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Standby Feedwater A.1 Restore Standby 30 days System pump Feedwater System pump to nonfunctional. FUNCTIONAL status.

B. Both Standby B.1 Restore at least one 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Feedwater System Standby Feedwater pumps nonfunctional. System pump to FUNCTIONAL status.

C. Demineralized Water C.1 Restore Demineralized 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Storage Tank volume Water Storage Tank not within limits. volume to within limits.

D. Required Action and D.1 Enter TR 13.0.3. IMMEDIATELY associated Completion Time of Condition A, B, or C not met.

Turkey Point Unit 3 and Unit 4 13.7.1-1 Revision 0 Standby Feedwater System 13.7.1

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.7.1.1 Verify Demineralized Water Storage Tank volume 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 145,000 gallons.

TRS 13.7.1.2 Start each Standby Feedwater System pump in 31 days on a the recirculation mode of operation. STAGGERED TEST BASIS

TRS 13.7.1.3 Verify proper alignment of the Standby Feedwater 18 months System flow paths by starting each pump and verifying flow from the Demineralized Water Storage Tank to the Steam Generators.

TRS 13.7.1.4 Perform inspection of the diesel engine for the 18 months diesel-driven Standby Feedwater System pump.

Turkey Point Unit 3 and Unit 4 13.7.1-2 Revision 0 Standby Feedwater System 13.7.1

SUPPORT FUNCTION

The Standby Feedwater System is not a required support function for any TS system.

BASES

The Standby Feedwater System consists of commercial grade components designed and constructed to industry and FPL standards of this class of equipment located in the outdoor plant environment typical of FPL facilities system wide. The system is expected to perform with high reliability, i.e., comparable to that typically achieved with this class of equipment. FPL intends to maintain the system in good operating condition with regard to structures, supports, component maintenance, calibrations, etc.

The function of the Standby Feedwater System for F UNCTIONALITY determinations is that it can be used as a backup to the Auxiliary Feedwater (AFW) System in the event the AFW System does not function properly. The Standby Feedwater System would be manually started, aligned, and controlled by the operator when needed. The A pump is electric-driven and is powered from the non-safety related C bus. Emergency power is not required for the pump and flow path components. In the event of a coincident loss of offsite power, the B pump is diesel driven and can be started and operated independent of the availability of on-site or off-site power.

A supply of 77,000 gallons from the non-safety grade Demineralized Water Storage Tank for the Standby Feedwater System pumps is sufficient to remove decay heat from the reactor for six (6) hours for a single unit or two (2) hours for two units. This was the basis used for requiring 77,000 gallons of water in the non-safety grade Demineralized Water Storage Tank and is judged to provide sufficient time for restoring the AFW System or establishing make-up to the Demineralized Water Storage Tank.

The minimum indicated volume (145,000 gallons) consists of an allowance for level indication instrument uncertainties (approximately 15,000 gallons) for water deemed unusable because of tank discharge line location and vortex formation (approximately 50,200 gallons) and the minimum usable volume (77,000 gallons). The minimum indicated volume corresponds to a water level of 9.2 feet in the Demineralized Water Storage Tank. Adequate demineralized water for the Standby Feedwater System is verified in accordance with the surveillance requirements.

The Demineralized Water Storage Tank provides a source of water to several systems and, therefore, requires daily verification.

The Standby Feedwater System pumps are not designed to NRC requirements applicable to the AFW System and is not required to satisfy Design Basis Event requirements.

The Standby Feedwater System pumps are verified FUNCTIONAL by starting and operating the pumps in the recirculation mode. Also, eac h Standby Feedwater System pump is started and aligned to provide flow to the nuclear units steam generators (SGs).

Turkey Point Unit 3 and Unit 4 13.7.1-3 Revision 0 Standby Feedwater System 13.7.1

BASES (continued)

This surveillance regimen demonstrates FUNCTIO NALITY of the entire flow path, backup non-safety grade power supply and pump associated with a unit at least each refueling outage.

The pump, motor driver, and normal power supply av ailability would typically be demonstrated by operation of the pumps in the recirculation mode monthly on a staggered test basis.

The diesel engine driver for the B Standby Feedwater System pump is periodically verified to be FUNCTIONAL. In addition, an inspection is performed on the diesel in accordance with procedures prepared in conjunction with its manufacturers recommendations for the diesels class of service. This inspection ensures that the diesel driven pump is maintained in good operating condition consistent with FPL's overall objectives for system reliability.

Turkey Point Unit 3 and Unit 4 13.7.1-4 Revision 0 CREVS Charcoal Filter and Compensatory Filtration Unit 13.7.2

13.7 PLANT SYSTEMS

13.7.2 Control Room Emergency Ventilation System (CREVS) Charcoal Filter and Compensatory Filtration Unit

TR 13.7.2 The CREVS compensatory filtration unit shall be FUNCTIONAL

AND

The laboratory analysis of the CREVS charcoal filter and the compensatory filtration unit charcoal filter shall be completed in accordance with TRS 13.7.2.1.

APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6 During movement of irradiated fuel assemblies.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Laboratory analysis of A.1 Enter TR 13.0.3. IMMEDIATELY CREVS charcoal filter not completed in accordance with TRS 13.7.2.1.

OR

Laboratory analysis of CREVS compensatory filtration unit charcoal filter not completed in accordance with TRS 13.7.2.1.

OR

CREVS compensatory filtration unit nonfunctional.

Turkey Point Unit 3 and Unit 4 13.7.2-1 Revision 0 CREVS Charcoal Filter and Compensatory Filtration Unit 13.7.2

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.7.2.1 Complete laboratory analysis of representative Once within 31 days carbon sample of the CREVS charcoal filter and after removal of a the compensatory filtration unit charcoal filter in representative accordance with the Ventilation Filter Testing carbon sample Program (VFTP).

TRS 13.7.2.2 Manually initiate flow for 15 minutes through the 92 days CREVS compensatory filtration unit.

TRS 13.7.2.3 Perform filter testing of the CREVS compensatory In accordance with filtration unit in accordance with the VFTP. the VFTP

TRS 13.7.2.4 Measure the control room envelope (CRE) In accordance with pressure relative to external areas adjacent to the the Control Room CRE boundary with the CREVS compensatory Envelope filtration unit in service in accordance with the Habitability Program Control Room Envelope Habitability Program.

TRS 13.7.2.5 Perform required CRE unfiltered air inleakage testing In accordance with with the CREVS compensatory filtration unit in service the Control Room in accordance with the Control Room Envelope Envelope Habitability Program. Habitability Program

Turkey Point Unit 3 and Unit 4 13.7.2-2 Revision 0 CREVS Charcoal Filter and Compensatory Filtration Unit 13.7.2

SUPPORT FUNCTION

The CREVS filters and compensatory filtration unit support TS 3.7.10.

BASES

The compensatory filtration unit is designed as a manual, safety-related, Seismic Class I backup to the installed system with the same functional and operational capabilities as the installed filter train. In addition, the unit is surveillance tested in accordance with the same requirements as those imposed on the installed filter.

Filter testing is performed in accordance with the VFTP. Regarding exposure of the filters to effluents that may have an adverse effect on the functional capability of the system, painting, fire, or chemical releases are considered "NOT communicating" with the HEPA filter or adsorber if the system is NOT in operation.

Turkey Point Unit 3 and Unit 4 13.7.2-3 Revision 0 Snubbers 13.7.3

13.7 PLANT SYSTEMS

13.7.3 Snubbers

TR 13.7.3 Snubbers affecting Technical Specification required safety-related systems shall be FUNCTIONAL.

APPLICABILITY: MODES 1, 2, 3, and 4, MODES 5 and 6 for snubbers located on systems required OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each snubber.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more required A.1 Restore snubber to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months snubbers nonfunctional FUNCTIONAL status.

affecting only one associated train or OR subsystem of a multiple train or subsystem A.2 Replace snubber with a 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months supported system. FUNCTIONAL snubber.

OR OR

One or more required A.3 Declare the supported 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months snubbers nonfunctional required feature(s) associated with a single inoperable.

train or subsystem supported system.

Turkey Point Unit 3 and Unit 4 13.7.3-1 Revision 0 Snubbers 13.7.3

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

B. One or more required B.1 Restore snubber to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months snubbers nonfunctional FUNCTIONAL status.

affecting more than one train or subsystem of a OR multiple train or subsystem supported B.2 Replace snubber with a 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system. FUNCTIONAL snubber.

OR

B.3 Declare the supported 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months required feature(s) inoperable.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.7.3.1 Perform testing of required snubbers in In accordance with accordance with the Snubber Testing Program. the Snubber Testing Program

Turkey Point Unit 3 and Unit 4 13.7.3-2 Revision 0 Snubbers 13.7.3

SUPPORT FUNCTION

Snubbers support various TS-required structures, systems, and components.

BASES

All snubbers are required FUNCTIONAL to ensure that the structural integrity of the Reactor Coolant System and all other Technical Specification required safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. The only snubbers excluded from the requirements are thos e installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any Technical Specification required safety-related system. Snubbers are demonstrated FUNCTIONAL in accordance with the Snubber Testing Program.

Turkey Point Unit 3 and Unit 4 13.7.3-3 Revision 0 Sealed Source Contamination 13.7.4

13.7 PLANT SYSTEMS

13.7.4 Sealed Source Contamination

TR 13.7.4 Each sealed source containing radioactive material either in excess of 100 µCuries of beta and/or gamma emitting material or 5 µCuries of alpha emitting material shall be free of 0.005 µCurie of removable contamination.

AND

A complete inventory of licensed radioactive materials in possession shall be maintained current.

APPLICABILITY: At all times.

ACTIONS

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

Separate Condition entry is allowed for each sealed source.

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more sealed A.1 Withdraw the seal source IMMEDIATELY source with removable from use.

contamination not within limits. AND

A.2.1 Initiate action to IMMEDIATELY decontaminate and repair the affected sealed source.

OR

A.2.2 Initiate action to dispose of IMMEDIATELY the sealed source in accordance with Commission Regulations.

B. Required Action and B.1 Enter TR 13.0.3. IMMEDIATELY associated Completion Time not met.

Turkey Point Unit 3 and Unit 4 13.7.4-1 Revision 0 Sealed Source Contamination 13.7.4

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.7.4.1 -------------------------------NOTE------------------------------

Not required to be performed for startup sources and fission detectors previously subjected to core flux or installed in the core.

Test each sealed source in use with a half-life 184 days

> 30 days (excluding Hydrogen 3) and in any form other than gas for leakage and/or contamination.

TRS 13.7.4.2 Test each stored sealed source and fission Prior to use if not detector not in use for leakage and/or performed within contamination. previous 184 days

AND

Prior to transfer if not performed within previous 184 days

AND

184 days

TRS 13.7.4.3 Test each stored sealed source and fission Prior to use detector transferred without a certificate indicating the last test date for leakage and/or contamination.

TRS 13.7.4.4 Test each startup source and fission detector for 31 days prior to leakage and/or contamination. being subjected to core flux or installed in the core

AND

Following repair or maintenance

Turkey Point Unit 3 and Unit 4 13.7.4-2 Revision 0 Sealed Source Contamination 13.7.4

SUPPORT FUNCTION

Sealed sources are not required support functions for any TS system.

BASES

The limitations on removable contamination for s ources requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(a)(3) limits fo r plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.

Sealed sources are classified into three groups a ccording to their use, with test requirements commensurate with the probability of damage to a source in that group. Those sources which are frequently handled are required to be tested more often than those which are not. Sealed sources which are continuously enclosed within a shielded mechanism (i.e., sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

Testing of sealed sources shall be performed by the licensee or other persons specifically authorized by the Commission or an Agreement State. The test method must have a detection sensitivity of 0.005 µCurie per test sample.

Turkey Point Unit 3 and Unit 4 13.7.4-3 Revision 0 EDG Fuel Oil 13.8.1

13.8 ELECTRICAL POWER SYSTEMS

13.8.1 Emergency Diesel Generator (EDG) Fuel Oil

TR 13.8.1 The EDG Fuel Oil Supply System shall be FUNCTIONAL.

APPLICABILITY: When associated EDG is required to be OPERABLE.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. EDG Fuel Oil Supply A.1 Enter TR 13.0.3. IMMEDIATELY System nonfunctional.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.8.1.1 Verifying the fuel transfer pump transfers fuel from 18 months the fuel storage tank (Unit 3) and fuel storage tanks (Unit 4) to the day tanks of each EDG associated with the unit via the installed cross-connection line.

TRS 13.8.1.2 Drain and clean each EDG fuel oil storage tank. 10 years

TRS 13.8.1.3 ------------------------------NOTE-----------------------------

Only applicable to Unit 4.

Perform a pressure test of the portions of the EDG 10 years Fuel Oil Supply System designed to Section III, subsection ND of the ASME Code in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

Turkey Point Unit 3 and Unit 4 13.8.1-1 Revision 0 EDG Fuel Oil 13.8.1

SUPPORT FUNCTION

The EDG Fuel Oil Supply System supports TSs 3.8.1, 3.8.2, and 3.8.3.

BASES

None.

Turkey Point Unit 3 and Unit 4 13.8.1-2 Revision 0 480 V LCs and MCCs - Operating 13.8.2

13.8 ELECTRICAL POWER SYSTEMS

13.8.2 480 V Load Centers (LCs) and Motor Control Centers (MCCs) - Operating

TR 13.8.2 Vital sections of Train A and B unit MCCs shown in TRM Table 13.8.2-1 (Unit 3) and Table 13.8.2-2 (Unit 4) shall be FUNCTIONAL.

AND

Train A or Train B opposite unit 480 V LCs and vital sections of MCCs shown in TRM Table 13.8.2-1 (Unit 3) and Table 13.8.2-2 (Unit 4) shall be FUNCTIONAL.

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

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more required A.1 Declare Technical IMMEDIATELY unit MCC vital sections Specification required nonfunctional. features supported by the nonfunctional MCC vital sections inoperable.

AND

A.2 Restore vital sections of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months MCCs to FUNCTIONAL status.

B. One or more required B.1 Declare Technical IMMEDIATELY opposite unit 480 V LCs Specification required or vital sections of features supported by the MCCs nonfunctional. nonfunctional LCs or vital sections of MCCs inoperable.

AND

B.2 Restore 480 V LCs and 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months vital sections of MCCs to FUNCTIONAL status.

Turkey Point Unit 3 and Unit 4 13.8.2-1 Revision 0 480 V LCs and MCCs - Operating 13.8.2

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

C. Required Action and C.1 Enter TR 13.0.3. IMMEDIATELY associated Completion Time not met.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.8.2.1 Verify correct breaker alignments and voltage to 7 days required 480 V LCs and MCCs.

Turkey Point Unit 3 and Unit 4 13.8.2-2 Revision 0 480 V LCs and MCCs - Operating 13.8.2

TRM Table 13.8.2-1 (page 1 of 1)

Unit 3 480 LCs and MCCs

TRAIN A TRAIN B

Load Centers Load Centers 4A, 4C, 4H(a) 4B, 4D, 4H(a)

MCCs MCCs 3C, 3D(a)(b)(c) 3B, 3D(a)(b)(c) 4C, 4D(a) 4B, 4D(a)

(a) Swing load center bus and associated MCC can be aligned to either train.

(b) Automatic transfer capability must be available to the other AC electrical power distribution train for the swing load center and associated MCC to be FUNCTIONAL.

(c) Associated swing load center is required by LCO 3.8.9, "Distribution Systems -

Operating."

Turkey Point Unit 3 and Unit 4 13.8.2-3 Revision 0 480 V LCs and MCCs - Operating 13.8.2

TRM Table 13.8.2-2 (page 1 of 1)

Unit 4 480 LCs and MCCs

TRAIN A TRAIN B

Load Centers Load Centers 3A, 3C, 3H(a) 3B, 3D, 3H(a)

MCCs MCCs 4A, 4C, 4D(a)(b)(c) 4B, 4D(a)(b)(c) 3C, 3D(a) 3B, 3D(a)

(a) Swing load center bus and associated MCC can be aligned to either train.

(b) Automatic transfer capability must be available to the other AC electrical power distribution train for the swing load center and associated MCC to be FUNCTIONAL.

(c) Associated swing load center is required by LCO 3.8.9, "Distribution Systems -

Operating."

Turkey Point Unit 3 and Unit 4 13.8.2-4 Revision 0 480 V LCs and MCCs - Operating 13.8.2

SUPPORT FUNCTION

The 480 LCs and MCCs support various TS-requir ed structures, systems, and components.

BASES

The FUNCTIONALITY of the 480 V load centers (LCs) and motor control centers (MCCs) ensure that sufficient power will be available to supply the safety-related equipment required for (1) the safe shutdown of the facility, and (2) the mitigation and control of accident conditions within the facility.

The 480 LCs and MCCs listed in TRM Tables 13.8.2-1 (Unit 3) and 13.8.2-2 (Unit 4) provide power to selected Technical Specification required features. Should one or more of the LC or MCC buses become nonfunctional due to a failure not affecting the OPERABILITY of a bus listed in Technical Specification Bases Table B 3.8.9-1 (Unit 3) or Table B 3.8.9-2 (Unit 4) (e.g.,

a breaker supplying a single distribution panel fails open), the individual Technical Specification required loads on the bus must be declared inoperable, and the appropriate Conditions and Required Actions of the LCOs governing the individual loads must be entered in accordance with Technical Specification LCO 3.0.2.

The ACTION requirements specified for the nonfunctionality of certain MCCs and LCs provide restrictions commensurate with the level of degradation on each unit and the amount of time one could reasonably diagnose and correct a minor problem. The level of degradation is based upon the types of equipment powered and the out-of-service limit imposed on that equipment by the associated ACTION statement. With one or more required unit MCC vital sections nonfunctional, then a Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is applied to the associated unit. For one or more opposite unit 480 V LCs or vital sections of MCCs nonfunctional, a Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is applied.

The unit MCCs support Technical Specification required features. Opposite unit LCs and MCCs provide support to selected Technical Specification required features necessary to meet Limiting Condition for Operation (LCO) 3.5.2, "ECCS - Operating," LCO 3.7.10, "Control Room Emergency Ventilation System (CREVS)," LC O 3.7.11, "Control Room Emergency Air Temperature Control System (CREATCS)," and LCO 3.8.4, "DC Sources - Operating."

Turkey Point Unit 3 and Unit 4 13.8.2-5 Revision 0 Battery Chargers - Parallel Operation 13.8.3

13.8 ELECTRICAL POWER SYSTEMS

13.8.3 Battery Chargers - Parallel Operation

TR 13.8.3 Each connected battery charger shall supply 10 amperes to associated DC bus.

APPLICABILITY: When DC bus is required to be OPERABLE and associated battery chargers are operating in parallel.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Battery charger A.1 Demonstrate that the Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months operating in parallel battery charger supplying connected to a single < 10 amperes will accept battery bank supplying and supply the DC bus

< 10 amperes to the load independent of its battery bank. associated battery charger.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.8.3.1 ------------------------------NOTE-----------------------------

Only applicable to battery chargers operating in parallel connected to a single battery bank.

Verify each battery charger is supplying 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 10 amperes to the associated battery bank.

Turkey Point Unit 3 and Unit 4 13.8.3-1 Revision 0 Battery Chargers - Parallel Operation 13.8.3

SUPPORT FUNCTION

Battery chargers support TSs 3.8.4 and 3.8.5.

BASES

None.

Turkey Point Unit 3 and Unit 4 13.8.3-2 Revision 0 Communications 13.9.1

13.9 REFUELING OPERATIONS

13.9.1 Communications

TR 13.9.1 Direct communications shall be maintained between the control room and personnel at the refueling station.

APPLICABILITY: During movement of fuel, sources, or reactivity control components in the reactor vessel.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Required A.1 Suspend movement of fuel, IMMEDIATELY communications not sources, and reactivity maintained. control components in the reactor vessel.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.9.1.1 Verify direct communications between the control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to room and personnel at the refueling station. movement of fuel, sources, or reactivity control components in the reactor vessel

AND

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter

Turkey Point Unit 3 and Unit 4 13.9.1-1 Revision 0 Communications 13.9.1

SUPPORT FUNCTION

Refueling communications are not required support functions for any TS system.

BASES

The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during movement of fuel, sources, and reactivity control components in the reactor vessel.

Turkey Point Unit 3 and Unit 4 13.9.1-2 Revision 0 Manipulator Cranes 13.9.2

13.9 REFUELING OPERATIONS

13.9.2 Manipulator Cranes

TR 13.9.2 a. The manipulator crane shall be FUNCTIONAL with:

1) A minimum capacity of 2750 pounds, and

2) An overload cutoff limit 2700 pounds.

b. The auxiliary hoist shall be FUNCTIONAL with:

1) A minimum capacity of 610 pounds, and

2) A load indicator used to prevent lifting loads in excess of 600 pounds.

APPLICABILITY: During movement of drive rods or fuel assemblies in the reactor vessel.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Manipulator crane A.1 Suspend use of IMMEDIATELY nonfunctional. manipulator crane from operations involving the movement of fuel assemblies in the reactor vessel.

B. Auxiliary hoist B.1 Suspend use of auxiliary IMMEDIATELY nonfunctional. hoist from operations involving the movement of drive rods in the reactor vessel.

Turkey Point Unit 3 and Unit 4 13.9.2-1 Revision 0 Manipulator Cranes 13.9.2

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.9.2.1 Perform a manipulator crane load test of Within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months 2750 pounds, demonstrating an automatic load prior to the start of cutoff prior to exceeding 2700 pounds. the movement of fuel assemblies in the reactor vessel

TRS 13.9.2.2 Perform an auxiliary hoist load test of 610 pounds. Within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of the movement of drive rods in the reactor vessel

Turkey Point Unit 3 and Unit 4 13.9.2-2 Revision 0 Manipulator Cranes 13.9.2

SUPPORT FUNCTION

The manipulator crane is not required support functions for any TS system.

BASES

The requirements for the manipulator cranes ensure that: (1) manipulator cranes will be used for movement of drive rods and fuel assemblies, (2) each crane has sufficient load capacity to lift a drive rod or fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

The requirement that the auxiliary hoist load indicator be used to prevent lifting excessive loads will require a manual action. The auxiliary hoist load indicator does not include any automatic mechanical or electrical interlocks that prevent lifting loads in excess of 600 pounds.

Turkey Point Unit 3 and Unit 4 13.9.2-3 Revision 0 Decay Time 13.9.3

13.9 REFUELING OPERATIONS

13.9.3 Decay Time

TR 13.9.3 The reactor shall be subcritical for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

APPLICABILITY: During movement of irradiated fuel in the reactor vessel.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. Reactor subcritical A.1 Suspend movement of IMMEDIATELY

< 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . irradiated fuel assemblies in the reactor vessel.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.9.3.1 Verify reactor has been subcritical for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . Prior to movement of irradiated fuel in the reactor vessel

Turkey Point Unit 3 and Unit 4 13.9.3-1 Revision 0 Decay Time 13.9.3

SUPPORT FUNCTION

The minimum decay time is not a required support function for any TS system.

BASES

The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of short-lived fission products. This decay time is consistent with the assumptions used in the safety analyses, and ensures that the release of fission product radioactivity, subsequent to a fuel handling accident, results in doses that are well within the values specified in 10 CFR 50.67 and RG 1.183.

This TS is applicable during movement of recently irradiated fuel assemblies within containment. Recently irradiated fuel is defined as fuel that has occupied part of a critical reactor core within the previous 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . However, the administrative controls as well as the inherent delay associated with completing the required preparatory steps for moving fuel in the reactor vessel will ensure that the proposed 72-hour decay time will be met prior to removing irradiated fuel from the reactor vessel for a refueling outage. The FHA is a postulated event that involves damage to irradiated fuel. The in-containment FHA involves dropping a single irradiated fuel assembly, resulting in damage to a single fuel assembly. The 72-hour required decay time before moving fuel in containment ensures that sufficient time has elapsed to allow the radioactive decay of short-lived fission products.

Turkey Point Unit 3 and Unit 4 13.9.3-2 Revision 0 RHR Flow Indicator 13.9.4

13.9 REFUELING OPERATIONS

13.9.4 Residual Heat Removal (RHR) Flow Indicator

TR 13.9.4 The RHR flow indicator shall be FUNCTIONAL.

APPLICABILITY: MODE 6, with the water level 23 feet above the top of the reactor vessel flange.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. RHR flow indicator A.1 Enter TR 13.0.3. IMMEDIATELY nonfunctional.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.9.4.1 Perform CHANNEL CALIBRATION. 18 months

Turkey Point Unit 3 and Unit 4 13.9.4-1 Revision 0 RHR Flow Indicator 13.9.4

SUPPORT FUNCTION

The RHR flow indicator supports TSs 3.9.5 and 3.9.6.

BASES

None.

Turkey Point Unit 3 and Unit 4 13.9.4-2 Revision 0 Spent Fuel Pit Metamic Inserts 13.9.5

13.9 REFUELING OPERATIONS

13.9.5 Spent Fuel Pit Metamic Inserts

TR 13.9.5 The spent fuel pit Metamic inserts shall be FUNCTIONAL.

APPLICABILITY: When fuel is stored in the spent fuel pit.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more inservice A.1 Enter TR 13.0.3. IMMEDIATELY Metamic inserts nonfunctional.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.9.5.1 Visually inspect a representative sample of In accordance with inservice Metamic inserts. the UFSAR Metamic Insert Surveillance Program

Turkey Point Unit 3 and Unit 4 13.9.5-1 Revision 0 Spent Fuel Pit Metamic Inserts 13.9.5

SUPPORT FUNCTION

The Metamic inserts supports TS 3.7.14.

BASES

The surveillance program ensures that the performance requirements of Metamic are met over the surveillance interval.

Turkey Point Unit 3 and Unit 4 13.9.5-2 Revision 0 Explosive Gas 13.11.1

13.11 RADIOLOGICAL EFFLUENTS

13.11.1 Explosive Gas

TR 13.11.1 The concentration of oxygen in the Gas Decay Tank System as measured in the in-service gas decay tank shall be limited to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

AND

One explosive gas hydrogen monitor and one explosive gas oxygen monitor shall be FUNCTIONAL.

APPLICABILITY: During Gas Decay Tank System operation.

ACTIONS

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

Separate Condition entry is allowed for each explosive gas monitor.

CONDITION REQUIRED ACTION COMPLETION TIME

NOTE------------ A.1 Analyze grab samples Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Only applicable during for hydrogen and degassing operations. oxygen concentration.

AND A. Less than the minimum number of explosive A.2 Restore explosive gas 30 days gas monitors monitor(s) to FUNCTIONAL. FUNCTIONAL status.

NOTE------------- B.1 Analyze grab samples for Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Only applicable during hydrogen and oxygen non-degassing Gas Decay concentration.

Tank System operations.

AND

B. Less than the minimum B.2 Restore explosive gas 30 days number of explosive monitor(s) to gas monitors FUNCTIONAL status.

FUNCTIONAL.

Turkey Point Unit 3 and Unit 4 13.11.1-1 Revision 0 Explosive Gas 13.11.1

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME

C. In-service gas decay C.1 Reduce in-service gas 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months tank oxygen decay tank oxygen concentration > 2% by concentration to 2%.

volume and 4% by volume.

D. In-service gas decay D.1 Suspend addition of waste IMMEDIATELY tank oxygen gases to gas decay tank.

concentration > 4% by volume. AND

AND D.2 Reduce gas decay tank IMMEDIATELY oxygen concentration to In-service gas decay 4%.

tank hydrogen concentration > 4% by volume.

E. Required Action and E.1 Enter TR 13.0.3. IMMEDIATELY associated Completion Time not met.

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.11.1.1 Perform CHANNEL CHECK of required explosive 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months gas monitors.

TRS 13.11.1.2 Perform COT of required explosive gas monitors. 31 days

TRS 13.11.1.3 Perform CHANNEL CALIBRATION of required 92 days explosive gas monitors.

Turkey Point Unit 3 and Unit 4 13.11.1-2 Revision 0 Explosive Gas 13.11.1

SUPPORT FUNCTION

The explosive gas limits are not required support functions for any TS system.

BASES

The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The Alarm/Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the Offsite Does Calculation Manual (ODCM) to ensure that the alar m/trip will occur prior to exceeding the limits of 10 CFR Part 20. With an explosive gas monitoring instrumentation channel Alarm/Trip Setpoint less conservative than required by TR 3.11.1, the channel is nonfunctional.

This instrumentation also includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in t he Gas Decay Tank System. The FUNCTIONALITY and use of this instrumentation are consistent with the requirements of General Design Criteria (GDC) 60, 63, and 64 of to 10 CFR 50, Appendix A.

TR 3.11.1 also ensures that the concentration of potentially explosive gas mixtures contained in the Gas Decay Tank System (as measured in the in-service gas decay tank) is maintained below the flammability limits of hydrogen and oxygen. T h e e x p l o s i v e g a s m o n i t o r s continuously monitor the hydrogen and oxygen concentrations of the in-service gas decay tank. Maintaining the concentration of hydrogen and oxygen below the flammability limits provides assurance that the releases of radioa ctive materials will be controlled in conformance with the requirements of 10 CFR 50, Appendix A, GDC 60.

The CHANNEL CALIBRATION of the hydrogen monitor shall include the use of standard gas samples containing a nominal:

a. One volume percent hydrogen, balance nitrogen, and

b. Four volume percent hydrogen, balance nitrogen.

The CHANNEL CALIBRATION of the oxygen monitor shall include the use of standard gas samples containing a nominal:

a. One volume percent oxygen, balance nitrogen, and

b. Four volume percent oxygen, balance nitrogen.

Turkey Point Unit 3 and Unit 4 13.11.1-3 Revision 0 Gas Decay Tanks 13.11.2

13.11 RADIOLOGICAL EFFLUENTS

13.11.2 Gas Decay Tanks

TR 13.11.2 The quantity of radioactivity contained in each gas decay tank shall be limited to 70,000 curies of noble gases (DOSE EQUIVALENT Xe-133).

APPLICABILITY: At all times.

ACTIONS

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

Separate Condition entry is allowed for each gas decay tank.

CONDITION REQUIRED ACTION COMPLETION TIME

A. Gas decay tank A.1 Suspend additions of IMMEDIATELY radioactivity quantity radioactive material to not within limit. affected tank.

AND

A.2 Reduce the quantity of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months radioactivity within the affected tank to within limit.

AND

A.3 Include a description of the In accordance with event in the next Technical Radioactive Effluent Specification 5.6.2, Release Report. "Radioactive Effluent Release Report"

Turkey Point Unit 3 and Unit 4 13.11.2-1 Revision 0 Gas Decay Tanks 13.11.2

TECHNICAL REQUIREMENT SURVEILLANCES

SURVEILLANCE FREQUENCY

TRS 13.11.2.1 ----------------------------NOTES----------------------------

Only applicable when Radioactive materials are being added to a gas decay tank and Reactor Coolant System specific activity exceeds the limits of Technical Specification 3.4.16, "RCS Specific Activity."

Determine the quantity of radioactive material 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months contained in each gas decay tank is within limit.

Turkey Point Unit 3 and Unit 4 13.11.2-2 Revision 0 Gas Decay Tanks 13.11.2

SUPPORT FUNCTION

The quantity of radioactivity contained in each gas decay tank supports maintaining the limits of TS 5.5.3, "Radioactive Effluent Controls Program."

BASES

Restricting the quantity of radioactivity contained in each Gas Decay Tank provides assurance that in the event of an uncontrolled release of the tank's contents, the resulting whole body exposure to a MEMBER OF THE PUBLIC at the nearest SITE BOUNDARY will not exceed 0.1 rem.

Turkey Point Unit 3 and Unit 4 13.11.2-3 Revision 0 Unit Staff 15.1.1

15.0 ADMINISTRATIVE CONTROLS

TR 15.1.1 Unit Staff

The unit staff organization shall include the following:

a. Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 15.1.1-1;

b. At least two licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips. In addition, while either unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Operator shall be in the control room; and

c. With fuel in the reactor pressure vessel (RPV), the movement of fuel, sources, or reactivity control components in the RPV shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.

TABLE 15.1.1-1 Minimum Shift Composition

POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION

One Unit in MODE 1, 2, 3, or 4 Both Units in AND Both Units in MODE 5 or 6, or One Unit in MODE 5 MODE 1, 2, 3, or 4 Defueled or 6, or Defueled

SM 1 1 1 SRO 1 None(b) 1 RO 3(a) 2(a) 3(a)

SM - Shift Manager with a Senior Operator license SRO - Individual with a Senior Operator license RO - Individual with an Operator license

(a) At least one of the required individuals must be assigned to the designated position for each unit.

(b) At least one licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling must be present during the movement of fuel, sources, or reactivity control components in the RPV when fuel is in the RPV on either unit, who has no other concurrent responsibilities.

Turkey Point Unit 3 and Unit 4 15.1.1-1 Revision 0 Snubber Testing Program 15.1.2

15.0 ADMINISTRATIVE CONTROLS

TR 15.1.2 Snubber Testing Program

This program conforms to the examination, testing and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR 50.55a inservice inspection (lSI) requirements for supports. The program shall be in accordance with the following:

a. This program shall meet 10 CFR 50.55a(g) lSI requirements for supports.

b. The program shall meet the requirements for lSI of supports set forth in subsequent editions of the Code of Record and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV)

Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR 50.55a(a) subject to the use and conditions on the use of standards listed in 10 CFR 50.55a(b) and subject to Commission approval.

c. The program shall, as required by 10 CFR 50.55a(b)(3)(v), meet Subsection ISTA, "General Requirements" and Subsection ISTD, "Preservice and lnservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants".

d. The 120-month program updates shall be made in accordance with 10 CFR 50.55a(g)(4), 10 CFR 50.55a(g)(3)(v) and 10 CFR 50.55a(b)

(including 10 CFR 50.55a(b)(3)(v)) subject to the conditions listed therein.

Turkey Point Unit 3 and Unit 4 15.1.2-1 Revision 0

ML24135A083

Text

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